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1. E Accident analysis AA S A OPERATIONAL SAFETY ISSUES fe Management MA ED Operations OP H Surveillance and maintenance SM ER Training TR Emergency preparedness incl physical pr Radiation protection RP 2 8 Fuel storage FS 1 imaoro nz Lyen Updated by dbo Aston 9 4 Nesis iPUBLCYohar 32 LWA Generic Safety 87 New Bitmap Image bmp 1998 07 14 15 08 A X 1508 In addition to the comments this screen also displays audit information such as the date the issue was initially inserted along with the date and the id of the person who last updated this record 10 LWRGSIDB User s Manual 3 6 Another view by Member States The system provides you with the functionality of viewing all issues from the view of the Member States that have taken measures on them Click the Member States tab and the click on Spain You will get all issues on which Spain has taken measures At this stage all functionality which is provided from the system s normal view by issue is also available here F LWR Generic Safety Issues gt Bulgaria Czech Republic Russia Ukraine gt Bulgaria Czech Republic Ukraine Bulgaria Ukraine 1 82 Czech Republic E Czech Republic Hungary Slovakia ae France ae France Germany Sweden USA Germany and Sweden Germany Sweden USA India ER Russia E 3 8 Russia and Ukraine Russia Ukraine and Bul2. Precautions for mid Ioop operati H Surveillance and maintenance SM ER Training TR 51 8 Emergency preparedness incl physical pr H Radiation protection RP EA Fuel storage FS amp FS1 Degradation of boron plates in fu FS2 Potential for fuel pool drainage 2 FS3 Damage to fuel during handling Safety Significan pm tm operational experience deviation from current standards and practices potential weakness identified by deterministic or probabilistic PSA analyses gt i 1398 07 22 10 03 A Aston E 9 4 fh Lw_MAINT Microsoft Vis YA LWR Generic Safety Issues C4 WNesisdtSPUBLIC ohar B Microsoft Word Starting 99 New Bitmap Image bmp X 10 03 15 LWRGSIDB User s Manual 3 9 Connecting to a different data source You can connect anytime to a different local data source To do this select Filelchange data source and with the browse feature locate and select the database you wish to connect to Press select when finished Please note that this feature is most often used by users of the Member States version after receiving a new copy of the database from the IAEA It can also be used by IAEA staff to check the contents of a database before delivering it to the Member States External hazards EH Accident analysis AA OPERATIONAL SAFETY ISSUES MA Management Operations OP Training TR 2 Emergency preparedness incl physical pr Radiation prote
3. IAEA Safety Reports Series No 12 Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards A Common Basis for Judgement 1998 Some of the findings of the 1991 conference have not yet been fully addressed An IAEA Symposium on Reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review those operating nuclear power plants which do not reach the high safety levels of the vast majority of plants and to undertake improvements with assistance from the international community if required Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear Safety and its implementation In order to perform safety reviews and to reassess the safety of operating nuclear power plants in a uniform manner it is imperative to have an internationally accepted reference Existing guidance needs to be complemented by a list of safety issues which have been encountered and resolved in other plants and which can be used in reassessing the safety of individual operating plants The IAEA TECDOC 1044 Generic Safety Issues for Nuclear Power Plants with Light Water Reactors and Measures Taken for Their Resolution September 1998 is a compilation of such safety issues which is based on broad international experience This compilation is one element in the framework of IAEA activities to assist
4. Member States in reassessing the safety of operating nuclear power plants It is a compilation not only of the generic safety issues identified in nuclear power plants but also in almost all cases the measures taken to resolve these issues The safety issues which are generic in nature with regard to light water reactors LWRs and the measures taken for their resolution are intended for use as a reference in the reassessment of the safety of operating plants The information contained in the main body of the TECDOC has been used to establish a database This database has search query and report functions This information is thus available in an electronic form which can be selectively queried and with which reports can be produced according to the requirements of the user The database also enables the IAEA to update the data periodically on the basis of information made available by Member States The IAEA staff member responsible for this publication was G Philip of the Division of Nuclear Installation Safety EDITORIAL NOTE In preparing this publication for press staff of the IAEA have made up the pages from the original manuscript s The views expressed do not necessarily reflect those of the IAEA the governments of the nominating Member States or the nominating organizations The use of particular designations of countries or territories does not imply any judgement by the publisher the IAEA as to the legal status of such countri
5. effectiveness to fulfill the assigned safety functions and 2 the structural capacity to cope with the corresponding thermal hydraulic loads acting on structural elements and components in accordance with acceptance criteria established for specific site and plant conditions Preliminary calculations conducted under conservative assumptions by the original Russian designer resulted in a value of 30 kPa for the differential pressure during the initial phase of the accident after an instantaneous double ended guillotine break of the largest pipe in the reactor coolant system which may be considered as an upper limit until more data and investigations are available Preliminary and conservative calculations performed on the basis of that value for Mochovce Dukovany and Bohunice V2 plants indicated that the bubbler condenser structure design has weak points and more detailed investigations are required before any strengthening measures are decided The thermal hydraulic parameters of bubbler condenser long term operation after LOCA have been verified in reduced scale tests No large scale tests have been performed Such tests are required to assure that there are no unexpected pressure oscillations with significantly high pressure pulses and fluid structure interactions dangerous to the integrity and functioning of the bubbler condenser No such loads have been xf Safety Significance Effectiveness of the bubbler condenser is es
6. outage activities to minimize risk MA5 Degraded and non conforming conditions and operability determinations MA7 Human and organizational factors in root cause analysi MA8 Impact of human factors in the safe operation of nuclear power plants MA9 Effectiveness of quality programmes MA10 Adequacy of procedures and their use MA11 Adequacy of emergency operating procedures MA12 Effectiveness of maintenance programmes OP3 Inadvertent introduction of chemicals and their effects on safety related sy OP1 Intentional bypassing of automatic actuation of plant protective features DP2 Response to loss of control room annunciators OP4 Precautions for mid loop operation SM6 Foreign material policy SM1 Adequacy of non destructive inspections and testingf SM2 Removal of components from service during power or shutdown operation SM3 Use of freeze seals SM4 Use of pressure injection of compounds to seal leaks E SM5 Inadequate testing of Engineered Safety Features ESF actuation systems 12 LWRGSIDB User s Manual The system will show the result under the Find Results tab EPI Need for effective off site communications during events ds I Sk FS2 Potential for fuel pool drainage At this stage viewing issues measures additional sources etc is supported in the usual manner Your search criteria could also contain wild cards e g the following search criteria flood earthquake would yield any text containi
7. COMPUTER MANUAL SERIES No 13 Light Water Reactor Generic Safety Issues Database LWRGSIDB User s Manual INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA 1999 The originating Section of this publication in the IAEA was Safety Assessment Section International Atomic Energy Agency Wagramer Strasse 5 P O Box 100 A 1400 Vienna Austria LIGHT WATER REACTOR GENERIC SAFETY ISSUES DATABASE LWRGSIDB USER S MANUAL IAEA VIENNA 1999 IAEA CMS 13 IAEA 1999 Printed by the IAEA in Austria February 1999 FOREWORD The IAEA Conference on The Safety of Nuclear Power Strategy for the Future in 1991 was a milestone in nuclear safety The objective of this conference was to review nuclear power safety issues for which achieving international consensus would be desirable to address concerns on nuclear safety and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards Some of the publications related to these two items that have been issued subsequent to this conference are A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards INSAG 8 1995 the IAEA Safety Guide 50 SG O12 Periodic Safety Review of Operational Nuclear Power Plants 1994 and
8. Safety Issues BEE File Edt Tools Help b HS S alls BBAY o a iu Codes Member States Find results EIA DESIGN SAFETY ISSUES ER General GL Reactor core RC 2 82 Component integrity Cl 51 8 Primary circuit and associated systems PC Safety systems SS Electrical and other support systems ES EI Instrumentation and control incl protectio E NA Containment and other structures CS C ment c A 4 052 Assessment of BWR containme amp 053 Containment and confinement ir 8 Intemal hazards IH External hazards EH H Accident analysis AA EQ OPERATIONAL SAFETY ISSUES Management MA Operations OP Surveillance and maintenance SM Training TR 6 Emergency preparedness incl physical pr ta 2 Radiation protection RP EI Fuel storage FS Issue Title Assessment of WWER 440 213 containment dynamic loadst 1 Issue Subtitle wwert T Draft The safety concerns about the bubbler condenser containment behaviour are related to two phases of the thermal hydraulic processes following a LOCA a the initial pressure difference acting on the walls of the bubbler condenser system immediately after LOCA and b the long term phenomena accompanying steam condensation in the water trays of the bubbler condenser system In this context there are two main issues not fully known and documented since its original design 1 the thermodynamic behaviour of the bubbler condenser under accident conditions and its
9. base neither the IAEA Windows 32 bit SAL Server Login Lx Data Source LWRGSI ur f y Agency Vienna Austria DK Login ID fioharh Cancel Password Options gt gt LWRGSIDB User s Manual 2 4 Select database Ea Sc y aca IAEA Program Files Starting the system Member State version The LWRGSIDB icon will appear on your Windows desktop once the installation is completed Double click on the icon marked LWRGSIDB You may also start the system by choosing the Windows 95 Start Menu then selecting ProgramsILWRGSIDB During the first run the initialization screen for the LWRGSIDB system will appear followed by the following database selection screen Generic Safety Issues for Light Water Reactor Nuclear Power Plants Disclaimer Version 1 0 0 Although great care has been taken to maintain the _ _ accuracy of the data in this database neither the IAEA Windows 32 bit nor its Member States assume any responsibility for Comment wdata mdb 1 0 12 10 1998 2 29 56 PM test data file from NS Navigate in the directories to specify data file extension mdb provided separately as a data diskette required decompression follow the instruction on the data diskette in the readme txt file You can see data file properties on the right side of the form Once selected data file will be used for the future sessions until you change it using FilelChange datasource
10. clicking measures would display the following screen 1o1x 9 LWR Generic Safety Issues Eile Edit Tools Measures Help EINE Codes Member States Find results Ay DESIGN SAFETY ISSUES General GL EB Reactor core RC Be gt Component integrity Cl Primary circuit and associated systems PC Safety systems SS Electrical and other support systems ES EI Instrumentation and control incl protectio EAA Containment and other structures CS INo work has been done so far The conclusions of AGNES project states that it would be very desirable to validate the containment thermal hydraulic models on the basis of a full scale experiment and continue the containment strength analyses As a result the thermal hydraulic functions of the containment and the bubbler condenser system could be assessed and the interaction between the flowing medium and the structural elements within e containment could be tested AGNES Summary page 36 053 Containment and confinement ir EI Internal hazards IH External hazards EH gt Accident analysis AA a ta OPERATIONAL SAFETY ISSUES ssia E Management MA EI Operations OP e position of the authorities has not been fully declared The representatives of the organization operating Kola NPP have stated that the existing Surveillance and maintenance SM SAR includes the following calculations gt Training TR Emergency preparedness incl physical pr mass flow rat
11. ction RP Fuel storage FS 1 2 Surveillance and maintenance SM 16 99 00294
12. ctures CS or all Design Safety Issues click on the area in the tree and follow the same steps as above to designate your choice of fields To print a mixed list of your choice of issues select Filelprint Select your choice of fields as before click on issues and enter your issue list using the Issue codes in the corresponding text box e g CS1 CS4 OP1 FS3 Select print preview when finished Pe LWR Generic Safety Issues ME File Edt Tools Help pala B Codes Member States Find results QQ DESIGN SAFETY ISSUES E gt General GL E Reactor core AC E Component integrity Cl E Primary circuit and associated systems PC Safety systems SS Electrical and other support systems ES 2 Instrumentation and control inci protectio A Containment and other structures CS amp CS1 Assessment of WWER 440 213 CS2 Assessment of BWR containme Description of Issue this is the description text CS3 Containment and confinement ir CS4 My Issue is Print Options olx 68 Intemal hazards IH Print fields External hazards EH E Accident analysis AA cd Boo B pe eee Y Title Subtitle TF Measures E Management MA TR x 3 9 Operations OP T Description TF Additional Sources DPI Intentional bypassing of automa I Safety Significance I Comment DP2 Response to loss of control oor a 2 OP3 Inadvertent introduction of cher Print issues range DPA
13. ersions of LWRGSIDB To uninstall follow the usual way Settings Control PanellAdd Remove programs To install the latest version of LWRGSIDB ask your TC Co ordinator where on your server the setup program is and simply run it Setup will install the necessary files locally on your hard disk Custom dictionary Initially the system looks for a custom dictionary named LWRGSI VTC by default at your local drive If you wish to use a shared custom dictionary on a network drive you would have to tell the system of its location This can be done very easily inside the dialogue that is activated when you run the spell check run spell checking by clicking on the spell checking icon click on Options click on Open Custom browse and select the custom dictionary you would like to use This can be a shared one on a network drive O Subsequently the system would remember the new custom dictionary and its location You will not have to do this every time LWRGSIDB User s Manual 2 2 Installing the system Member State version There are 2 steps for of the installation of LWRGSIDB system The first step is the setting up of the software from the diskettes The second step is the installation of the database file provided as separate data diskette Software installation is normally required only once but occasionally you may receive a new version of the software from the IAEA and it may be required to re install the software Database i
14. es of steam air mixture at the inlet into the bubbler condenser 3 Radiation protection RP determination of required quantity of water in the bubbler condenser trays Fuel storage FS hydrodynamic analysis of tray behaviour strength analysis of bubbler condenser metallic structure without taking into account the dynamic phenomena in the initial period of the accident There has been so far no direct discussion of the necessity of any further analyses or strengthening of the bubbler condenser structure lovakia IAEA mission has reviewed the plant specific status in Bohunice and Mochovce NPPs and proposed the ways of bubbler condenser structure strengthening An experimental study of the problem has been prepared and is planned to be started in 1996 In Mochovce NPP there is also an international working group which studies the problem and will specify the extent of the necessary calculations and possible upgrading Ukraine INo decisions made as yet Ukrainian specialists see the problem as the need for individual reinforcements of elements of the bubbler condenser kK sssor a 14 45 A Mstart amp E 9 A Nesid SPUBLCYohar FALWR Generic Safety QE 14 45 LWRGSIDB User s Manual 3 4 Howto view additional sources You can view the additional sources of any issue by clicking on the additional sources tab on top of the right part of the screen E g for CSI assessment of WWER 440 213 clicking additional s
15. es or territories of their authorities and institutions or of the delimitation of their boundaries The mention of names of specific companies or products whether or not indicated as registered does not imply any intention to infringe proprietary rights nor should it be construed as an endorsement or recommendation on the part of the IAEA The IAEA has made reasonable efforts to check the program disk s for known viruses prior to distribution but makes no warranty that all viruses are absent Although great care has been taken to maintain the accuracy of the data in this database neither the IAEA nor its Member States assume any responsibility for consequences which may arise from its use The IAEA makes no warranty concerning the function or fitness of any program and or subroutine reproduced on the disk s and shall have no liability or responsibility to any recipient with respect to any liability loss or damage directly or indirectly arising out of the use of the disk s and the programs and or subroutines contained therein including but limited to any loss of business or other incidental or consequential damages CONTENTS LANE RO DUCTION RRA NANA TA E TE 1 GETTING STARTED e dose ibi essence 1 2 1 Installing the system Vienna version usessssssnsessnnessnnnensnnnnsnnnennnnensnnnennnnennn nn 1 2 2 Installing the system Member State VersiOW ooooconconocnnonnconnnnnnnnnnnnonccnncnrnn cnn ncnnnaron anno 2 2 3 Starting
16. garia akia Steam and feedwater piping degradation EP1 Need for effective off site communications during even ES1 Reliability of off site power supply fs ES Control room habitability 1C8 Human engineering of control rooms ddd e 1C15 Improving the detection of primary secondary leaks Q MA2 Fitness for duty MA Human and organizational factors in root cause analys MA11 Adequacy of emergency operating procedures MA12 Effectiveness of maintenance programmes OP3 Inadvertent introduction of chemicals and their effects OP4 Precautions for mid loop operation PWR 57 Boron crystallization and dilution in the core in case of Note also the special entry of Issues without measures at the bottom of the tree This entry contains those issues which have no measure taken entered yet so that they are not lost in this view of the database 11 LWRGSIDB User s Manual Reactor core RC BREA 3 7 Operations OP Training TR Emergency prepar Radiation protect Fuel storage FS Surveillance and r How to search for issues You can search for an issue or a group of issues that fulfil a certain search criteria of one or more words To do this click the find button enter your criteria and press find at the bottom of the screen In the following example the system will search the description field and measure text of all operational safety issues for the word earthquake MA4 Control of
17. luation Guidelines for bubbler condenser metallic structure in WWER 440 213 NPPs containments LAEA WWER SC 095 July 1994 dt Review of bubbler condenser structural integrity in Mochovce and Bohunice V2 NPPs LAEA WWER SC 159 1995 report to the Steering Committee s USNRC Regulatory Guides RGs 1 11 1 53 1 151 1 153 1 33 INTERNATIONAL ATOMIC ENERGY AGENCY Code on the safety of nuclear power plants design Safety Series No 50 C D Rev 1 IAEA Vienna 1988 gt 1988 07 14 14 53 Li Start amp 9 4 Nesid PUBLICVchar JALWA Generic Safety A New Bitmap Image bp Re 1453 LWRGSIDB User s Manual 3 5 Howto view comments and record audit information You can view any comments on any issue by clicking on the Comments tab on top of the right part of the screen E g for CS1 assessment of WWER 440 213 clicking comment would display the following screen F4 LWR Generic Safety Issues Eile Edit Tools Help Pel ES Dux a DESIGN SAFETY ISSUES ER General GL ED Reactor core AC E Component integrity CI ES Primary circuit and associated systems PC EI Safety systems SS Electrical and other support systems ES E Instrumentation and control incl protectio QQ Containment and other structures CS amp CS1 Assessment of WWER 440 21 2 52 Assessment of BWR containme 153 Containment and confinement ir E o Internal hazards IH E gt Extemal hazards EH
18. menu item LWRGSIDB User s Manual 3 FEATURES COMMON TO ALL VERSIONS OF THE SOFTWARE 3 1 Initial screen After starting the system the following screen will then appear This is the main screen of the system 8 Accident analysis AA PERATIONAL SAFETY ISSUES MA Operations OP 8 Surveillance and maintenance SM Radiation protection RP Fuel storage FS LWRGSIDB User s Manual Inside the left section of the screen you can expand any area by clicking on it e g Clicking on Containment and other structures CS would display the existing issues for that area CS EAA DESIGN SAFETY ISSUES E General GL E Reactor core RC ED Component integrity CI E Primary circuit and associated systems P Safety systems SS Electrical and other support systems ES Instrumentation and control incl protectio 253 Containment and confinement i Internal hazards IH External hazards EH Accident analysis AA OPERATIONAL SAFETY ISSUES Management MA Operations OP Surveillance and maintenance SM Training TR Emergency preparedness incl physical p Radiation protection RP Fuel storage FS LWRGSIDB User s Manual 3 2 Howto view an issue You can view the issue description and safety significance of any issue by clicking on its respective entry in the issues tree inside the left part of the screen E g Clicking on CSI assessment of WWER 440 213 would display the following screen Pe LWR Generic
19. ng the words flood and earthquake with anything in between You also can print issues from the result set individual issues or groups of issues With a mouse click and the help of the shift key you can highlight for printing a group of consecutive issues in the normal windows style You can for example click on the first issue press shift and then click on the last issue This would highlight all issues Instead of the shift key you can use the control key along with the mouse to highlight non consecutive issues for printing Also this is a MS Windows feature 13 LWRGSIDB User s Manual 3 8 How to print issues You can print some or all fields of any single issue all issues of a particular area all issues belonging to a group of areas or a mixed list of your choice of issues belonging to different areas You always have the choice to preview the printout before you actually print For example to print title subtitle and description of issue CS4 Click on it select FilelPrint from the menu click on description Title subtitle is selected by default then press print fs LWR Generic Safety Issues oxi File Edit Tools Help Rear ES Codes Member States Find results My Issue Issue Code cs 4 Issue Subtitle W Draft Description of Issue General GL H Reactor core RC 3 82 Component integrity Cl E Primary circuit and associated systems PC ER Safety systems SS 2 8 Electrical and other
20. nstallation should be repeated each time when you receive a new copy of the LWGSI database 1 In order to install the software insert the first of 6 installation diskettes and run the setup file from this diskette Then follow the instructions that appear on the screen 2 Database installation should be performed according to the readme txt file located on the first data diskette For convenience these instructions are repeated here e Copy LWDATA EXE file to the hard disk this needs at least 4 Mb free space e Run LWDATA EXE The new LWDATA MDB file will be extracted and created e Delete LWDATA EXE e Use LWDATA MDB file as data file for LWGSIDB system FilelChange datasource menu Please check the details in the readme txt file in case there have been any last minute changes since this manual was written LWRGSIDB User s Manual 2 3 Starting the system Vienna version The LWRGSIDB icon will appear on your Windows desktop once the installation is completed Double click on the icon marked LWRGSIDB You may also start the system by choosing the Windows 95 Start Menu then selecting ProgramsILWRGSIDB The initialization screen for the LWRGSIDB system will appear followed by the following Logon screen Enter your login ID and Password and select OK Generic Safety Issues for Light Water Reactor Nuclear Power Plants i i Yersion 0 1 0 great care has been taken to maintain the A of the data in this data
21. ources would display the following screen Pe LWR Generic Safety Issues AmE File Edit Tools Additional Source Help DERE Baay Codes Member States Find results EIA DESIGN SAFETY ISSUES ER General GL E Reactor core RC 2 8 Component integrity CI 1 8 Primary circuit and associated systems PC ER Safety systems SS 2 8 Electrical and other support systems ES te Instrumentation and control incl protectio QQ Containment and other structures CS INTERNAT ONAL ATOMICHE EBP WWERNJ Vienna 19 MOHT OTJIG RM EDF DE CLI Revision 6 February 1997 ERGY AGENCY Safety issues and their ranking for WWER 440 model 213 nuclear power plants IAEA USNRC Inspection Report 50 397 92 37 W P Ang et al Special inspection issued November 1992 Title 10 Code of Federal Regulations Part 50 10CFR50 66 Requirements for thermal annealing of the reactor pressure vessel December 19 1995 t C ment c 1 052 Assessment of BWR containme 053 Containment and confinement ir 8 Intemal hazards IH H External hazards EH H Accident analysis AA EPA OPERATIONAL SAFETY ISSUES Management MA Operations OP Surveillance and maintenance SM Training TR Emergency preparedness incl physical pr Radiation protection RP EI Fuel storage FS INTERNATIONAL ATOMIC ENERGY AGENCY Analysis of WWER 1000 safety enhancement measures WWER RD 080 1994 INTERNATIONAL ATOMIC ENERGY AGENCY Eva
22. sential for fulfilling the safety function relating to limiting the maximum pressure after a DBA occurrence and to preventing the release of radioactive products to the environment To fulfill this objective efficient condensation of steam in water trays need to be assured without excessive bypassing of trays If the bubbler condenser structure walls and caps were to fail in the initial moment of the postulated accident then the water would flow out of its shelves into the bubbler condenser tower early after the accident This would provide sudden steam condensation and pressure drop inside the containment but the water would be lost from the bubbler condenser shelves and in the subsequent stages of the accident process the bubbler condenser would not be able to fulfill its safety functions The bubbler condenser structural failure can question its safety function and this in tum can lead to the damage of the containment that is question the third barrier against release of radioactive products Source of Issue check as appropriate operational experience viation from current standards and practices gt 1998 07 14 14 44 L Start E 9 4 Nesis SPUBLICWohar FALWR Generic Safety e 14 44 LWRGSIDB User s Manual 3 3 Howto view measures taken You can view the measures takes on any issue by clicking on the measures tab on top of the right part of the screen E g for CSI assessment of WWER 440 213
23. support systems ES E Instrumentation and control incl protectio QQ Containment and other structures CS amp CS1 Assessment of WWER 440 212 Assessment of BWR containme this is the description text iw Print Options oO x Print fields Tall V Title Subtitle I Measures IV Description TF Additional Sources Safety Significance Comment temal hazards E External hazards EH 8 Accident analysis AA EA OPERATIONAL SAFETY ISSUES 1 Management MA EA Operations OP OP1 Intentional bypassing of automa T Source OP2 Response to loss of control roor OP3 Inadvertent introduction of cher Fron issues rence OPA Precautions for mid loop operati oso 3 Surveillance and maintenance SM ee ca Training TR E o Emergency preparedness incl physical pr E Radiation protection RP E a Fuel storage FS FS1 Degradation of boron plates in fu 2 F52 Potential for fuel pool drainage 2 FS3 Damage to fuel during handling C Issues es operational experience deviation from current standards and practices potential weakness identified by deterministic or probabilistic PSA analyses gt i 1398 07 22 09 42 4 A Stan esa I thy LW_MAINT Microsoft Vi TALWAR Generic Safety Issues aM NesisdH PUBLIC ohar BY Microsoft Word Starting t 09 42 14 LWRGSIDB User s Manual Likewise to print all issues belonging to the area Containment and other stru
24. the system Vienna version lehnen 3 2 4 Starting the system Member State version cessccesscecesceceeneeceeceeceeececeeeeecseeeeeeaeees 4 FEATURES COMMON TO ALL VERSIONS OF THE SOFTWARE eennn 5 AR o tan rn En Ra I LE RE 5 3 2 HOW to view an ISSUC E e a ad A SAG ah Oe 7 3 3 How to view measures taken occccccccnnnncocicoconoconinoninininanacinanananananananananananana ra rara nana 8 3 4 How to view additional SOUICES ooccccnccnnnoninononininononananinanananinanananananananananana nara rara nana 9 3 5 How to view comments and record audit informati0ON ococcccncnnnnnnnnnnnnnnonanonininananenes 10 3 6 Another view by Member States muscle uam 11 3 7 How to s arch for 1ssues cuca 12 0 HOW tO POE LINE 1S SUES gk E E EE ER 14 3 9 Connecting to a different data source 100 dorado nes 16 LWRGSIDB User s Manual 1 INTRODUCTION Please note that Section 2 of this document GETTING STARTED should be read very carefully There are 2 versions of the software one 1s installed at the Headquarters of the IAEA in Vienna Vienna version and the other is distributed to Member States on diskettes Member State version Please make sure you read the correct sections which apply to the version you have installed on your PC Section 3 onwards 1s common to both versions 2 GETTING STARTED 2 1 Installing the system Vienna version Before installation make sure you ve uninstalled any older v
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