Generic assessment procedures for determining protective actions during a reactor accident

Transcription

1 IAEA-TECDOC-955 Generic assessment procedures for determining protective actions during a reactor accident INTERNATIONAL ATOMIC ENERGY AGENCY

2 The IAEA does not normally maintain stocks of reports in this series However, microfiche copies of these reports can be obtained from INIS Clearinghouse International Atomic Energy Agency Wagramerstrasse

3 The originating Section of this publication in the IAEA was: Radiation Safety Section International Atomic Energy Agency Wagramerstrasse

4 One FOREWORD

5 EDITORIAL NOTE In preparing this publication for press, staff of the IAEA have made up the pages from the original manuscripts). The views expressed do not necessarily reflect those of the governments of the nominating Member States or of the nominating organizations. Although great care

6 CONTENTS INTRODUCTION...

7 Table Ol Assessment priorities Table Al Accident classification the operating, standby and hot shutdown mode Table

8 WORKSHEETS Worksheet

9 INTRODUCTION The aim of this publication is to provide practical guidance and tools for accident assessment that,

10 OBJECTIVES

11 STRUCTURE The manual is organized in sections based on proposed assessment organization and in the order that assessments most likely will be performed. Each section contains methods, that are standalone procedures. Sections start with

12 SECTION O ACCIDENT ASSESSMENT MANAGER PROCEDURES Caution: The procedures in this section must be revised to reflect local and plant conditions

13 Performed

14 Accident Assessment Procedure Ol Pg. 2 of 3 Accident Assessment Manager

15 TABLE

16 SECTION

17 Performed

18 Performed

19 Nuclear Condition Assessment Procedure

20 TABLE Al ACCIDENT CLASSIFICATION THE OPERATING, STAND-BY OR HOT SHUTDOWN MODE

21 TABLE Al ACCIDENT CLASSIFICATION THE OPERATING, STAND-BY OR HOT SHUTDOWN MODE For the following accident entry conditions: Declare

22 TABLE Al ACCIDENT CLASSIFICATION THE OPERATING, STAND-BY OR HOT SHUTDOWN MODE

23 TABLE

24 to do TABLE

25 TABLE

26 U) o TABLE Al ACCIDENT CLASSIFICATION THE OPERATING, STAND-BY OR HOT SHUTDOWN MODE

27 TABLE A1 ACCIDENT CLASSIFICATION THE OPERATING, STAND-BY OR HOT SHUTDOWN MODE

28 to TABLE A1 ACCIDENT CLASSIFICATION THE OPERATING, STAND-BY OR HOT SHUTDOWN MODE For the following accident entry conditions; Unplanned increase in plant radiation levels Declare a General Emergency if: Multiple plant radiation monitors show an unplanned or unpredicted increase by a factor High ambient dose rates beyond the site boundary.

29 TABLE Al ACCIDENT CLASSIFICATION THE OPERATING. STAND-BY OR HOT SHUTDOWN MODE

30 TABLE

31 Nuclear Condition Assessment Procedure Al Pg. 14 of 24 TABLE

32 TABLE

33 TABLE A2 ACCIDENT CLASSIFICATION FOR COLD SHUTDOWN OR REFUELLING

34 TABLE

35 TABLE

36 P". o TABLE A2 ACCIDENT CLASSIFICATION FOR COLD SHUTDOWN OR REFUELLING For the following accident entry conditions: Confirmed

37 TABLE

38 K) TABLE

39 Nuclear Condition Assessment Procedure Al Pg. 22 of 24 FIGURE Al COOLING MARGIN - SATURATION CURVE Discussion A primary system temperature greater than

40 Nuclear Condition Assessment Procedure Al Pg. 23 of 24 FIGURE A2 INJECTION REQUIRED

41 Nuclear Condition Assessment Procedure

42 Performed, by: Nuclear Condition Assessment Manager ASSESSMENT PROCEDURE A2

43 Performed

44 Nuclear Condition Assessment Procedure

45 Nuclear Condition Assessment Procedure

46 Performed by: Nuclear Condition Assessment Manager PROCEDURE A2b CORE DAMAGE ASSESSMENT BASED ON CONTAINMENT RADIATION LEVELS Pg.

47 Nuclear Condition Assessment Procedure Alb Pg. 2 of [MW(th)} where: damge X ṁonitor Normalized monitor reading [mgy/h] from table A4. Estimated monitor reading [msv/h] to be used in assessment of actual readmg Volume p plant SF

48 Nuclear Condition Assessment Procedure A2b Pg. 3 of 9 FIGURE A3 LARGE PWR CONTAINMENT MONITOR It is assumed that the release from the core is uniformly mixed in the containment; the monitor

49 Nuclear Condition Assessment Procedure

50 Nuclear Condition Assessment Procedure

51 Nuclear Condition Assessment Procedure A2b Pg. 6 of 9 FIGURE A6

52 Nuclear Condition Assessment Procedure

53 Nuclear Condition Assessment Procedure

54 Nuclear Condition Assessment Procedure A2b Pg. 9 of 9 It FIGURE A9 WWER-213 CONTAINMENT MONITOR

55 Performed by: Nuclear Condition Assessment Manager PROCEDURE

56 Nuclear Condition Assessment Procedure A2c Pg. 2 of 3 For other reactors with primary system coolant inventories considerably different from 2.5xl0

57 Nuclear Condition Assessment Procedure A2cPg. 3 of 3 TABLE

58 Performed by: Nuclear Condition Assessment Manager PROCEDURE A2d SPENT FUEL DAMAGE ASSESSMENT Pg.

59 Performed by: Nudear Condition Assessment Manager PROCEDURE A3 ASSESSMENT OF RELEASE ROUTES AND CONDITIONS Pg. Iof4 Purpose:

60 Nuclear Condition Assessment Procedure A3 Pg. 2 of 4 TABLE A7 RELEASE ROUTE EVALUATION GUIDE Possible Routes Release from the containment: Release out of primary system through the containment to the atmosphere. Indicators Core melts until core has been recovered with water

61 Nuclear Condition Assessment Procedure A3 Pg. 3 of 4 TABLE

62 Nuclear Condition Assessment Procedure A3 Pg. 4 of 4 TABLE

63 SECTION

64 Performed by: Protective Action. Manager PROCEDURE

65 Protective Action Assessment Procedure Bl Pg. 2 of 9 Step 5 After the threat of a major release is over and the composition of the deposition has been fully characterized, request

66 Protective Action Assessment Procedure

67 Protective Action Assessment Procedure Bl Pg. 4 of 9 TABLE B1 PROTECTIVE ACTIONS BASED ON CLASSIFICATION Protective actions (a) Evacuate

68 Protective Action Assessment Procedure Bl Pg. 5 of 9 TABLE B2 PUBLIC PROTECTIVE ACTIONS BASED ON PROJECTIONS AND IN PLUME MEASUREMENTS Projections BASIS Ambient dose rate

69 -J TABLE

70 TABLE

71 OIL # Default value A-Protective action B-Defmition C-Summary

72 Protective Action Assessment TABLE

73 Caution: SECTION C RADIATION PROTECTION MANAGER PROCEDURES

74 Performed

75 Radiation Protection Procedure

76 SECTION D ENVIRONMENTAL ANALYST PROCEDURES Caution: The procedures in this section must be revised to reflect local and plant conditions for which they will be applied. NEXT PAGE(S)

77 Performed by: Environmental Analyst PROCEDURE Dl ENVIRONMENTAL ASSESSMENT Page 1 of 3 Purpose To manage environmental monitoring. Discussion The measurements are arranged by priorities the results are needed in case of an accident, so do not change the order. Input > Accident class from Worksheet

78 oo ON TABLE

79 TABLE

80 Caution: SECTION E PROJECTION ANALYST PROCEDURES

81 Performed

82 Projected Protective Action Distances Procedure EO Pg. 2 of 2 Step 3 Ensure Worksheet

83 Performed by: Projection Analyst PROCEDURE El PROJECTED URGENT PROTECTIVE ACTION DISTANCES BASED ON PLANT CONDITIONS Pg.lofl Purpose To estimate urgent protective action distances based

84 Performed by: Projection Analyst PROCEDURE Ela RELEASE FROM THE CONTAINMENT Pg. 1 of 5 Purpose To estimate protective action distances for a release which passes through the primary system and through

85 Projected Protective Action Distances Procedure

86 Projected Protective Action Distances Procedure Ela Pg. 3 of 5 FIGURE E2 Projected Urgent Protective Action Distances for RELEASE FROM

87 Projected Protective Action Distances Procedure El a Pg. 4 of 5 FIGURE E3 Projected Urgent Protective Action Distances for RELEASE FROM

88 Projected Protective Action Distances Procedure

89 Performed by: Projection Analyst PROCEDURE

90 Projected Protective Action Distances Procedure Elb Pg. 2 of 3 FIGURE E5 Projected Urgent Protective Action Distances for CONTAINMENT BY-PASS UNDER DRY CONDITIONS

91 Projected Protective Action Distances Procedure Elb Pg. 3 of 3 FIGURE E6 Projected Urgent Protective Action Distances

92 Performed

93 Projected Protective Action Distances Procedure

94 Projected Protective Action Distances Procedure

95 Performed

96 Projected Protective Action Distances Procedure

97 Performed by:. Projection Analyst PROCEDURE E2 PROJECTED URGENT PROTECTIVE ACTION DISTANCES BASED

98 Projected Protective Action Distances Procedure E2 Pg. 2 of 2 FIGURE E10 Projected Urgent Protective Action Distances based

99 Performed

100 Projected Protective Action Distances Procedure

101 SECTION

102 Performed

103 Performed by: Sample Analyst PROCEDURE Fl REVISION OF PLUME EXPOSURE OILs AND EMERGENCY WORKER TURN BACK GUIDANCE

104 Sample Analysis Procedure

105 Sample Analysis Procedure Fl Pg. 3 of 5 Step 6 Recalculate

106 Sample Analysis frocedure Fl Pg. 4 of 5 TABLE F1 INHALATION DOSE RATE CONVERSION FACTORS Discussion:

107 Sample Analysis Procedure

108 Performed

109 Sample Analysis Procedure

110 Sample Analysis Procedure F2 Pg. 3 of 6 TABLE

111 Sample Analysis Procedure F2 Pg. 4 of 6 TABLE F5 DOSE AND DOSE RATE CONVERSION FACTORS FOR EXPOSURE TO GROUND CONTAMINATION Discussion: This contains dose conversion factors (CF) for the first, second month and 50 year periods of exposure to ground contamination. Decay, ingrowth and weathering have been considered. The

112 Sample Analysis Procedure F2 Pg. 5 of 6 Radionuclide Ru-106

113 Sample Analysis Procedure

114 Performed

115 Sample Analysis Procedure F3 Pg. 2 of 3 Step 1 Using Worksheet F3 recalculate OIL6 and OIL? for both and Cs-137 for groups 1 and 2 for the

116 Sample Analysis Procedure

117 Performed by: Sample Analyst PROCEDURE

118 Sample Analysis TABLE

119 Sample Analysis Procedure

120 Sample Analysis Procedure F4 Pg. 4 of 8 TABLE F8 REDUCTION FACTORS FOR PROCESSING OR FILTERING for FOOD Discussion: Processing

121 Sample Analysis Procedure

122 Sample Analysis Procedure F4 Pg. 6 of 8 Element Caesium Food Meat Fish Mushrooms boiling bones frying wet salting dry salting pickling boiling frying cleaning Preparation Berries Strontium Spinach Cabbage Green beans Tomatoes Onions Potatoes Carrots Beets Cereals Rye Rice Milk

123 Sample Analysis Procedure

124 Sample Analysis Procedure F4 Pg. 8 of 8 TABLE F9 IAEA TOTAL EFFECTIVE DOSE GUIDANCE FOR EMERGENCY WORKERS TASKS Type

125 Performed by: Sample Analyst EVALUATION PROCEDURE F5

126 Sample Analysis Procedure

127 WORKSHEETS Caution: The worksheets hi this section must be revised to reflect local and plant conditions for which they will be applied. NEXT PAQE(S) I ( ft BLANK

128 Performed

129 Performed ;by; Itfudear CawMon Assessment Manager FLANT- ON1>I11 N ASSESSMENT No: Prepared

130 Performed by: Protective Action Manager WORKSHEET Bl EVACUATION, THYROID BLOCKING/ SHELTER

131 Performed by: Protective Action Manager WORKSHEET B2 FOOD EVALUATION AND RESTRICTION MAP No: Prepared by: (full name) Provide copies

132 Performed by: Environmental Analyst WORKSHEET Dl AMBIENT DOSE RATE AROUND THE PLANT No: Survey Team: (names) Provide copies to: L-l Radiation Protection Manager Date: I I Protective Action Manager D Projection Analyst Survey monitor: Sector Distance [km] Time Weather: Ambient Dose Rate [msv/h] Remark Open Window Close Window A B C D E F G H J K L M N P R S Record die highest ambient dose rate for the opened and closed probe window within each sector, the distance from the plant and the time measurement was taken. These measurements should be made within 1-2 km zone around

133 Performed by: Environmental Analyst WORKSHEET D2 NEAR-HELD AMBIENT DOSE RATE MAP [msv/h] No: Prepared

134 Performed

135 Performed

136 Prepared Performed by: Environmental Analyst WORKSHEET D5 NEAR-FIELD MARKER ISOTOPE DEPOSITION CONCENTRATION MAP No:

137 Performed

138 Performed

139 Performed by: Samp le Analyst RESULTS FROM WORKSHEET D8

140 Performed by: Projection Analyst Prepared WORKSHEET El PROJECTED PROTECTIVE ACTION DISTANCES No:

141 Performed by: WORKSHEET Sample Analyst

142 Performed by: Sample Analyst WORKSHEET

143 Performed

144 Performed by: Sample Analyst WORKSHEET

145 APPENDICES NEXT PAGE(S) left BLANK

146 Appendix I Assumptions Appendix

147 Appendii

148 Appendix I OEL2: Take thyroid blocking agent based

149 Appendix

150 Appendix I Assumptions where: Y r productivity; assume RF u,cow ff f m, OIL6 OIL7 GAL G ^g, j, core melt ^i, G, core melt

151 Appendix

152 Appendix I Assumptions Core

153 Appendix

154 Appendix I Assumptions TABLE IB: PWR Typical Normal Coolant Concentrations NndkJe H-3 Mn-54 Co-58 Co-60 Kr-85 Kr-85m Kr-87 Kr-88 Sr-89 Sr-90 Sr-91 Y-91 Mo-99 Tc-99 Ru-103 Ru-106 Te-129m Te-131m Te-132 Sb-127 Sb Xe-131m Xe-133 Xe-133m Xe-135 Xe-138 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-144 Np-239 Source: ANSI84 Normal Coacentratioa [kbq/g] 3.70E E E E E E E-KX) 1.04E E E E E E E E E E E E E E E E E-HX) 2.70E E-K)! 2.59E-HK) 3.15E-H)! 4.44E E E E E E E E

155 Appendix I Assumptions TABLE 1C: BWR Typical Normal Coolant Concentrations Nndide H-3 Mn-54 Co-58 Co-60 Kr-85 Kr-85m Kr-87 Kr-88 Sr-89 Sr-90 Sr-9I Y-91 Mo-99 Tc-99 Ru-103 Ru-106 Te-129m Te-131m Te-132 Sb-127 Sb Xe-131m Xe-133 Xe-133m Xe-135 Xe-138 Cs-134 Cs-136 Cs-137 Ba-140 La-140 Ce-I44 Np-239 Source: ANS184 Normal Coacoitratioa [IcBq/fe] 3.70B E E E E E E E E E E E E E E-04 O.OOE+00 O.OOE E E E-01 I.59E E-01 O.OOE-KK) O.OOE-KK) O.OOE-KK) O.OOE+00 O.OOE IE E E E E E E

156 Appendix I Assumptions Table ID: Fission Product Inventory (FPI)* Discussion: This lists

157 Appendix

158 Appendix I Table

159 Appendix I Assumptions TABLE IF: System Particulate/Aerosol Release Reduction Factors (RDF) Reduction Mechanism RDF Redaction Factor* assumed for in Section E for the following routes

160 Appendix

161 Appendix I TABLE

162 Appendix I Assumptions Dose Calculation Doses

163 Appendix

164 Appendii I Assumptions Procedures

165 Appendix H InterRAS Model Appendix n InterRAS MODEL (May, 1997 release) INDEX 1. Introduction 2. Running InterRAS 2.1. Getting Started 2.2. Capabilities 2.3. Getting Around The Program with a mouse 2.4. Getting Around without

166 Appendix II IruerRAS Model

167 Appendix

168 Appendix II InterRAS Model help windows

169 Appendix U InlerRAS Model

170 Appendix

171 Appendix

172 Appendix n InterRAS Model 2.5. Exiting InterRAS When

173 Appendix U InterRAS Model Default Units

174 Appendix

175 Appendix

176 Appendix n InterRAS Model 3.2. FM-DOSE Modifications The dose calculations have

177 Appendix II InterRAS Model 4. SETTING RUNTIME OPTIONS 4.1. Configuration File InterRAS uses a configuration file named RASCAL21.CFG to control where files are stored on

178 Appendix II InterRAS Model Describe

179 Appendix II InterRAS Model Problem:

180 Appendix

181 Appendix II InlerRAS Model 6. PROGRAMMING LANGUAGES USED The following software packages and compilers were used in the creation of InterRAS Version 1.1: Microsoft

182 Appendix II InterRAS Model Where: a = result type number (reference b = c = d = e =

183 Appendix D InterRAS Model The format of the file is: result type (integer*2) engineering units (character*3) Cartesian grid array (31,31) (real*4) polar grid array (36,3) (real*4) InterRAS Batch File InterRAS is composed of a number of standalone executable files. The running of theses files in

184 Appendix

185 Appendix

186 Appendix II InterRAS Model R2NUC.DAT File Format

187 Appendix II InterRAS Model DECAY.DAT File Format The ASCE file DECAY.DAT defines the decay matrices of each radionuclide used in the DECAY calculator. A fragment of the file is shown below for illustration. Ti-44 Sc E-10 O.OOE E E-05 <- a <-b <- c The file consists of the following lines: a

188 Appendix II InterRAS Model where:

189 Appendix

190 Appendix II InterRAS Model Messages

191 Appendix

192 Appendix D InterRAS Model Do not edit the RASCAL21.CFG file directly to add a printer. For InterRAS to recognize and use a printer driver it must be properly defined in the RCFG.DAT file. This means that the file must contain

193 Appendix

194 Appendix HI Dose Calculation Appendix

195 Appendix HI Dose Calculation SECTION A CALCULATE URGENT PHASE DOSE (Total Effective Dose,

196 Appendix in Dose Calculation where: R 2 Thyroid dose rate

197 Appendix HI Dose Calculation SECTION

198 Appendix

199 Appendix

200 Appendix in Table ffla: Ingestion dose conversion factors (e(g)) Dose Calculation Nndide H-3 Mn-54 Co-58 Co-60 Rb-87 Rb-88 Sr-89 Sr-90 Sr-91 Y-90 Y-91 Y-91m Zr-95 Nb-95 Mo-99 Tc-99 Tc-99m Ru-103 Ru-106 Rh-106 Sb-127 Sb-129 Te-127 Te-127m Te-129 Te-129m Te-131 Te-131m Te Cs-134 Cs-135 Cs-136 Cs-137 Cs-138 Ba-140 Infant Age 1-2 a [msv/kbq] 120E E E E-02 l.ooe E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E-02 Child Ag*7-12a [msv/kbq] 5.70E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E-02 6J20E E E E E E E-03 l.ooe E E-03 Adult Age>17a (msv/kbq] 4.20E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E

201 Appendix En Dose Calculation Nudide Infant Age La-140 Ce-141 Ce-144 Pr-144 Th-231 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Am241

202 Appendix IV Decay Data Appendix IV RADIOACTIVE HALF-LIVES, DECAY DATA

203 Appendix

204 Appendix

205 Appendix

206 Appendix IV Decay Data Sb-127 (3.85

207 Appendix IV Decay Data (6.61

208 Appendix

209 SYMBOLS Only the symbols that are used in more than one formula or procedure are shown Symbol Br c^ ^before c^ *- table c. c fc, Q, C G Unit m 3 /h kbq/kg or kbq/1 kbq/kg or kbq/1 kbq/g kbq/g kbq/m 3 kfiq/rn 2 kbq/kg or kbq/1 kbq/kg Description Breathing rate Concentration c fj kbq/m 2 CF, (msv/h)/(kbq/m 3 ) CF 2l (msv/h)/(kbq/m 3 ) CF 3l (msv/h)/(kbq/m 2 ) CF 4, (msv)/(kbq/m 2 ) CF 5l DI R mg msv/kbq d msv ET 7 msv msv E, ns msv/h ^ inh msv/h EWG msv

210 Symbol 4 GAL G GIL e Unit (kbq/l)/(kbq/day) kbq/kg msv Description Transfer factor for isotope / from ingestion to cow's milk Food, water or milk concentration Generic Action Level for group G above which food restriction should be considered ( See Table F6 for IAEA recommendations) Generic intervention level GIL^ msv GIL r H.,o H., g msv msv msv H thy #» *; *: T* OIL! msv msv/h msv/h msv/h msv/h msv/h OIL2 msv/h OILS msv/h OIL4 msv/h OILS uswh OIL6 kbq/m 2

211 Symbol OIL? Unit kbq/m 2 Description Deposition levels OILS kbq/kg OIL9 kbq/kg pa plant r RF MW(th) R, R, SF T e h T d ^ T, u fi days hours, days years kg/d u«, w x. x r kg/d km km Xthy km Y kg/m 2

212 REFERENCES ANSI79 American National Standard ANSI84 ASME93 DOE84 DOE95 EGG75 EPA70 EPA88 EPA92 EPA93 EPA94 FEMA87 IAEA74

213 IAEA 86 Derived Intervention Levels IAEA94 IAEA94a IAEA96 1AEA97 ICRP75

214 NRC83a NRC83b A. L. Camp, et al., Light Water Reactor Hydrogen Manual, NUREG/CR (SAND , R3), U.S. Nuclear Regulatory Commission, Washington, D.C.. June J.

215 GLOSSARY Definitions of terms and acronyms used in the document These definitions are only assist the user of this document. AC Alternating current Active fuel

216 Ambient dose rate Ambient Dose Equivalent, H*(d)

217 BWR See: Boiling water reactor By-pass Route that allows fission products released from a reactor core to enter the environment without passing through the containment or accident localization volume. Catastrophic failure Failure of the reactor containment in a manner that releases most of the fission products in the containment into the environment in a short time. Centerline (plume) An imaginary line drawn in the middle of the plume along its downwind travel direction with a straight-line Gaussian approximation model. The plume concentrations and deposition are assumed to be the highest along the centerline. CET See: Core exit thermocouple Charging Pump A pump used during normal operation to maintain primary system water level. Also referred to as a make-up pump or normal injection pump. This pump may also used as part of the ECCS system. Child A 10 year old. Chronic dose Radiation dose received over

218 generator. In a boiling water reactor, it returns to the reactor vessel. The heat removed from the system

219 Curie (Ci)

220 Emergency action level (EAL) A pre-determined site specific observable threshold at which places a plant and off-site response organizations

221 Fuel rod (fuel pin) A long, slender tube that holds fissionable material (fuel) for nuclear reactor use. Fuel rods are assembled into bundles called fuel elements

222 Half-life, biological

223 Intervention level The level of avertable dose at which a specific protective action or remedial action is taken in an emergency exposure situation or a chronic exposure situation. Isotopes Nuclides

224 Normal coolant release

225 Pressurizer A tank

226 Re-entry Temporary entry into

227 Severe core damage Damage

228 Spiked coolant release The release of 100 times the non-noble gas fission products found in the coolant. Spiked coolant Rapid increase in non-noble gas fission products in the reactor coolant. This can occur following rapid shutdown

229 Tissue or organ Gonads Bone marrow (red) Colon (a) Lung Stomach Bladder Breast Liver Oesophagus Thyroid Skin Bone surface Remainder (b) Tissue weighting factor W T

230 Turn back guidance An integrated dose reading

231 CONTRIBUTORS TO DRAFTING AND REVIEW I. CONSULTANTS MEETING Vienna November, 1995 Asculai, E. Israel Atomic Energy Commission, Tel-Aviv, Israel McKenna,

232 Trefethen,

233 CORRECTIONS TO REPORT Vienna August, 1996 McKenna, T. (Scientific Secretary) Martincic, R. Winkler, G. Division of Radiation and Waste Safety, International Atomic Energy Agency, Vienna, Austria J. Stefan Institute, Ljubljana, Slovenia Atom Institute of the Austrian Universities, Vienna, Austria QUALITY CHECK AND REVISIONS Vienna October, 1996 McKenna,

234 McKenna, V. CONSULTANT MEETING Vienna January, 1997

235 AC INDEX

236 conversion factors for ingestion for ambient dose rate from deposition , 178 for future maximum cow milk isotope concentration for long term dose from deposition , 178 from inhalation...

237 emergency

238 marker isotope 125,136 maximum cow milk isotope concentration 128 milk 211 monitor

239 radiation protection 81 Radiation Protection Manager