Ranking of safety issues for
|
|
|
- Lindsey Peters
- 5 years ago
- Views:
Transcription
1 IAEA-TECDOC-640 Ranking of safety issues for WWER-440 model
2 RANKING OF SAFETY ISSUES FOR WWER-440 MODEL
3 PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK
4 RANKING OF SAFETY ISSUES FOR WWER-440 MODEL
5 FOREWORD In response to requests from Member States operating Soviet designed WWER- 440/230 nuclear power plants (NPPs) for assistance through the IAEA's nuclear safety services,
6 In preparing this material EDITORIAL NOTE
7 CONTENTS 1. INTRODUCTION...
8 1. INTRODUCTION
9
10 Due consideration was also given to two aspects specific to WWER-440/230 NPPs. First, these plants were designed according
11 Finally the issue is evaluated based on its potential to cause accidents with unacceptable consequences. The approach used for ranking of issues related to plant operation is in principle the same. Issues affecting management and organization essential procedures,and training are among those ranked in higher categories. The methodology described aimed at providing guidance for the experts to rank safety issues
12 2. OVERVIEW OF SAFETY ISSUES
13 instrumentation and control (including man-machine interface), electric power supply, fire protection, protection against earthquakes and other external hazards, accident analysis,
14 Safety issues related
15 2.2. Cooling
16 Control
17 Failure
18 Safety issues related to this subsection are: Electrical
19
20
21 Accident Analysis 8 Accident Analysis 9 Operating Procedures 2 Training Radiological Consequences (II) Evaluation of Modifications (III) Emergency Operating Procedures (IV)
22 Safety issues related to this subsection are: Systems
23 It has been proven, though, that the rate of embrittlement can be significantly slowed down
24 Primary Circuit Overpressure Protection Protection of primary circuit against overpressure is insured by the pressurizer safety valves. These valves are generally pilot operated valves. But they are not qualified for water or water/steam mixtures. This means that the primary circuit is not well protected during periods when
25 Components
26 Systems 15 Accident Analysis 1 Accident Analysis 8 Operating Procedures 2 Maintenance Dynamic Loads Due to Piping Failures (II) Confinement Analysis (III) Radiological Consequences (II) Emergency Operating Procedures (IV)
27
28 define what should be done at the level of I&C to improve the performance of each safety function (e.g. accident monitoring instrumentation...). Finally, a detailed programme for upgrading systems and equipment is required where the investigations have identified shortcomings. Safety issues related
29 Implementation of Additional Scram Signals. Highest consideration should
30 Remote Shutdown Panel There
31 At the same time, the means to improve separation in the layout between the two trains should be investigated and strict procedures should be implemented to keep doors and ducts between rooms of the two trains closed. Potential consequences on the required cooling and ventilation systems capacity need to be considered. In case of loss of off-site power, the main source of AC power supply is the diesel. Three diesel generators are installed in each unit, two of them are directly connected to the two redundant 6 kv busbars, the third one is on standby and can be connected to any of
32 DC Power Supply
33 In most of the plants, RMGs have shown a poor reliability and have required frequent repairs. They should
34 With respect to fire detection only areas such as transformers, cable corridors and diesels are covered. Other places with high fire risks or with high safety consequences in case of fire, such as the turbine oil tanks, the safety injection pump room, the reactor hall, the service water pump building or even the main control room are generally not equipped with fire detection systems. In all the areas where a fire would have severe consequences for safety due to common mode failure
35 consider appropriate boundary conditions, application of the single failure criterion, assumptions concerning operator action and common mode failures. Accidents not considered so far, including accidents beyond the DBA should be included in the analyses.
36 Management The safe and efficient operation of a nuclear power plant requires that the organizational structure and responsibilities be clearly defined; that management set the example for and expect high performance standards; that objectives and goals be established, monitored,
37 Issues relating to operating procedures covered in this section are: Accident Analysis 6 Operating Procedures Scope of Accident and Transient Analysis (III)
38
39 emergency plans in most cases were based on the most severe accident scenarios, which places considerable constraints on both the on-site and off-site plans. Emergency plans needed
40 3. DESIGN ISSUES 39
41 ISSUE NUMBER: Core
42 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE II IN-CORE MONITORING II IN-CORE MONITORING II IN-CORE MONITORING II IN-CORE MONITORING
43 ISSUE NUMBER: Core 2 ISSUE TITLE: Core Design Margin Evaluation RANK
44 ISSUE ITEM n. TITTLE/Descnption ASPECT AREA REFERENCE II CORE DESIGN MARGIN EVALUATION II COKE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II II CORE DESIGN MARGIN EVALUATION CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION II CORE DESIGN MARGIN EVALUATION
45 ISSUE NUMBER: Core
46 CAT. ISSUE ITEM n. TITTLE/Oescnption ASPECT AREA CLASS REFERENCE II FUEL EXAMINATION
47 ISSUE NUMBER: Core 4 ISSUE TITLE: Reloading Procedures
48 CAT. ISSUE ITEM
49 ISSUE NUMBER: Systems
50 CAT. ISSUE ITEM
51 ISSUE NUMBER: Systems
52 CAT. ISSUE ITEM
53 ISSUE NUMBER: Systems 3 ISSUE TITLE: Decay heat removal. Ensuring adequate SG inventory RANK
54 CAT. ISSUE ITEM n. TITTLE/Descnption ASPECT AREA CLASS REFERENCE IV DECAY HEAT REMOVAL - SG INVENTORY IV DECAY HEAT REMOVAL - SG INVENTORY IV DECAY HEAT REMOVAL
55 ISSUE NUMBER: Systems
56 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE [I DECAY HEAT REMOVAL
57 ISSUE NUMBER: Systems 5 ISSUE TITLE: Decay Heat Removal. Service Water System RANK OF ISSUE: III ISSUE CLARIFICATION:
58 CAT ISSUE ITEM
59 ISSUE NUMBER: System 6 ISSUE TITLE: Decay Heat Removal. Component Reliability RANK OF ISSUE: III ISSUE CLARIFICATION: The failure probability of active components needed for decay heat removal purposes shall be small to ensure adequate reliability. The existing systematic recording and evaluation
60 CAT. ISSUE ITEM
61 ISSUE NUMBER: Systems
62 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE 111 ECCS - FULL LOCA SPECTRUM CAPABILITY 384 STARTUP OF SPRAY PUMPS D ACCIDENT Ï.6 BOHUHICE 11.9.(2) Check the possibility of earlier connection of the spray pumps to the Diesel to achieve lower confirment peak pressure and reduce activity release. Ill ECCS - FULL LOCA SPECTRUM CAPABILITY 628 SPRAY CAPABILITY 0 SYSTEMS 3.7 KOZLOOUY 8.5.(7) Review spray system design capability and performance after new accident analysis for all LOCA spectrun. Ill ECCS - FULL LOCA SPECTRUM CAPABILITY 689 HYDRO ACCUMULATORS 0 ACCIDENT 3.6 KOZLOOUY 11.2.(1) High pressure hydro accumulators should be installed. lit ECCS - FULL LOCA SPECTRUM CAPABILITY 856 ACCUMULATORS FOR LARGER LOCA 0 ACCIDENT 1.11 NOVOVORONE 12.3.(11) The concerns (high energy tanks in the reactor building, coincident top and bottom core flooding) should
63 ISSUE NUMBER: Systems 8 ISSUE TITLE: ECCS - Redundancy and Physical Separation of Redundant Parts RANK OF ISSUE: IV ISSUE CLARIFICATION:
64 CAT ISSUE ITEM n TITTLE/Descnption ASPECT AREA CLASS REFERENCE IV ECCS - REDUNDANCY AND SEPARATION IV ECCS REDUNDANCY AND SEPARATION 54 SAFETY INJECTION POINTS D SYSTEMS 3 6 DESREV Some stations have modified the emergency injection points The 12 cold leg points are no longer used and injection is in 2 hot legs Injection on hot leg must be demonstrated to be effective. 55 HOT LEG INJECTION REDUNDANCY D SYSTEMS 3.6 DESREV A In plants were safety injection is in 2 hot legs, the reduction of injection poits must be assessed. Of concern is a break in a leg so that all injection from one train is lost to the break, coupled with a single failure in the other train. IV ECCS REDUNDANCY AND SEPARATION IV ECCS
65 CAT. ISSUE ITEM
66 ISSUES NUMBER: Systems
67 CAT. ISSUE ITEM n. TITTlE/Description ASPECT AREA CLASS REFERENCE II ECCS - PRIMARY BREAK ISOLATION OPTIONS 39 PRIMARY LOOP ISOLATION STUDY 0 SYSTEMS 1.11 OESREV
68 ISSUE NUMBER: Systems
69 CAT. ISSUE ITEM
70 ISSUE NUMBER: Systems 11 ISSUE TITLE: Primary Circuit Pressure Relief RANK OF ISSUE: III ISSUE CLARIFICATION: In thé original WWER 440/230 design, safety relief valves are provided on the pressurizer. Thèse valves are not qualified to relieve water and their operational reliability is not proven to be adequate under various operating conditions. RELATED ITEMS: 41, 42, 310, 604, 605, 606, 607, , 794, 1043 JUSTIFICATION OF RANKING: Reactor coolant system integrity strongly depends on the reliable operation of primary relief valves. Unreliability
71 CAT. ISSUE ITEM
72 ISSUE NUMBER: Systems 12 ISSUE TITLE: RANK: Secondary Circuit Pressure Relief II ISSUE CLARIFICATION: In thé original WWER 440/230 design 2 safety relief valves are provided for each steam generator on the secondary side. These valves are not qualified to relieve water and their operability
73 CAT. ISSUE ITEM n. T ITTLE/Description ASPECT AREA CLASS REFERENCE II SECONDARY CIRCUIT PRESSURE RELIEF 602 STEAM RELIEF VALVES 0 SYSTEMS 3.6 KOZLODUY 8.1.(7) Complete planned change of steam generator relief valves. II SECONDARY CIRCUIT PRESSURE RELIEF 603 SEGREGATION OF REDUNDANT LINES 0 SYSTEMS 1.9 KOZLCOUY 8.1.(8) Segregation
74 ISSUE NUMBER: System 13 ISSUE TITLE: Reliable Isolation RANK
75 CAT. ISSUE ITEM
76 ISSUE NUMBER: Systems 14 ISSUE TITLE: RANK OF ISSUE: Ventilation/Cooling Capability III ISSUE CLARIFICATION: I&C, cable
77 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III VENTILATION / COOLING CAPABILITY III VENTILATION / COOLING CAPABILITY III VENTILATION
78 ISSUE NUMBER: Systems
79 CAT. ISSUE ITEM
80 ISSUE NUMBER: Components ISSUE TITLE: Embrittlement. Introduction BACKGROUND INFORMATION:
81 ISSUE NUMBER: Components 1 ISSUE TITLE: Embrittlement. Baseline information and analysis. RANK
82 CAT. ISSUE ITEM n. TITTLE/Descriptfon ASPECT AREA CLASS REFERENCE IV EMBRITTLEMENT - BASELINE INFORMATION IV EMBRITTLEMENT - BASELINE INFORMATION IV EMBRITTLEMENT
83 ISSUE NUMBER: Components 2 ISSUE TITLE: Embrittlement. Validation
84 CAT. ISSUE ITEM
85 ISSUE NUMBER: Components
86 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE IV EM8RITTLEHENT - FLUX REDUCTION 79 REDUCTION OF FLUENCE TO VESSEL D COMPONENTS 1.10 OESREV III Corrective measures have been taken
87 ISSUE NUMBER: Components
88 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE IV EMBRITTLEMENT
89 ISSUE NUMBER: Components
90 CAT. ISSUE III VESSEL ISI - INSPECTION TECHNIQUES III VESSEL ISI - INSPECTION TECHNIQUES III VESSEL ISI - INSPECTION TECHNIQUES III VESSEL
91 ISSUE NUMBER: Components
92 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE II VESSEL
93 ISSUE NUMBER: Components
94 CAT. ISSUE ITEM n. TITUE/Descriptlon ASPECT AREA CLASS REFERENCE III VESSEL STRESS ANALYSIS 82 VESSEL OPERATING HISTORY 0 COMPONENTS 1.15 DESREV HI Vessel operating history data, including process conditions III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS III VESSEL STRESS ANALYSIS
95 ISSUE NUMBER: Components 8 ISSUE TITLE: Leak Before Break Applicability RANK
96 CAT. ISSUE ITEM n. TITTLE/Descnptlon ASPECT AREA CLASS REFERENCE IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV IV IV LEAK BEFORE BREAK APPLICABILITY LEAK BEFORE BREAK APPLICABILITY LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV IV IV LEAK BEFORE BREAK APPLICABILITY LEAK BEFORE BREAK APPLICABILITY LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY IV LEAK BEFORE BREAK APPLICABILITY
97 CAT. ISSUE ITEM n. TITTLE/Descnption ASPECT AREA CLASS REFERENCE IV LEAK BEFORE BREAK APPLICABILITY 1104 DISSIMILAR WELD RESEARCH
98 ISSUE NUMBER: Components 9 ISSUE TITLE: Primary circuit in-service inspection RANK
99 CAT. ISSUE ITEM
100 ISSUE NUMBER: Components
101 CAT. ISSUE ITEM
102 ISSUE NUMBER: Components 11 ISSUE TITLE: Vessel Support Integrity RANK
103 CAT. ITEM n. TITTLË/Description ASPECT AREA III VESSEL SUPPORT INTEGRITY 88 INSPECTION OF VESSEL SUPPORT D+0 COMPONENTS 3.3 OESREV The reactor vessel support structure III VESSEL SUPPORT INTEGRITY
104 ISSUE NUMBER: Components 12 ISSUE TITLE: Secondary Circuit In-Service Inspection RANK OF ISSUE: II ISSUE CLARIFICATION: In-service inspection
105 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE II SECONDARY CIRCUIT IN-SERVICE INSPECTION 11 SECONDARY CIRCUIT IN-SERVICE INSPECTION II SECONDARY CIRCUIT IN-SERVICE INSPECTION II II SECONDARY CIRCUIT IN-SERVICE INSPECTION SECONDARY CIRCUIT IN-SERVICE INSPECTION II SECONDARY CIRCUIT IN-SERVICE INSPECTION
106 ISSUE NUMBER: Instrumentation
107 CAT. ISSUE ITEM n. TmLE/Description ASPECT AREA CLASS REFERENCE II II II II II II ACCIDENT MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION 28 BEYOND DBA MONITORING D I&C 4.6 DESREV III Accident monitoring for the core does not exist for beyond Design Basis Accident, e.g. level indication. Hydrogen in primary water. 109 SAFETY PARAMETER DISPLAY D I&C 2.3 DESREV The installation of a computerized safety parameter display system would be of help to the operators for transient and accident management. 125 POST ACCIDENT MONITORING 0 I&C 1.7 DESREV III Check that the range of radiation monitoring corresponds to the maximum possible post accident level. The system shall be provided with on line recording. 346 ACCIDENT MONITORING D l&c 4.6 BOHUM1CE 10.1.(8) Severe accident monitoring instruments should II ACCIDENT MONITORING INSTRUMENTATION II ACCIDENT MONITORING INSTRUMENTATION
108 ISSUE NUMBER:
109 CAT. ISSUE ITEM
110 ISSUE NUMBER: I&C 3 ISSUE TITLE: Control and protection systems interaction RANK OF ISSUE: II ISSUE CLARIFICATION: Full isolation or separation between control and protection functions of instrumentation is not provided. A fault in the non safety related instrumentation may induce the failure of safety related equipment. RELATED ITEMS: 101, 352, 668, 782, 1120 JUSTIFICATION OF RANKING: Control systems faults that
111 CAT. ISSUE ITEM
112 ISSUE NUMBER:
113 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE IV
114 ISSUE NUMBER: I&C 5 ISSUE TITLE:
115 CAT. ISSUE ITEM n TITTLE/Description ASPECT AREA CLASS III I&C SUPPORT TO OPERATION / CONTROL ROOM III
116 CAT. ISSUE ITEM n. TlTTLE/Description ASPECT AREA CLASS REFERENCE operators should
117 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE
118 ISSUE NUMBER: I&C 6 ISSUE TITLE: Interlocking RANK OF ISSUE: II ISSUE CLARIFICATION: Insufficient automatic interlocking
119 CAT. ISSUE ITEM n. TITTLE/Descriptlon ASPECT AREA CLASS REFERENCE II INTERLOCKING 11 INTERLOCKING II INTERLOCKING II INTERLOCKING II INTERLOCKING 11 INTERLOCKING II INTERLOCKING II INTERLOCKING II II INTERLOCKING INTERLOCKING II INTERLOCKING II INTERLOCKING II INTERLOCKING II II INTERLOCKING INTERLOCKING II INTERLOCKING II INTERLOCKING 11 INTERLOCKING
120 CAT. ISSUE ITEM
121 ISSUE NUMBER:
122 CAT. ISSUE ITEM n. TITTLE/Descnption ASPECT AREA CLASS REFERENCE III I&C / ELECTRICAL EQUIPMENT QUALIFICATION HI I&C / ELECTRICAL EQUIPMENT QUALIFICATION III I&C / ELECTRICAL EQUIPMENT QUALIFICATION Ut I&C / ELECTRICAL EQUIPMENT QUALIFICATION III I&C / ELECTRICAL EQUIPMENT QUALIFICATION
123 ISSUE NUMBER:
124 CAT. ISSUE ITEM
125 ISSUE NUMBER:
126 CAT. ISSUE ITEM
127 ISSUE NUMBER:
128 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE III TESTABILITY
129 ISSUE NUMBER: I&C 11 ISSUE TITLE: Control Room Habitability/Remote Shutdown Panel RANK OF ISSUE: III ISSUE CLARIFICATION: There is insufficient provision to maintain control room habitability. In case of main control room inhabitability or unavailability, there is no other centralized location from where
130 CAT. ISSUE ITEM n. TlTTLE/Description ASPECT AREA REFERENCE III CONTROL ROOM HABITABI
131 ISSUE NUMBER:
132 CAT. ISSUE ITEM
133 ISSUE NUMBER: Electrical
134 CAT. ISSUE ITEM
135 CAT. ISSUE ITEM
136 ISSUE NUMBER: Electrical 2 ISSUE TITLE: Reliability
137 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE III RELIABILITY OF ELECTRICAL EQUIPMENT III RELIABILITY OF ELECTRICAL EQUIPMENT [II RELIABILITY
138 ISSUE NUMBER: Electrical 3 ISSUE TITLE: Diesel Generator Loading RANK
139 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE IV IV DIESEL GENERATOR LOADING DIESEL GENERATOR LOADING 144 DIESEL GENERATOR RATING D ELECTRICAL 1.5 DESREV S.O.5.4 Relative low rating of 1600 ku is a concern. For LOCA conditions two Diesels are necessary to provide necessary power. IV DIESEL GENERATOR LOADING IV DIESEL GENERATOR LOADING IV DIESEL GENERATOR LOADING
140 ISSUE NUMBER: Electrical
141 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE 11! BATTERY DISCHARGE TIME 133 BATTERIES 111 BATTERY DISCHARGE TIME III BATTERY DISCHARGE TIME III BATTERY DISCHARGE TINE
142 ISSUE NUMBER: Electrical 5 ISSUE TITLE: Connection to offsite Power Supplies RANK OF ISSUE: II ISSUE CLARIFICATION: The need for manual action to restore off-site supplies following a reactor trip places unnecessary demands on the diesel generators. RELATED ITEMS (AND PRIORITIES): 141, 142, 368, 676, 813 JUSTIFICATION OF RANKING: Loss
143 CAT. ISSUE ITEM n. T!TTLE/Description ASPECT AREA CLASS REFERENCE II CONNECTION TO OFF-SITE POUER SUPPLIES U1 EXTERNAL POWER SOURCES D ELECTRICAL 4.3 DESREV Confirm that
144 ISSUE NUMBER: Accident Analysis
145 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III COMFINEHENT ANALYSIS 67 FLAP CHARACTERISTICS D SYSTEMS 3.7 DESREV B III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS III CONFINEMENT ANALYSIS
146 ISSUE NUMBER: Accident Analysis
147 CAT. ISSUE ITEM
148 ISSUE NUMBER: Accident Analysis 3 ISSUE TITLE: Severe accident analysis RANK
149 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE II SEVERE ACCIDENT ANALYSIS
150 ISSUE NUMBER: Accident Analysis
151 CAT. ISSUE ITEM
152 ISSUE NUMBER: Accident Analysis
153 CAT. ITEM
154 CAT. ISSUE II QUALIFICATION OF SAFETY ANALYSIS II II QUALIFICATION OF SAFETY ANALYSIS QUALIFICATION
155 ISSUE NUMBER: Accident Analysis 6 ISSUE TITLE: Scope
156 CAT. ISSUE ITEM
157 CAT. ISSUE ITEM
158 CAT. ISSUE ITEM
159 ISSUE NUMBER: Accident Analysis 7 ISSUE TITLE: Loss of coolant accidents RANK
160 CAT. ISSUE HEM n. TlTTLE/Oescription ASPECT AREA CLASS REFERENCE III LOSS
161 CAT. ISSUE III LOSS
162 ISSUE NUMBER: Accident Analysis 8 ISSUE TITLE: Radiological consequences RANK
163 CAT. ISSUE ITEM n, TITTLE/Descnption ASPECT AREA CLASS REFERENCE II RADIOLOGICAL CONSEQUENCES 11 RADIOLOGICAL CONSEQUENCES II II RADIOLOGICAL CONSEQUENCES RADIOLOGICAL CONSEQUENCES
164 ISSUE NUMBER: Accident Analysis 9 ISSUE TITLE: Evaluation
165 CAT. ISSUE ITEM n. TITTlE/Description ASPECT AREA CUSS REFERENCE III EVALUATION OF MODIFICATIONS III EVALUATION OF MODIFICATIONS III EVALUATION OF MODIFICATIONS
166 ISSUE NUMBER: Fire Protection
167 CAT. ISSUE ITEM
168 ISSUE NUMBER: Fire Protection
169 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III FIRE PROTECTION
170 ISSUE NUMBER: Fire Protection 3 ISSUE TITLE: Fire Protection. Inspection RANK OF ISSUE: III ISSUE
171 CAT. ISSUE ITEM
172 4. OPERATIONAL ISSUES 179
173 ISSUE NUMBER: Management
174 CAT. ISSUE ITEM
175 ISSUE NUMBER: Management 2 ISSUE TITLE: Management Development RANK
176 CAT. ISSUE ITEM
177 ISSUE NUMBER: Management
178 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE IV SAFETY CULTURE
179 ISSUE NUMBER: Management 4 ISSUE TITLE: Housekeeping RANK
180 CAT. ISSUE ITEM
181 ISSUE NUMBER: Management 5 ISSUE TITLE: Organization RANK OF ISSUE: III ISSUE CLARIFICATION: An adequate organization provides for clear responsibilities, lines of communication, and enhances the plant's ability to accomplish common goals. The structure of the organization should insure that important areas
182 CAT. ISSUE ITEM
183 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III ORGANIZATION have III ORGANIZATION III ORGANIZATION III ORGANIZATION III ORGANIZATION III ORGANIZATION III ORGANIZATION III ORGANIZATION
184 ISSUE NUMBER: Management 6 ISSUE TITLE: Modification Control RANK
185 CAT. ISSUE ITEM
186 ISSUE NUMBER: Management 7 ISSUE TITLE: Document Management RANK OF ISSUE: I ISSUE CLARIFICATION:
187 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE 1 DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT 201 STORAGE OF QUALITY RECORDS 0 HOA 1.19 BOHUNICE 1.6.(2) Quality records should be kept in fire proof cabinets and in rooms equiped with smoke detectors. I DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT I I I I DOCUMENT MANAGEMENT DOCUMENT MANAGEMENT DOCUMENT MANAGEMENT DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT 1 DOCUMENT MANAGEMENT I DOCUMENT MANAGEMENT
188 ISSUE NUMBER: Management 8 ISSUE TITLE: Configuration Management RANK
189 CAT. ISSUE ITEM n. TlULE/Oescription ASPECT AREA CLASS REFERENCE III CONFIGURATION MANAGEMENT 413 CENTRALIZED RECORD SYSTEM III CONFIGURATION MANAGEMENT III CONFIGURATION MANAGEMENT
190 ISSUE NUMBER: Management
191 CAT. ISSUE ITEM
192 ISSUE NUMBER: Management
193 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE II! QUALITY ASSURANCE 194 INDEPENDENT CHECK III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE III QUALITY ASSURANCE
194 ISSUE NUMBER: Management
195 CAT. ISSUE ITEH
196 ISSUE NUMBER: Management 12 ISSUE TITLE: Industrial Safety Practices RANK
197 CAT. ISSUE ITEM
198 ISSUE NUMBER: Management
199 CAT. ISSUE ITEM n. TITTLE/Oescrlption ASPECT AREA CLASS REFERENCE I I COHPUTER UTILIZATION COHPUTER UTILIZATION 193 I COHPUTER UTILIZATION I I I I COHPUTER UTILIZATION COHPUTER UTILIZATION COHPUTER UTILIZATION COHPUTER UTILIZATION I COMPUTER UTILIZATION I COHPUTER UTILIZATION
200 ISSUE NUMBER: Operating Procedures 1 ISSUE TITLE: Procedures. Program RANK
201 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE II PROCEDURES - PROGRAMME II PROCEDURES - PROGRAMME II PROCEDURES - PROGRAMME II PROCEDURES - PROGRAMME II PROCEDURES
202 ISSUE NUMBER: Operating Procedures 2 ISSUE TITLE: Emergency Operating Procedures RANK
203 CAT. ISSUE ITEM
204 ISSUE NUMBER: Operating Procedures
205 CAT. ISSUE ITEM
206 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III LIMITS
207 ISSUE NUMBER: Operating Procedures 4 ISSUE TITLE: Procedures. Operation RANK OF ISSUE: II ISSUE CLARIFICATION: Operating personnel should be provided with detailed instructions to control locked valves, operate systems, coordinated plant startup/shutdown, conduct shift turnovers
208 CAT. ISSUE ITEM n, TITTLE/Oescription ASPECT AREA CLASS REFERENCE II II PROCEDURES - OPERATION PROCEDURES
209 ISSUE NUMBER: Plant Operations 1 ISSUE TITLE: Surveillance Program RANK
210 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE II SURVEILLANCE PROGRAMME II II II SURVEILLANCE PROGRAMME SURVEILLANCE PROGRAMME SURVEILLANCE PROGRAMME II SURVEILLANCE PROGRAMME II SURVEILLANCE PROGRAMME II SURVEILLANCE PROGRAMME II SURVEILLANCE PROGRAMME II SURVEILLANCE PROGRAMME
211 ISSUE NUMBER: Plant Operations 2 ISSUE TITLE: Procedures. Surveillance RANK OF ISSUE: III ISSUE CLARIFICATION: Personnel should
212 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE 111 PROCEDURES - SURVEILLANCE III PROCEDURES
213 ISSUE NUMBER: Plant Operations
214 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE lit WORK CONTROL 252 TAGGING SYSTEM III UORK CONTROL III UORK CONTROL III UORK CONTROL III UORK CONTROL III UORK CONTROL III UORK CONTROL III UORK CONTROL III UORK CONTROL III WORK CONTROL III UORK CONTROL III WORK CONTROL III WORK CONTROL III UORK CONTROL III UORK CONTROL III UORK CONTROL III WORK CONTROL
215 ISSUE NUMBER: Plant Operations 4 ISSUE TITLE: Organization of Shifts RANK
216 CAT. ISSUE ITEM
217 ISSUE NUMBER: Plant Operations
218 CAT. ISSUE ITEM n. TITTLE/Descnption ASPECT AREA CLASS REFERENCE II LABELS
219 ISSUE NUMBER: Plant Operations
220 CAT. ISSUE ITEM n. TITTLE/Descrlptlon ASPECT AREA CLASS REFERENCE I CHEMISTRY 769 STRESS CORROSION MONITORING D COMPONENTS 1.10 NOVOVORONE 9.1.<2) Water chemistry of the primary circuit requires utmost attention. Aggressive impurities will
221 ISSUE NUMBER: Maintenance l ISSUE TITLE: Maintenance Program RANK
222 CAT. ISSUE ITEM n. TITTLE/Oescnption ASPECT AREA CLASS REFERENCE II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II II II MAINTENANCE PROGRAMME MAINTENANCE PROGRAMME MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II II MAINTENANCE PROGRAMME MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME II MAINTENANCE PROGRAMME
223 ISSUE NUMBER: Maintenance
224 CAT. ISSUE ITEM
225 ISSUE NUMBER: Maintenance 3 ISSUE TITLE: Equipment Material Conditions RANK OF ISSUE: IV ISSUE CLARIFICATION: Equipment should be maintained in a state of readiness so that it can reliably operate. Immediate action is required to restore safety equipment to their design conditions. RELATED ITEMS: 491, 513, 514, 799, 833, 966, 1153, 1154, 1288, 1289, JUSTIFICATION
226 CAT. ISSUE ITEM
227 ISSUE NUMBER: Maintenance 4 ISSUE TITLE: Warehouse RANK
228 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE I WAREHOUSES 530 IMPROVE WAREHOUSES 0 MAINT 1.19 KOZLODUY 4.7.(5) The existing warehouses should be improved by improving door seals and windowsand installing ventilation. I WAREHOUSES 983 SPARE PARTS CLEANNESS 0 MAINT 1.19 NOVOVORONE 4.8.(1) The centralized warehouse and the spare parts should be kept clean. I WAREHOUSES 984 STAINLESS STEEL 0 MAINT 1.19 NOVOVORONE 4.8.(2) A special store should be used for stainless steel. I WAREHOUSES 985 HOLD STORE 0 MAINT 1.19 NOVOVORONE 4.8.(3) A separate "hold" store should be set up for spare parts that await quality control checks. 238
229 ISSUE NUMBER: Training
230 CAT. ISSUE ITEM
231 CAT. ISSUE ITEM III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME 111 TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME
232 CAT. ISSUE ITEM III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME III TRAINING PROGRAMME
233 ISSUE NUMBER: Training
234 CAT. ISSUE ITEM
235 ISSUE NUMBER: Training 3 ISSUE TITLE: Training Facilities RANK
236 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE II TRAINING - FACILITIES II TRAINING
237 ISSUE NUMBER: Training
238 ISSUE ITEM n. Time/Description ASPECT AREA CLASS REFERENCE til TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL III TRAINING MATERIAL
239 ISSUE NUMBER: Training 5 ISSUE TITLE: Training Records RANK
240 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE 1 TRAINING RECORDS 211 TRAINING RECORDS 0 TO 1.19 BOHUNICE 2.1.(8) Install computerized central training records. I TRAINING RECORDS
241 ISSUE NUMBER: Emergency Planning 1 ISSUE TITLE: Emergency Response Programme RANK OF ISSUE: III ISSUE CLARIFICATION: An effective Emergency Response Programme must address all essential aspects of accident assessment and classification, on-site planning, off-site planning and coordination. RELATED ITEMS: 284, 285, 286, 287, 545, 546, 549, 556, 559, 561, 577, 578, 579, 1003, 1004, 1006, 1007, 1008, 1010, 1015, 1018, 1315, 1316, 1319 JUSTIFICATION
242 CAT. ISSUE ITEM n. TITTLE/Oescription ASPECT AREA CLASS REFERENCE III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME 284 ON SITE EMERGENCY PLAN 0 EP 5.2 BOHUNICE 6.2.(1) Comprehesive emergency plan should be prepared, including: actions to correct abnormal conditions, assessmen of potential consequences, activating emergency arrangements, recommending protective measures. It should describe the organizational units, their functions and tasks. 285 ON Off SITE INTERFACE 0 EP 5.2 BOHUNICE 6.2.(2) III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME til EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME 111 EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME 111 EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME III EMERGENCY RESPONSE PROGRAMME
243 CAT. ISSUE 1TEH
244 ISSUE NUMBER: Emergency Planning 2 ISSUE TITLE: Emergency Response Procedures RANK
245 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE 111 EMERGENCY RESPONSE - PROCEDURES III EMERGENCY RESPONSE
246 ISSUE NUMBER: Emergency Planning 3 ISSUE TITLE: Emergency Response Facilities RANK OF ISSUE: III ISSUE CLARIFICATION: Facilities and equipment should be available to properly monitor, coordinate and respond
247 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III EMERGENCY RESPONSE - FACILITIES III EMERGENCY RESPONSE
248 CAT. ISSUE ITEM n. TITTLE/Description ASPECT AREA CLASS REFERENCE III EMERGENCY RESPONSE - FACILITIES 1325 IODINE TABLETS STORAGE 0 EP 5.2 KOLA 6.4.(6) Iodine tablets should be wrapped in foil and stored in containers indicating type of tablets and expiration date. Ill EMERGENCY RESPONSE
249 ISSUE NUMBER: Emergency Planning
250 CAT. ISSUE II EMERGENCY RESPONSE
251 ISSUE NUMBER: Emergency Planning
252 CAT. ISSUE ITEM
253 RD - Reference Documents REFERENCES
254 LIST
255 THE RUSSIAN FEDERATION
256 Project Review Meeting Safety of WWER 440 Model 230 Plants 28 October to 1 November 1991 AUSTRIA Mr. G. Weimann Austrian Research Centre Seibersdorf Vienna BULGARIA Mr. B. Dimitrov Institute Energoproekt 1407 Sofia 51 Anton Ivanov blvd Mr.
257 SPAIN Mr.
258 IAEA PARTICIPANTS Mr. L. Lederman Mr. C. Almeida Mr. J. Hoehn Mr. B. Gachot Mr. R. Havel Mr. A. Erwin Ms. A. Carnino Mr. B. Moore Mr. - Scientific Secretary - NENS/SAS - Safety Assessment Section/NENS - Safety Assessment Section/NENS - Safety Assessment Section/NENS - NENF - NPP Operational Safety Services/NOSS - Advisor, NENS - NPP Operational Safety Services/NOSS
259 Steering Committee Meeting Safety
260 SPAIN Mr.
261 COMMISSION
262 IAEA PARTICIPANTS Mr. M. Rosen Mr. - DIR/NENS
CONTENTS OF THE PCSR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION
PAGE : 1 / 8 CONTENTS OF THE PCSR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION SUB-CHAPTER 1.1 INTRODUCTION SUB-CHAPTER 1.2 GENERAL DESCRIPTION OF THE UNIT SUB-CHAPTER 1.3 COMPARISON WITH REACTORS
Review and Assessment of Engineering Factors
Review and Assessment of Engineering Factors 2013 Learning Objectives After going through this presentation the participants are expected to be familiar with: Engineering factors as follows; Defense in
IAEA SAFETY STANDARDS for protecting people and the environment
IAEA SAFETY STANDARDS for protecting people and the environment DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS DRAFT SAFETY GUIDE DS 482 STATUS: STEP 11 Submission to Review
IAEA SAFETY STANDARDS for protecting people and the environment
Date: 2016-08-31 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: STEP 8a For Submission to Member States DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS
Verification and validation of computer codes Exercise
IAEA Safety Assessment Education and Training (SAET) Programme Joint ICTP- IAEA Essential Knowledge Workshop on Deterministic Safety Assessment and Engineering Aspects Important to Safety Verification
FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER P: REFERENCE OPERATING CONDITION STUDIES (PCC)
PAGE : 1 / 11 1. PASSIVE SINGLE FAILURE ANALYSIS The aim of the accident analysis in Chapter P is to demonstrate that the safety objectives have been fully achieved, despite the most adverse single failure.
Workshop Information IAEA Workshop
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Safety Assessment of General Design Aspects of NPPs (Part 2) Lecturer Lesson Lesson III III 1_2 1_2 Workshop Information IAEA
FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS. A high-capacity EBA system [CSVS] [main purge]
![FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS. A high-capacity EBA system [CSVS] [main purge]](/thumbs/88/117664573.jpg "FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS. A high-capacity EBA system [CSVS] [main purge]")
PAGE : 1 / 9 5. CONTAINMENT PURGE (EBA [CSVS]) The Reactor Building purge system comprises the following: A high-capacity EBA system [CSVS] [main purge] A low-capacity EBA system [CSVS] [mini-purge] 5.1.
DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS
SAFETY STANDARDS SERIES No. NS-G-1.10 DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY GUIDE DS 482 2016-04-20 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, C-41 (May 13)
ASVAD THE SIMPLE ANSWER TO A SERIOUS PROBLEM. Automatic Safety Valve for Accumulator Depressurization. (p.p.)
ASVAD Automatic Safety Valve for Accumulator Depressurization (p.p.) THE SIMPLE ANSWER TO A SERIOUS PROBLEM International Experts Meeting on Strengthening Research and Development Effectiveness in the
Safety Analysis: Event Classification
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Safety Analysis: Event Classification Lecturer Lesson IV 1_2 Workshop Information IAEA Workshop City, Country XX - XX Month,
DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS
SAFETY STANDARDS SERIES No. NS-G-1.10 DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY GUIDE DS 482 2016-04-20 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, C-41 (May 13)
OPERATING PROCEDURES
OPERATING PROCEDURES 1.0 Purpose This element identifies Petsec s Operating Procedures for its Safety and Environmental Management System (SEMS) Program; it applies to all Petsec operations. Petsec is
Considerations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design
Considerations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects
Enhancing NPP Safety through an Effective Dependability Management
Prepared and presented by Gheorghe VIERU, PhD Senior Scientific Nuclear Security Research Worker AREN/c.o. Institute for Nuclear Research Pitesti, ROMANIA Safety: Defence in Depth, October 2013 1 OUTLINES
UKEPR Issue 04
Title: PCSR Sub-chapter 6.8 Main steam relief train system - VDA [MSRT] Total number of pages: 16 Page No.: I / III Chapter Pilot: M. LACHAISE Name/Initials Date 25-06-2012 Approved for EDF by: A. PETIT
The Nitrogen Threat. The simple answer to a serious problem. 1. Why nitrogen is a risky threat to our reactors? 2. Current strategies to deal with it.
International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants. The simple answer to a serious problem Vienna. 6 9 June 2017
HEALTH AND SAFETY EXECUTIVE HM NUCLEAR INSTALLATIONS INSPECTORATE
HEALTH AND SAFETY EXECUTIVE HM NUCLEAR INSTALLATIONS INSPECTORATE New Reactor Generic Design Assessment (GDA) - Step 2 Preliminary Review Assessment of: Structural Integrity Aspects of AREVA/EdF EPR HM
Assessment of Internal Hazards
Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste, 12-23 October 2015 Assessment of Internal Hazards Javier Yllera Department
Workshop Information IAEA Workshop
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Risk Monitoring tools: Requirements of Risk Monitors, relation with the Living PSA, applications of Risk Monitors Lecturer Lesson
Safety Standards. of the Nuclear Safety Standards Commission (KTA)
Safety Standards of the Nuclear Safety Standards Commission (KTA) KTA 3502 (2012-11) Accident Measuring Systems (Störfallinstrumentierung) If there is any doubt regarding the information contained in this
NUBIKI Nuclear Safety Research Institute, Budapest, Hungary
System Reliability Analysis and Probabilistic Safety Assessment to Support the Design of a New Containment Cooling System for Severe Accident Management at NPP Paks Tamas Siklossy* a, Attila Bareith a,
Custom-Engineered Solutions for the Nuclear Power Industry from SOR
Custom-Engineered Solutions for the Nuclear Power Industry from SOR As the world s aging nuclear power plants continue to be challenged with maintenance and Instrumentation Solutions for the Nuclear Power
Safe management of industrial steam and hot water boilers A guide for owners, managers and supervisors of boilers, boiler houses and boiler plant
Health and Safety Executive Safe management of industrial steam and hot water boilers A guide for owners, managers and supervisors of boilers, boiler houses and boiler plant Background Accidents involving
Safety Classification of Structures, Systems and Components in Nuclear Power Plants
DS367 Draft 5.1 IAEA SAFETY STANDARDS for protecting people and the environment Date: 04/11/2008 Status: for Member States comments Reviewed in NS-SSCS Please submit your comments by 20 March 2009 Safety
Regulatory requirements with respect to Spent Fuel Pool Cooling
Regulatory requirements with respect to Spent Fuel Pool Cooling Dr. Christoph Pistner Annual Meeting on Nuclear Technology Hamburg, 12.05.2016 Important Documents Safety Requirements for Nuclear Power
Every things under control High-Integrity Pressure Protection System (HIPPS)
Every things under control www.adico.co info@adico.co Table Of Contents 1. Introduction... 2 2. Standards... 3 3. HIPPS vs Emergency Shut Down... 4 4. Safety Requirement Specification... 4 5. Device Integrity
MDEP Common Position No AP
MDEP Validity: until net update or archiving MDEP Common Position No AP1000-01 Related to : AP1000 Working Group activities THE DESIGN AND USE OF EXPLOSIVE - ACTUATED (SQUIB) VALVES IN NUCLEAR POWER PLANTS
Nuclear safety Lecture 4. The accident of the TMI-2 (1979)
Nuclear safety Lecture 4. The accident of the TMI-2 (1979) Ildikó Boros BME NTI 27 February 2017 The China Syndrome Opening: 16 March 1979 Story: the operator of the Ventana NPP tries to hide the safety
IAEA Headquarters in Vienna, Austria 6 to 9 June 2017 Ref No.: CN-251. Ivica Bašić, Ivan Vrbanić APoSS d.o.o.
Overview And Comparison Of International Practices Concerning The Requirements On Single Failure Criterion With Emphasize On New Water-Cooled Reactor Designs Presentation on International Conference on
Complementarity between Safety and Physical Protection in the Protection against Acts of Sabotage of Nuclear Facilities
Complementarity between Safety and Physical Protection in the Protection against Acts of Sabotage of Nuclear Facilities Robert Venot Institut de Radioprotection et de Sûreté Nucléaire 77-83, avenue du
-. 30ýv. Entergy ARKANSAS NUCLEAR ONE - UNIT I IMPROVED TECHNICAL SPECIFICATIONS SUBMITTAL. 05/01101 Supplement Volume 2 of 2. (Sections 3.7 and 3.
ARKANSAS NUCLEAR ONE - UNIT I IMPROVED TECHNICAL SPECIFICATIONS SUBMITTAL -. 30ýv May 1, 2001 05/01101 Supplement Volume 2 of 2 (Sections 3.7 and 3.8) Entergy MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam
SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 440/270 REACTOR
PROCEEDINGS OF THE YEREVAN STATE UNIVERSITY Physical and Mathematical Sciences 216, 2, p. 57 62 P h y s i c s SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 44/27
PROCEDURES FOR REPAIRS TO ASME NV STAMPED PRESSURE RELIEF DEVICES OF NUCLEAR SAFETY RELATED PRESSURE RELIEF VALVES
NB16 0603 NR Task Group 1 9 16 1. One update by NR task group page 3: 7/17/19 2. Two updates to S6.1 and S6.3 on page 1: 7/19/17 SUPPLEMENT 6 PROCEDURES FOR REPAIRS TO ASME NV STAMPED PRESSURE RELIEF DEVICES
DeZURIK. KSV Knife Gate Valve. Safety Manual
KSV Knife Gate Valve Safety Manual Manual D11035 August 29, 2014 Table of Contents 1 Introduction... 3 1.1 Terms... 3 1.2 Abbreviations... 4 1.3 Product Support... 4 1.4 Related Literature... 4 1.5 Reference
DISTRIBUTION LIST. Preliminary Safety Report Chapter 19 Internal Hazards UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF
Rev: 000 Page: 2 / 20 DISTRIBUTION LIST Recipients GNS Executive GNS all staff Cross Box GNS and BRB all staff CGN EDF Regulators Public Rev: 000 Page: 3 / 20 SENSITIVE INFORMATION RECORD Section Number
DeZURIK Double Block & Bleed (DBB) Knife Gate Valve Safety Manual
Double Block & Bleed (DBB) Knife Gate Valve Safety Manual Manual D11044 September, 2015 Table of Contents 1 Introduction... 3 1.1 Terms... 3 1.2 Abbreviations... 4 1.3 Product Support... 4 1.4 Related
Technical Specification Bases Update to the NRC for Period Dated
...~Entergy Entergy Operations, Inc. 7003 Bald Hill Road PO. Box 756 Port Gibson, MS 39150 Tel 601 437 6299 Christina L. Perino Manager Licensing GNRO-2009/00017 March 4, 2009 U.S. Nudear Regulatory Commission
Safety and efficiency go hand in hand at MVM Paks NPP
International Forum Atomexpo 2018 Safety and efficiency go hand in hand at MVM Paks NPP József Elter MVM Paks Nuclear Power Plant Ltd. Hungary Start up Four of the VVER-440/V213 unit Power units up-rate
LECTURE 3 MAINTENANCE DECISION MAKING STRATEGIES (RELIABILITY CENTERED MAINTENANCE)
LECTURE 3 MAINTENANCE DECISION MAKING STRATEGIES (RELIABILITY CENTERED MAINTENANCE) Politecnico di Milano, Italy piero.baraldi@polimi.it 1 Types of maintenance approaches Intervention Unplanned Planned
FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER F: CONTAINMENT AND SAFEGUARD SYSTEMS 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS])
![FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER F: CONTAINMENT AND SAFEGUARD SYSTEMS 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS])](/thumbs/78/77361990.jpg "FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER F: CONTAINMENT AND SAFEGUARD SYSTEMS 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS])")
PAGE : 1 / 16 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS]) 7.0. SAFETY REQUIREMENTS 7.0.1. Safety functions The main functions of the EVU system [CHRS] are to limit the pressure inside the containment
Solenoid Valves used in Safety Instrumented Systems
I&M V9629R1 Solenoid Valves used in Safety Instrumented Systems Operating Manual in accordance with IEC 61508 ASCO Valves Page 1 of 7 Table of Contents 1 Introduction...3 1.1 Terms and Abbreviations...3
DeZURIK. KGC Cast Knife Gate Valve. Safety Manual
KGC Cast Knife Gate Valve Safety Manual Manual D11036 August 29, 2014 Table of Contents 1 Introduction... 3 1.1 Terms... 3 1.2 Abbreviations... 4 1.3 Product Support... 4 1.4 Related Literature... 4 1.5
HTR Systems and Components
IAEA Course on HTR Technology Beijing, 22-26.October 2012 HTR Systems and Components Dr. Gerd Brinkmann Dieter Vanvor AREVA NP GMBH Henry-Dunant-Strasse 50 91058 Erlangen phone +49 9131 900 96840/95821
10. SYSTEM ANALYSIS. The assessment consist of two elements: Safety Analysis Report and an independent Review of Safety Report.
10. SYSTEM ANALYSIS Several projects related to the safety analysis of the Ignalina NPP or its safety systems have been performed. The joint Lithuanian - Sweden Barselina project - the first probabilistic
Severe Accident Management Programmes for Nuclear Power Plants
DS 483: Mode 2 27 March 2017 IAEA SAFETY STANDARDS for protecting people and the environment STEP 11: Approval by the relevant review Committees Reviewed in NSOC (Asfaw) Severe Accident Management Programmes
Loss of Normal Feedwater Analysis by RELAP5/MOD3.3 in Support to Human Reliability Analysis
Loss of Normal Feedwater Analysis by RELAP5/MOD3.3 in Support to Human Reliability Analysis ABSTRACT Andrej Prošek, Borut Mavko Jožef Stefan Institute Jamova cesta 39, SI-1 Ljubljana, Slovenia Andrej.Prosek@ijs.si,
Nuclear Safety. Module 3 DEFENSE IN DEPTH. Reacu03.ppt. Slide!
Nuclear Safety Module 3 DEFENSE IN DEPTH Slide! Reacu03.ppt Defense in Depth The principle that multiple, redundant nuclear safety provisions are required to protect workers, the public and the environment
ACCIDENT MANAGEMENT AND EPR AT DUKOVANY NPP
ACCIDENT MANAGEMENT AND EPR AT DUKOVANY NPP 27-29 September 2017 Vienna IAEA Miroslav Trnka OVERVIEW General EOPs and SAMGs (changes) DAM (FLEX) EDMG Equipment (new + ongoing projects) Staff (drills and
RISKAUDIT GRS - IRSN Safety assessment of the BELENE NPP
RISKAUDIT GRS - IRSN Safety assessment of the BELENE NPP Bulatom Conference 2010 Bulgarian Nuclear Energy National, Regional and World Energy Safety 9th -11th June 2010, Riviera complex, Varna Système
Evaluation and Demonstration of Safety of Decommissioning of
Evaluation and Demonstration of Safety of Decommissioning of Research Reactors Borislava Batandjieva, IAEA Research Reactor Decommissioning Demonstration Project (R2D2P) 26-30 June 2006, Manila, Philippines
Lockout/Tagout Training Overview. Safety Fest 2013
Lockout/Tagout Training Overview Safety Fest 2013 Purpose of Lockout/Tagout The standard covers the servicing and maintenance of machine and equipment in which the unexpected energization or start up of
SHUTDOWN SYSTEMS: SDS1 AND SDS2
Chapter 12 SHUTDOWN SYSTEMS: SDS1 AND SDS2 12.1 INTRODUCTION Up to this point we have looked with great details at the reactor regulating system. In order to better understand the overall design of a CANDU
BPZM-MRD Nitrogen Injection System
BPZM-MRD Nitrogen Injection System (Transformer protector) Overview BPZM-MRD Nitrogen Injection Explosion Prevention & Fire Protection System became more advanced fire protection and explosion prevention
EMERGENCY CORE COOLING SYSTEM SIMPLIFICATION
EMERGENCY CORE COOLING SYSTEM SIMPLIFICATION XA9846601 R.S. HART Sheridan Park Research Community, Atomic Energy of Canada Ltd, Mississauga, Ontario D.B. RHODES Chalk River Laboratories, Atomic Energy
Periodical surveys of cargo installations on ships carrying liquefied gases in bulk
(June 1999) (Rev.1 Mar 2006) (Rev.2 May 2007) (Rev.3 Mar 2010) (Corr.1 Feb 2011) (Rev.4 Oct 2013) Periodical surveys of cargo installations on ships carrying liquefied gases in bulk 1 General 1.1 Scope
DRAFT REGULATORY GUIDE DG-1074
Draft Guide DG-1074 - December 1998 Page 1 of 55 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REGULATORY RESEARCH DRAFT REGULATORY GUIDE December 1998 Division 1 Draft DG-1074 Contact: E.L. Murphy
Recent Research on Hazards PSA
Recent Research on Hazards PSA Marina Röwekamp, Hartmut Holtschmidt, Michael Türschmann Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh IEM8 - International Experts Meeting on Strengthening
FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS 2. VOLUME AND CHEMICAL CONTROL (RCV [CVCS])
![FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS 2. VOLUME AND CHEMICAL CONTROL (RCV [CVCS])](/thumbs/90/103043958.jpg "FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS 2. VOLUME AND CHEMICAL CONTROL (RCV [CVCS])")
PAGE : 1 / 16 2. VOLUME AND CHEMICAL CONTROL (RCV [CVCS]) 2.0. SAFETY REQUIREMENTS 2.0.1. Safety functions 2.0.1.1. Control of reactivity In normal operation, the RCV [CVCS] regulates and adjusts (jointly
An Improved Modeling Method for ISLOCA for RI-ISI and Other Risk Informed Applications
An Improved odeling ethod for ISLOCA for RI-ISI and Other Risk Informed Applications Young G. Jo 1) 1) Southern Nuclear Operating Company, Birmingham, AL, USA ABSTRACT In this study, an improved modeling
FP15 Interface Valve. SIL Safety Manual. SIL SM.018 Rev 1. Compiled By : G. Elliott, Date: 30/10/2017. Innovative and Reliable Valve & Pump Solutions
SIL SM.018 Rev 1 FP15 Interface Valve Compiled By : G. Elliott, Date: 30/10/2017 FP15/L1 FP15/H1 Contents Terminology Definitions......3 Acronyms & Abbreviations...4 1. Introduction...5 1.1 Scope.. 5 1.2
HUMAN FACTORS CHECKLIST
HUMAN FACTORS CHECKLIST Item I. Housekeeping and General Work Environment 1 Are adequate signs posted near maintenance, cleanup, or staging areas to warn workers of special or unique hazards associated
Periodic Survey of Fuel Installations on Ships other than Liquefied Gas Carriers utilizing gas or other low flash point fuels
(Jan 2017) Periodic Survey of Fuel Installations on Ships other than Liquefied Gas Carriers utilizing gas or other low flash point fuels CONTENTS 1. Application 2. Special Survey 2.1 Schedule 2.2 Scope
Process Safety Management Of Highly Hazardous Chemicals OSHA 29 CFR
Process Safety Management Of Highly Hazardous Chemicals OSHA 29 CFR 1910.119 PSM - Definition Not all refining hazards are caused by the same factors or involve ve the same degree of potential damage.
DISTRIBUTION LIST. Preliminary Safety Report Chapter 7 Safety Systems UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF
Rev: 000 Page: 2 / 82 DISTRIBUTION LIST Recipients GNS Executive GNS all staff Cross Box GNS and BRB all staff CGN EDF Regulators Public Rev: 000 Page: 3 / 82 SENSITIVE INFORMATION RECORD Section Number
Energy Control. Suite 2A, 55 Frid Street Hamilton, ON L8P 4M3 office: cell:
Energy Control Suite 2A, 55 Frid Street Hamilton, ON L8P 4M3 office: 905.577.0303 cell: 905.977.0210 consultant@staffaid.ca www.staffaid.com Safety, Energy Control, Power Lockout & Function Test Procedures
Record of Assessment OFFICER IN CHARGE OF AN ENGINEERING WATCH
Record of Assessment for OFFICER IN CHARGE OF AN ENGINEERING WATCH Candidate s Name Candidate s Signature Candidate s Mariner Reference NOTE TO QUALIFIED ASSESSOR(S): In performing your function as a Qualified,
SEMS II: BSEE should focus on eliminating human error
SEMS II: BSEE should focus on eliminating human error How US companies can prevent accidents on start-ups and shut-downs by using valve interlocks The proposed changes to BSEE s SEMS (Safety and Environmental
2600T Series Pressure Transmitters Plugged Impulse Line Detection Diagnostic. Pressure Measurement Engineered solutions for all applications
Application Description AG/266PILD-EN Rev. C 2600T Series Pressure Transmitters Plugged Impulse Line Detection Diagnostic Pressure Measurement Engineered solutions for all applications Increase plant productivity
Reliability of Safety-Critical Systems Chapter 4. Testing and Maintenance
Reliability of Safety-Critical Systems Chapter 4. Testing and Maintenance Mary Ann Lundteigen and Marvin Rausand mary.a.lundteigen@ntnu.no RAMS Group Department of Production and Quality Engineering NTNU
CASE STUDY. Compressed Air Control System. Industry. Application. Background. Challenge. Results. Automotive Assembly
Compressed Air Control System Industry Automotive Assembly Application Savigent Platform and Industrial Compressed Air Systems Background This automotive assembly plant was using over 40,000 kilowatt hours
Control Performance: An Imperative for Safety
Control Performance: An Imperative for Safety George Buckbee 2014 ExperTune, a Metso Company Page 1 Control Performance: An Imperative for Safety George Buckbee, ExperTune 2014 ExperTune, a Metso Company
OBJECTIVE 22: EMERGENCY WORKERS, EQUIPMENT, AND VEHICLES - MONITORING AND DECONTAMINATION
OBJECTIVE Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment, and vehicles. INTENT This objective is derived from NUREG-0654 which provides that
Hazard Operability Analysis
Hazard Operability Analysis Politecnico di Milano Dipartimento di Energia HAZOP Qualitative Deductive (search for causes) Inductive (consequence analysis) AIM: Identification of possible process anomalies
LOCKOUT/TAGOUT PROGRAM
Santa Clarita Community College District LOCKOUT/TAGOUT PROGRAM Revised March 2018 TABLE OF CONTENTS PURPOSE... 3 COMPLIANCE...4 DEFINITIONS...5 SECTION I - ENERGY CONTROL PROCEDURES... 7 SECTION II -
REDUNDANT PROPULSION SHIPS RULES FOR CLASSIFICATION OF NEWBUILDINGS DET NORSKE VERITAS SPECIAL EQUIPMENT AND SYSTEMS ADDITIONAL CLASS PART 6 CHAPTER 2
RULES FOR CLASSIFICATION OF SHIPS NEWBUILDINGS SPECIAL EQUIPMENT AND SYSTEMS ADDITIONAL CLASS PART 6 CHAPTER 2 REDUNDANT PROPULSION JANUARY 1996 CONTENTS PAGE Sec. 1 General Requirements... 5 Sec. 2 System
Requirements for Reduced Supervision of Power Plants, Thermal Liquid Heating Systems, and Heating Plants
the pressure equipment safety authority Requirements for Reduced Supervision of Power Plants, Thermal Liquid Heating Systems, and Heating Plants AB-528 Edition 2, Revision 1 Issued 2016-09-12 Table of
AP1000 European 19. Probabilistic Risk Assessment Design Control Document
APPENDIX 19E SHUTDOWN EVALUATION 19E.1 Introduction Westinghouse has considered shutdown operations in the design of the A1000 nuclear power plant. The AP1000 defense-in-depth design philosophy to provide
SPR - Pneumatic Spool Valve
SIL SM.008 Rev 7 SPR - Pneumatic Spool Valve Compiled By : G. Elliott, Date: 31/08/17 Contents Terminology Definitions:... 3 Acronyms & Abbreviations:... 4 1.0 Introduction... 5 1.1 Purpose & Scope...
Lockout / Tag out Program
Lockout / Tag out Program Presented by DOSHTI www.doshti.com You will learn Purpose of Lockout- Tag out Requirements for LOTO Types of Hazardous Energy Procedures for LOTO The OSHA Standard for the Control
Field Evaluation of ASTM E in Relation to Control Room Habitability Testing and Boundary Maintenance in Nuclear Power Plants.
Field Evaluation of ASTM E741-00 in Relation to Control Room Habitability Testing and Boundary Maintenance in Nuclear Power Plants. Presented By Clinton B. Summers Eric M. Banks NUCON International, Inc.
How to reinforce the defence-indepth in NPP by taking into account natural hazards?
How to reinforce the defence-indepth in NPP by taking into account natural hazards? Caroline LAVARENNE Karine HERVIOU Patricia DUPUY Céline PICOT IAEA 21-24 October 2013, Vienna Introduction The DiD has
PASSENGER SHIPS Guidelines for preparation of Hull Structural Surveys
(Feb 2010) PASSENGER SHIPS Guidelines for preparation of Hull Structural Surveys Contents 1 Introduction 2 Preparations for Survey 2.1 General 2.2 Conditions for survey 2.3 Access to structures 2.4 Survey
MANUAL DIRECT PURGE OPTION. UNION Instruments GmbH CWD2005 PLUS. General information, safety standards and regulations for direct purge option
MANUAL DIRECT PURGE OPTION UNION Instruments GmbH CWD2005 PLUS General information, safety standards and regulations for direct purge option Version: V1.00 Stand: 24.03.2010 Union Instruments GmbH Zeppelinstr.
Table 6: Schedule of Operational Commitments
Page 26 of 46 Table 6: Schedule of s OC 1558.1 OC 1558.2 OC 1560.1 OC 1560.2 OC 1560.3 OC 1560.4 OC 1560.5 OC 1560.6 Close out Requir This restriction was complied with prior to the core offload. Completed
KOMPRESSOREN COMPRESSORS KAESER AIR SERVICE Our Services An Overview
KOMPRESSOREN Our Services An Overview Fully equipped 100% quality and service One of the key requirements for any compressed air application is maximum compressed air availability. This is achieved however
Reliability of Safety-Critical Systems Chapter 10. Common-Cause Failures - part 1
Reliability of Safety-Critical Systems Chapter 10. Common-Cause Failures - part 1 Mary Ann Lundteigen and Marvin Rausand mary.a.lundteigen@ntnu.no &marvin.rausand@ntnu.no RAMS Group Department of Production
Electrical, electronic and control engineering at the operational level
STCW Code Table A-III/6 Specification of minimum standard of for electro-technical officers Ref: https://www.edumaritime.net/stcw-code Source: IMO Function: Electrical, electronic and control engineering
Health and Safety Executive. Key aspects of HS(G) 253. Andrew Hall HID CI 1G. HM Specialist Inspector (Mechanical)
Health and Safety Executive Key aspects of HS(G) 253 Andrew Hall HID CI 1G HM Specialist Inspector (Mechanical) Human Factors Human Failures can be grouped into: Errors And Violations Errors are not intended
NORMAL OPERATING PROCEDURES Operating Parameter Information
Operating Parameter Information Each operator performing the normal operating procedures (routine checks) of the facility should be familiar with the current normal operating parameters of all systems
23.1 Functions, Basic Configuration, and Interfaces
23 (6.6.D) SF 6 and Other Special Gases 23.1 Functions, Basic Configuration, and Interfaces 23.1.1 Functions The primary function performed by the SF 6 and other special gases system is to provide SF 6
The «practical elimination» approach for pressurized water reactors
The «practical elimination» approach for pressurized water reactors V. TIBERI K.HERVIOU International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water
Removal of hydraulic load holding valve incident causing injury
Removal of hydraulic load holding valve incident causing injury Preface In regards to the incident involving injury caused by an uncontrolled release of energy, I will offer several recommendations which
Preliminary Failure Mode and Effect Analysis for CH HCSB TBM
Preliminary Failure Mode and Effect Analysis for CH HCSB TBM Presented by: Chen Zhi Contributors by HCSB TBM Safety Group, in China June 21, 2007 E-mail: chenz@swip.ac.cn Outline Introduction FMEA Main
EXPERIMENTAL SUPPORT OF THE BLEED AND FEED ACCIDENT MANAGEMENT MEASURES FOR VVER-440/213 TYPE REACTORS
International Conference Nuclear Energy for New Europe 22 Kranjska Gora, Slovenia, September 9-12, 22 www.drustvo-js.si/gora22 EXPERIMENTAL SUPPORT OF THE BLEED AND FEED ACCIDENT MANAGEMENT MEASURES FOR
Reliability Assessment of the Whistler Propane Vaporizers
Reliability Assessment of the Whistler Propane Vaporizers Prepared for: Terasen & Fransen Engineering Prepared by: ClearSky Risk Management Inc. 815 23 rd Ave East Vancouver, BC V6B 5Z3 Phone: 604.899.1470
Effects of Delayed RCP Trip during SBLOCA in PWR
Effects of Delayed RCP Trip during SBLOCA in PWR Javier Montero Technical University of Madrid, Alenza 4, 28003, Madrid, Spain fj.montero@alumnos.upm.es Cesar Queral, Juan Gonzalez-Cadelo cesar.queral@upm.es,
Safety Engineering - Hazard Identification Techniques - M. Jahoda
Safety Engineering - Hazard Identification Techniques - M. Jahoda Hazard identification The risk management of a plant 2 Identification of the hazards involved in the operation of the plant, due to the
RULES PUBLICATION NO. 119/P
RULES PUBLICATION NO. 119/P PERIODIC SURVEYS OF FUEL INSTALLATIONS ON SHIPS OTHER THAN LIQUEFIED GAS CARRIERS UTILIZING GAS OR OTHER LOW FLASH POINT FUELS 2019 January Publications P (Additional Rule Requirements)
LOCKOUT SYSTEM AND POLICIES
LOCKOUT SYSTEM AND POLICIES Lockout System Purpose Employees health and safety takes top priority. Isolating hazardous energy to prevent sudden and unexpected energisation of machines, equipment, and processes