SAFETY ASSESSMENT OF EMERGENCY ELECTRIC POWER SYSTEMS FOR NUCLEAR POWER PLANTS
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1 IAEA-TECOOC-390 SAFETY ASSESSMENT OF EMERGENCY ELECTRIC POWER SYSTEMS FOR NUCLEAR POWER PLANTS A MANUAL ON THE USE OF IAEA SAFETY SERIES No.50-SG-D7: EMERGENCY POWER SYSTEMS AT NUCLEAR POWER PLANTS A TECHNICAL DOCUMENT ISSUED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1986
2 SAFETY ASSESSMENT
3 ALL PLEASE BE AWARE THAT
4 The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be obtained from IN IS Clearinghouse International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100,
5 FOREWORD
6 CONTENTS I. PREFACE... 7 II. INTRODUCTION...
7 4. EQUIPMENT AND COMPONENTS DISTRIBUTION SYSTEM SWITCHING COMPONENTS STANDBY ELECTRIC POWER SUPPLY UNITS AND SUPPORT SYSTEMS...
8 I. PREFACE
9 the plant supplier
10 should include
11 (3) The third part of the assessment deals with the adequacy of the systems as constructed on site. It refers to the QA programme including inspection
12 H. INTRODUCTION This paper
13 ffl. SAFETY ASSESSMENT REVIEW GUIDANCE aware As a starting point of his review, the safety assessor must become
14 Table
15 the forword
16 1. OFF-SITE
17 forced outage frequency of the nuclear unit to an unacceptable level, given
18 following:
19
20 2. ON-SITE
21 Single Failure
22 Some components
23 2.3 INDEPENDENCE AND PHYSICAL SEPARATION Basis for Acceptance Code, sections 2.10, 2.12 ^ SG-D7, relevant parts of sections 4.1, 4.2, 4.3, 4.4, , À-3.2, A-4, in particular A.4.4 Assessment Questions
24 separation
25 (4) Are the components and equipment for the EEPS housed and/or otherwise protected so as to remain functional against the direct and consequential effects (including the failure of unqualified equipment and structures) of tornados, hurricanes, tsunami and seiches, i.e., of high winds, missiles, floods, etc,
26 contain
27
28 the nuclear power station. In order to specify acceptable electrical parameters for the EEPS several aspects have to be considered including: Load surveys
29
30
31 2.8.4 Voltage Considerations System voltage studies
32
33 Proper coordination of protective devices allows energisation and operation of the EEPS, start-up and operation of required loads, and the selective isolation of faults so as to localise the disturbance and minimise the effects on the EEPS. Short circuit studies are also performed for the EEPS and are used to:
34 (5) Are the protective device ratings and capabilities adequate for the maximum overload and short circuit current service for which they are applied under all credible conditions?
35 2.10 SHARING
36 conform with the requirements related to redundancy, electrical and physical independence contained in sections 2.2 and 2.3 conformed to? 2.11 INSTRUMENTATION, MONITORING AND CONTROL OF THE EEPS Basis
37 2.12 IDENTIFICATION
38 of the components of the system and the operability of the EEPS as a whole in a manner as close to design as practicable?
39
40 3. ON-SITE
41 (2) Does the d-c system conform to the design principles, requirements and acceptance criteria of Section 2? (3) Does the d-c system meet the single failure criterion? (4) Do the batteries, battery chargers and inverters conform to the required capacities stated above?
42
43
44 accident conditions should show that the diesel engines will perform according to the required power output taking into account start up time and electrical load sequence programme.
45 (6) What measures have been taken to avoid common cause failures in more than
46
47 (3) Is the storage volume in accordance with consumption calculations
48 Assessment Questions
49 (3) Are there adequate measures in the control room to indicate any battery room ventilation defects?
50
51
52 (2) Are the penetrations compatible with the cables which are leading
53 5. AD DIT ION AL CON SIDE RAT ION S
54 Basis for Acceptance SG-D7, section A-3.7 Assessment Questions
55 Assessment Questions (1) Is emergency lighting provided at strategic locations as identified and described above? (2) Is the emergency lighting provided for the control room independent of normal lighting?
56 IV. REFERENCE LIST OF RECOMMENDED INFORMATION FOR THE SAFETY ASSESSMENT This chapter provides information
57 It should also
58 Documentation to be submitted TABLE 1
59 o\ o Documentation
60 Documentation to be submitted by applicant Reference
61 CCv K) Documentation to be submitted by applicant
62 2.12 Identification of Equipment, Components end Documents 2.13 Provisions
63 o\ -f». Documentation
64 Documentation to be submitted
65 ON Documentation
66 Documentation to be submitted
67 OO Documentation
68 Documentation to be submitted
69 L BIBLIOGRAPHY objectives. The bibliography provided in this chapter is to serve 'two
70 FEDERAL REPUBLIC OF GERMANY VDE Standards, obtainable from VDE-Verlag GmbH, Bismarckstrasse
71 Other Guidelines obtainable from Deutsches Institut für Normung e.v., Postfach 1107, D-1000 Berlin
72 KTA No. *2206 *2207 Title Auslegung von Kernkraftwerken gegen Blitzeinwirkungen (Draft) (Design *3403 *3501 *3504 * * * * *3703 *3704 *3705
73 KTA No. Title *3706 Nachweis der Beständigkeit von elektrischen Einrichtungen unter Störfallbedingungen (Resistance of Electrical Equipment for Incident Conditions) *3904 Warte, Notsteuerstelle und örtliche Leitstände in Kernkraftwerken (6/85) (Control Room
74 FRANCE REGLES FONDAMENTALES DE SURETE (RFS) ETABLIES PAR LE SERVICE CENTRAL
75 R.F.S IV.2.b
76 N.F.C
77
78 UNITED KINGDOM HM Nuclear Installations Inspectorate Safety Assessment Principles for Nuclear Power Plants ISBN
79 UNITED STATES
80 Division 1 Regulatory Guides (RG) Power Reactors RG No. Titie 1.6 Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Rev.O, 3/71) 1.9 Selection of Diesel Generator Set Capacity for Standby Power Supplies (Rev. 0, 3/71) 1.22 Periodic Testing
81 IEEE
82 IEEE
83 IEEE
84 No. Title *C Schedules
85 INTERNATIONAL ELECTROTECHNICAL COMMISSION IEC Publications available from IEC Central Office, 3 rue de Varembé, 1211 Geneva 20, Switzerland IEC
86 lec No. Title *300 Reliability
87 LIST OF PARTICIPANTS
STANDARD REVIEW PLAN
NUREG-0800 (Formerly NUREG-75/087),jEt R E14 t STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION, U.s NUCLEAR REGULATORY COMMISSION 8.1 ELECTRIC POWER - INTRODUCTION REVIEW RESPONSIBILITIES Primary
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