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| AP600 DOCUMENT COVER SHEET !
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| TDC: IDS: 1 S {
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| Form 58202G(5/94)
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| AP600 CENTRAL FILE USE ONLY: l RFS*: RFS ITEM #-
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| AP600 DOCUMENT NO. REVISION NO.
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| m ASSIGNED TO Control Copy # 1 Q GW-GL-021 10 Page 1 of N/A /UAG V !
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| ALTERNATE DOCUMENT NUMBER: 'NORK BREAKDOWN #: 3.2.3 i DESIGN AGENT ORGANIZATION: Westinghouse Electric Corporation !
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| , TITLE: AP600 Standard Safety Analysis Report (VOLUMES 111) l 1
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| I ATTACHMENTS: DCP #/REV INCORPORATED IN THIS DOCUMENT REVISION:
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| CALCULATION / ANALYSIS
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| ==REFERENCE:==
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| ELECTRONIC FILENAME ELECTRONIC FILE FORMAT ELECTRONIC FILE DESCRIPTION (C) WESTINGHOUSE ELECTRIC CORPORATION 1992 1996 0 WESTINGHOUSE PROPRIETARY CLASS 2 This document contains information propnetary to Westinghouse Electric Corporation; it is submrtted in confidence and is to be used solely for the purpose for which it is furnished and returned upon request. This document and such information is not to be reproduced, transmitted, disclosed or used otherwise in whole or in part without prior written authorization of Westinghouse Electric Corporation. Energy Systems Business Unit, subject to the legends contained hereof.
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| O WESTINGHOUSE PROPRIETARY CLASS 2C 1 This document is the property of and contains Proprietary Information owned by Westinghouse Electric Corporation and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you. l 0 WESTINGHOUSE CLASS 3 (NON PROPRIETARY) !
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| COMPLETE 1 IF WORK PERFORMED UNDER DESIGN CERTIFICATION Q3 COMPLETE 2 IF WORK PERFORMED I UNDER FOAKE.
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| 1 DOE DESIGN CERTIFICATION PROGRAM - GOVERNMENT LIMITED RIGHTS STATEMENT ISee page 21 Copyright statement: A license is reserved to the U.S. Government under contract DE ACO3-90SF18495.
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| O DOE CONTRACT DELIVERABLES (DELIVERED DATA)
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| Subject to specified exceptions, disclosure of this data is restncted until September 30,1995 or Design Certification under DOE contract DE-ACO3 90SF18495, whichever is later.
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| EPRI CONFIDENTIAL: NOTICE: 1E 2 3 4 5 CATEGORY: A@ B C D E F 2 ARC FOAKE PROGRAM - ARC LIMITED RIGHTS STATEMENT ISee page 21 Copyright statement: A heense is reserved to the U.S. Government under contract DE-FCO2 NE34267 and subcontract ARC 93-3-SC-001.
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| O ARC CONTRACT DELIVERABLES (CONTRACT DATA)
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| Subsect to specified exceptions, disclosure of this data is restry under ARC Subconty ARC 93 3-SC-001.
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| ORIGINATOR SIGNATURE /DATE M. A. Lindgren , - / ao fg "AP600 RESPONSIBLE MANAGER SIGNATUR
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| * kPPROVAL (IATE /
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| B A MCintyre j, [ n ,pp,pg k proval of the responsible manager signifies that document is complete. all r% ired reviews are complete, electronic file is attached and document is released for use. _
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| 9612270015 961219 P0t ADOCK 05200003 A PDR
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| AP600 DOCUMENT COVER SHEET P:g12 Form 58202G(5/94) LIMITED RIGHTS STA TEMENTS DOE GOVERNMENT LIMITED RIGHTS STATEMENT (A) These data are submitted with limited rights under government contract No. DE.ACO3-90SF18495, These data may be reproduced and used by the government with the express limitation that they will not, wrthout written permission of the contractor, be used for purposes of manuf acture* nor disclosed outside the government; except that the government may disclose these data outside the government for the following purposes, if any, provided that the government makes such disclosure subject to prohibition against further use and disclosure:
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| (1) This
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| * Proprietary Data" may be disclosed for evaluation purposes under the restrictions above.
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| (!!) The " Proprietary Data" may be disclosed to the Electnc Power Research Institute (EPRI), electric utility representatives and their direct consultants, excluding direct commercial competitors, and the DOE National Laboratones under the prohibitions and restnctions above.
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| (8) This notice shall be marked on any reproduction of these data, in whole or in part.
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| ARC LIMITED RIGHTS STATEMENT:
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| This propnetary data, furnished under Subcontract Number ARC-93-3-SC-001 with ARC may be duplicated and used by the government and ARC, subject to the limitations of Article H-17.F. of that subcontract, with the express lim;talions that the propnetary data may not be disclosed outside the government or ARC, or ARC's Class 1 & 3 members or EPRIor be used fer purposes of manufacture without prior permission of the Subcontractor, except that further disclosure or use may be made solely f" ine following purposes:
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| This proprietary data may be disclosed to other than commercial competites of Subcor P .or evaluation purposes of this subcontract under the restriction that the proprietary data be retained in confidence % not be fura esclosed, and subject to the terms of a non-disclosure agreement between the Subcontractor and that organizatm, t w:luding DOE and its contractors.
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| DEFINITIONS CONTRACTIDELIVERED DATA - Consists of documents (e.g, specifications, drawings, reports) which are generated under the DOE or ARC contracts which contain no background proprietary sata, EPRI CONFIDENTIALITY / OBLIGATIONNOTICES NOTICE 1: The data in this document is subject to no confidentiality obligations.
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| NOTICE 2: The data in this document is propnetary and confidential to Westinghouse Electnc Corporation and/or rts Contractors. It is forwarded to recipient under an obligation of Confidence and Trust for limited purposes only. Any use, disclosure to unauthonzed persons, or copying of this document or parts thereof as prohibited except as agreed to in advance by the Electnc Power Research institute (EPRI)
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| (nd Westinghouse Electnc Corporation. Recipient of this data has a duty to inquire of EPRI and/or Westinghouse as to the uses of the information contained herein that are permitted. l NOTICE 3: The data in this document is prop 6etary and confidential to Westinghouse Electric Corporation and/or its Contractors. It is forwarded to recipient under an obligation of Confidence and Trust for use only m evaluation tasks specsfically authorized by the Electric Power Research Institute (EPRI). Any use, disclosure to unauthorized persons, or copying this document or parts thereof is prohibited except as agreed to in advance by EPRI and Westinghouse Electnc Corporation. Recipient of this data has a duty to inquire of EPRI and/or Westinghouse as to the uses of the information contained herein that are permitted. This document and any copies or excerpts thereof that may have been generated are to be returned to Westinghouse, directly or through EPRI, when requested to do so. l NOTICE 4: The data in this document is proprietary and confidential to Westinghuuse Electnc Corporation and/nr its Contractors, it is being revealed in confidence and trust only to Employees of EPRI and to certain contractors of EPRI for limited evaluation tasks authonzed by EPRI. Any use, disclosure to unauthorized persons, or copying of this document or parte thereof is prohibited. This Document and cny copies or excerpts thereof that may have been generated are to be returned to Westinghouse, directly or through EPRI, when requested to do so.
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| NOTICE 5: The data en this document is proprietary and confidential to Westinghouse Electnc Corporation and/or its Contractors. Access to this data is given in Confidence and Trust only at Westinghouse facilities for hmited evaluation tasks assigned by EPRI. Any use, 1 disclosure to unauthonred persons, or copying of this document or parts thereof is prohibited. Neither this document nor any excerpts i therefrom are to be removed from Westinghouse facilities. '
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| EPRI CONFIDENTIALITY / OBLIGATION CATEGORIES CATEGORY *A* - (See Delivered Data) Consists of CONTRACTOR Foreground Data that is contained in an issued reported.
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| CATEGORY "B" - (See Delivered Data) Consists of CONTRACTOR Foreground Data that is not contained in an issued report, escept for computer programs.
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| CATEGORY *C" - Consists of CONTRACTOR Background Data except for computer programs.
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| CATEGORY *D* - Consists of computer programs developed in the course of performing the Work.
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| CATEGORY *E" - Consists of computer programs developed pnor to the Effective Date or after the Effective Date but outside the scope of the Work.
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| CATEGORY *F" - Consists of administrative plans and administrative reports.
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| O
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| I 1
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| e 4
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| ! I I i s
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| 1 1 l l
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| l Package 1 of 3 l SSAR Revision 10 - December 20,1996
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| i t .
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| 1 !
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| { i i i h'
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| i Volume 1 !
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| i
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| -Master Table of Contents ,
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| List of Effective Pages O change Roadmap (Insert in front of Volume 1) ,
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| i l,
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| \
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| )
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| i, O
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| l SSAR Revision 10 - December 20,1996 '
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| !b! .
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| Master Table of Contents j 1
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| / 4
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| (_ / l MASTER TABLE OF CONTENTS i
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| Section Title Pm !
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| Volume 1 i i
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| CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT . .. 1.1-1 1.i Introduction .. ....... ....... .. ... ...... .. . . . 1.1-1 1.1.1 Plant Location . .... ...... .. .... .. .. .. .. 1.1-1 !
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| 1.1.2 Containment Type ...... . . . . ............... . 1.1-1 ,
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| 1.1.3 Reactor Type . .. . .... .... ...... ... .. . 1.1 -1 1.1.4 Power Output . . . ..... . . .. . .. ... .. .. . . . 1.1 -1 ]
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| 1.1.5 Schedule . . . . . . ... .. .. ......... .... . . . . . 1.1 -1 1.1.6 Format and Content .. .... .. ...... ........ 1.1-2 l
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| 1.1.7 Combined License lnformation . . . . ....... .... . . . .. . 1.1-3 !
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| 1.2 General Plant Description . . . . . ........ . . . ... . ..... . . 1.2-1 l 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 1.2.2 Site Description . . . . ........ . . .. . .. .. . . 1.2-15 1.2.3 Plant Arrangement Description . . . .... .... .. ... . . 1.2-16 ,
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| 1.2.4 Nuclear Island ........ ....... . . ... . .. .... 1.2-17 l 1.2.5 Annex Building . ......... . . ..... . .. .. 1.2-24
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| ,.~ 1.2.6 Diesel Generator Building . . . .. .. ... .......... . 1.2-25 l
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| (
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| ')' l.2.7 l.2.8 Radwaste BuildinE . . . . . . . . . . . . . . . . . . . .......
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| Turbine Building .......... ... ... .... .
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| .. 1.2-26 1.2-26 1.2.9 Combined License Information . . . . . . .... ... ....... .... 1.2-27 1.3 Comparisons with Similar Facility Designs . . . .. . .... .. ... 1.3-1 1 1.4 Identification of Agents and Contractors . . . . . . . ... ... .... ... 1.4-1 1.4.1 Applicant - Program Manager . . ....... .. .... .... 1.4-1 1.4.2 Other Contractors and Panicipants . . . . ..... . ... ..... . 1.4-1 1.4.3 Combined License Information . . ... ...... ..... . . 1.4-3 1.5 Requirements for Funher Technical Information . . ...... ........... . 1.5-1 1.5.1 AP600 Safety-Related Tests . . . .. ... .. . . . . 1.5-1 1.5.2 AP600 Component Design Tests . ......... . ... .. .. 1.5-7 1.5.3 Combined License Information . . . ..... . . ... .. 1.5-8 1.5.4 References . . . . . ..... .. ..... . ............. . 1.5-8 1.6 Material Referenced .... ...... . . ...... .. .. . .. 1.6-1 1.7 Drawings and Other Detailed Information ........ .... ...... .. 1.7-1 1.7.1 Electrical and Instmmentation and Control Drawings . ... . 1.7-1 1.7.2 Piping and Instmmentation Diagrams . . ... . . .. . 1.7-1 1.7.3 Combined License Information . . .. . .. . . 1.7-1 1.8 Interfaces for Standard Design . ......... .... . .. . . . 1.8-1 1.9 Compliance with Regulatory Criteria ... . .. .. . . 1.9-1 1.9.1 Regulatory Guides . . . . . . . . . . . . . ......... . . . . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) .... .. . 1.9-3 1.9.3 Three Mile Island Issues .. . . . . . ... . . 1.9-3
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| ,a Revision: 10
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| [ W85tiflgt10LIS8 i December 20,1996
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| u -- u l Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age 1.9.4 Unresolved Safety Issues and Generic Safety Issues . . . . .... . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues . . . . . . . . . 1.9-74 1.9.6 Combined License Information . . . . ........ ...... . 1.9-107 1.9.7 References .... ........... . . .. .... ... .. 1.9 108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES . . . . . .... . . 1 A-1 1 A.1 References . .... ... ..... . . .. ... . . . . . . . . . . . I A-79 APPENDIX 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES . . . . . . . 1 B- 1 IB.1 Introduction .... ... . .. .. .. . . . . . . . ... . . IB-1 IB.2 Summary . . . . . .. ...... .... . . .... ... . . .. . IB-1 IB.3 Selection of SAMDAS . .... . ... . . . . . .. . . . . . . . . I B-2 IB.4 Methodology ..... ..... .... . . .. . . .. . IB-2 IB.4.1 Risk Reduction ... . . . .. . .... . . . . . . IB-2 1B.4.2 Capital Cost Esiimates .. .. . .. .. .... . 1B-3 I B.4.3 Cost Benefit Analysis . . . . .. . . ...... ... . . . I B-3 IB.5 PRA Release Categories . . .. ........ . .. ..... ... .. . IB-3 I B.5.1 Release Category OK . . ... .. ....... .. .. .. 1B-4 1B.5.2 Release Category OKP . ... ..... ..... . . . . . . . I B-4 l IB.5.3 Release Category CC . .... . ... .. . ......... . . IB-5 1B.5.4 Release Category CI . .. ... .. .. . ... . . . . . I B-5 IB.6 Total Population Dose . ..... .. ... . . .... . ... . . I B-5 ,
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| IB.7 SAMDA Description and Benefit ............ . ... . ....... IB-6 l 1B.7.1 Upgrade the CVCS for Small LOCAs . .. .. . . . . . . . . 1 B-6 IB.7.2 Filtered Vent . . . . . . ....... . .. . . .... . . . I B-6 1 B.7.3 Locate Normal RHR Inside Containment .. ... . .. .. . 1B-7 1B.7.4 Self-Actuating Containment Isolation Valves . . . .. ..... . 1B-7 i 1B.7.5 Passive Containment Sprays ..... ...... . . ...... . . 1 B-7 IB.7.6 Active High Pressure Safety injection System . .... . . I B-7 I B.7.7 Steam Generator Shell-Side Heat Removal System . .. . . IB-8 )
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| IB.7.8 Direct Steam Generator Relief Flow to the IRWST . IB-8 l 1B.7.9 Increased Steam Generator Pressure Capability . . . ... .... 1B-8 IB.7.10 Secondary Containment Filtered Ventilation . . .. . IB-8 1 B.7.11 Diversify the IRWST Discharge Valves . . .. . . 1B-9 1 B.7.12 Ex-Vessel Core Catcher . . . . . . . I B-9 IB.7.13 High Pressure Containment Design . . . . . . . IB-9 1B.7.14 Increase Reliability of Diverse Actuation System . . . . I B-9 1 B.8 Results .. . ..... . . . ... . . . . . I B-9 I B.9 References . . . ..... ... . . . .. . ... . 1B-ll l
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| Revision: 10 i December 20,1996 i T Westinghouse
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| Master Table of Contents n
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| i
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| \s) MASTER iAL: E OF CONTENTS (Cont.)
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| Section Title Page CHAPTER 2 SITE CHARACTERISTICS . .... ..... . . ... .. . .. 2-1 2.1 Geography and Demography ....... ..... ...... ... . . 2-1 2.1.1 Combined License Information for Geography and Demography .. 2-1 2.2 Nearby Industrial, Transportation, and Military Facilities ..... . .. .. 2-1 2.2.1 Combined License Information for Identification of Site-specific Potential Hazards . .. . . . . .. .. . . ... . . 2-2 2.3 Meteorology ... ..... . . ........... .... . .. ... ... 2-2 2.3.1 Regional Climatology . ... . ... . .. .. .. . . 2-3 2.3.2 Local Meteorology . ... .. ... ........ . . .. . 2-3 2.3.3 Onsite Meteorological Measurement Programs .... .. . 2-3 2.3.4 Short-Term Diffusion Estimates . . . .. . .. . . 2-3 2.3.5 Long-Term Diffusion Estimates . . . ..... . . . . 2-4 2.3.6 Combined Licensed Information . . . ... ...... . . .. 2-4 2.4 Hydrologic Engineering . . . ....... .... ..... . ... ... 2-5 2.4.1 Combined License Information . . .... ...... ...... . 2-5 2.5 Geology, Seismology, and Geotechnical Engineering . ... .... . . . . 2-6 2.5.1 Basic Geological and Seismic Combined License Information . . . . . 2-6 2.5.2 Vibratory Ground Motion . . .. . . ... . .. .... . 2-7
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| ,/~T 2.5.3 Surface Faulting Combined License Information ...... . 2-7 C) 2.5.4 Stability of Subsurface Materials and Foundations ... . . . . . 2-8 2.5.5 Combined License Information for Stability of Slopes ... . . 2-12 2.5.6 Combined License Information for Embankments and Dams . . . . . . 2-13 2.5.7 References .. ... .... ...... . . . . .... .. 2-13 APPENDIX 2A DESIGN SOIL PROFILES . . . . . ........ ...... ...... . . 2A-1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. . . 2A-1 2A.2 Generic Soil Profiles . . . . . . . . . . . .... .......... .. . 2A-2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . . 2A-4 2A.4 Free-Fie!.i Site Response Analysis . . . . . ... ..... . 2A-5 2A.5 2D Soil-Structure Interaction Analysis .. . . ...... .. . 2A-7 2A.6 AP600 Design Soil Profiles . .... . .. . . 2A-12 2A.7 References . . . . .. ...... . . . . . 2A-14 APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL PROFILFS ... . .. . .. . . .. .. .. . 2B-1 2B.1 2D SSI /. alysis Parameters and Procedures . .... .. . . . 2B-2 2B. I .1 i ructural Models . . . . . .. ... ... 2B-2 2B.I.2 SASSI Foundation Models . . . . . . . . 2B-2 2B. I .3 Soil Properties for SSI Analysis . .. . .. 2B-2 2B.1.4 Input Motion . .... . . . . . 2B-3 2B.I .5 Two-Dimensional Enveloped SSI Results . . . 2B-3 2B.2 Design Soil Profiles . . .. . . . ... . . . . 2B-3 i i V
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| I Revision: 10 1
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| [ We"iflghotise ii December 20,1996 -
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| 1
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| 1 l
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| -- Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h 1
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| 1 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) ... . .... 2B-4 i 2B.2.2 Finn Rock Profiles (V,=3500 fps) . .... . .... ..... . 2 B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . . . 2B-5 )
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| 2B.2.4 Variation of Soil Properties and 60 Percent Requirement of l Free-Field Spectra at Foundation Level . . . . .... .. 2B-5 2B.2.5 AP600 Design Soil Profiles . . . .. ... . . . . . . . . 2 B-6 28.3 Soil Profile Parametric Studies: ...... . .. . ... . . .. 2B-6 2B.3.1 Depth-to-Base Rock . .. .. 2B-7 2B.3.2 l
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| Soil Curves for Clay Material . ......... . . .. ... . 2B-7 i 29.3.3 Poisson's Ratio for Soil above Water Table . . . . . . ... . 2B-8 21).3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site .. . ... . 2B-8 2'.l.3.5 Idriss 1990 Soil Curves . . . . . . . .... . 2B-9 2B.3.5 Soil Densitys . . ... .. . . . . . . . . . 2B-9 2B.4 References . . . ............. . .. . . . 2B-9A l
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| Volume 2 l1 APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES ... .. . . . . . . . 2C-1 I 2C.1 2D SASSI Analysis for Seismic Lateral Earth Pressure . . . . . . . . . 2C- 1 2C.l .1 Analysis Method .... .... . . . . . ... . . . . . . 2C-1 2C.I .2 Structural Models . . .. .... . . ....... ... . . . 2C-1 2C.I.3 SASSI Foundation Models .. .... . . .. . . . . . 2C- 1 2C.I .4 Representation of Adjacent Structures . . . . . .. .... . 2C-2 2C.I .5 Input Motion . . . . . . . .. . .... ... . . .... . 2C-2 2C.I.6 Soil Properties . . .. .. .. . . . . .. ..... 2C-2 2C.1.7 2D SASSI Analyses Results . ,. ..... ... . . . . . 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island . .. . . . . 2C-2 2C.3 Local Distribution of Lateral Earth Pressure .. .... . . . . . 2C-3 2C.4 References . ..... .. . . .. . .... . 2C-4 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS .. ....... . . . .. . . 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria . 3.1-1 3.1.1 Overall Requirements .. .... . . . 3.1-1 3.1.2 Protection by Multiple Fission Product Barriers . .. .. 3.1-4 3.1.3 Protection and Reactivity Control Systems .. . . 3.1-12 3.1.4 Fluid Systems ...... . . . . . . . 3.1-18 3.1.5 Reactor Containment ... . . . . . 3.1-30 3.1.6 Fuel and Reactivity Control . . ... .. 3.1-34 3.1.7 Combined License Information .. . 3.1-37 3.1.8 References . .... ... . .. . ... . . . . 3.1-37 Revision: 10 December 20,1996 iv Westingh0USS
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| Master Tcble of Contents p
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| MASTER TABLE OF CONTENTS (Cont.) j Section Title Eage I 3.2 Classification of Structures, Components, and Systems . .. . . ...... 3.2-1 3.2.1 Seismic Classification . . .. . ...... ... ...... . 3.2-1 3.2.2 AP600 Classification System ............ . ..... . . 3.2-3 3.2.3 Inspection Requirements . ... .. . ........ . 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System . . . .. . . ... . .. . . . 3.2-13 3.2.5 Combined License Information .. .. ... . . .. . 3.2-16 3.2.6 References . . . . ... .. ... .. . . . 3.2-17 3.3 Wind and Tomado Loadings . ... .. ... . ..... . .. 3.3-1 3.3.1 Wind Loadings . . . . . . . ... . . ... 3.3-1 l 3.3.2 Tornado Loadings . . . . . . ... . . .. .... . . ..... . 3.3-2 3.3.3 Combined License Information .. .. ...... .. .. 3.3-4 3.3.4 References .... . ....... . . ... ... . 3.3-4 3.4 Water Level (Flood) Design . .... .. . . .. ... . . 3.4-1 3.4.1 Flood Protection .. . . ... .... . .. . 3.4 1 3.4.2 Analytical and Test Procedures . . . . ..... . 3.4-24 3.4.3 Combined License Information . .. .. . ... . . 3.4-24 3.4.4 References . . . .. .. . .. .... . . ....... 3.4-24 3.5 Missile Protection . ... ...... .... . ...... ..... ... . 3.5-1 1 V)
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| : 3.5.1 3.5.2 Missile Selection and Description Protection from Externally Generated Missiles
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| . . . . . 3.5-4 3.5-13 3.5.3 Barrier Design Procedures . . . . ... ....... . . 3.5-13 3.5.4 Combined License Information ... ... ..... ..... 3.5-16 3.5.5 References . . . . . ..... .... . .. ...... .... 3.5-16 3.6 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping ... .. .. . . . . ..... . . .. 3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems inside and Outside Containment ..... ...... .... .......... .. 3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping . .. ... 3.6-12 3.6.3 Leak-before-Break Evaluation Procedures . . .. .. . 3.6-31 3.6.4 Combined License Information . . .. . .. 3.6-38 3.6.5 References ... . .. . .. . 3.6-38 3.7 Seismic Design ... . ... .. . .... . 3.7-1 3.7.1 Seismic Input ... . . . . . 3.7-1 3.7.2 Seismic System Analysis . .. . ..... 3.7-6 3.7.3 Seismic Subsystem Analysis . . 3.7-20 3.7.4 Seismic Instmmentation . .. . . .. . 3.7-46 3.7.5 Combined License Information . . . . 3.7-48 3.7.6 References . .. . . . . 3.7-49 3.8 Design of Category I Structures . .... . 3.8-1 3.8.1 Concrete Containment . . . . 3.8-1 3.8.2 Steel Containment .. .... .. . 3.8-1 p . .
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| Revision: 10
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| [ W85tingt10llSe y December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.8.3 Concrete and Steel Intemal Structures of Steel Containment . . 3.8-16 3.8.4 Other Category I Structures . . . .. ..... ...... . . 3.8-39 3.8.5 Foundations . . ... .... .. . . . . . . . . . 3.8-53 3.8.6 Combined License Information .. ...... . . . . 3.8-60 3.8.7 References . . . . ........... ...... . .. . .. . 3.8-60 Volume 3 3.9 Mechanical Systems and Components ..... . . .. . .. .... 3.9-1 3.9.1 Special Topics for Mechanical Components ......... .. 3.9-1 3.9.2 Dynamic Testing and Analysis . . .... ....... .... 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Components, Component Supports, and Core Support Structures . . ... . . . . . . 3.9-45 3.9.4 Control Rod Drive System (CRDS) .... . . . .... . 3.9-71 3.9.5 Reactor Pressure Vessel Internals . . ... . . . . 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . . .. . . . . . . 3.9-89 3.9.7 Integrated Head Package . ... ...... . ... . 3.9-97 3.9.8 Combined License Information .. ...... .. . . . . . 3.9-102 ,
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| 3.9.9 References . . ......... .. ....... .. . ..... 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and i Electrical Equipment . . ........... ......... . . . . . . . . 3.10- 1 3.10.1 Seismic and Dynamic Qualification Criteria ... . ..... ... 3.10-2 3.10.2 Methods and Procedmes for Qualifying Electrical Equipment. l Instrumentation. and Mechanical Components ....... . . 3.10-3 3.10.3 Method and Procedures for Quar /ying Supports of Electrical Equipment, Instrumentation, and Mechanical Components . . . . . 3.10-7 {
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| 3.10.4 Documentation .... ..... . . .... ..... . . 3.10-7 l 3.10.5 Standard Review Plan Evaluation . . .... .. ... . .. 3.10-7 3.10.6 Combined License Information Item on Experienced-Based Qualification . . .. .. ....... ..... . 3.10-8 ;
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| 3.10.7 References ... ..... .. . . . .. ... . 3.10-8 i 3.11 Environmental Qualification of Mechanical and Electrical Equip'ment . . . 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . . . . . 3.11-1 3.11.2 Qualification Tests and Analysis . . .. . . 3.11-3 3.11.3 Loss of Ventilation . . ...... ... .. . 3.11-4 3.11.4 Estimated Radiation and Chemical Environment 3.11-5 3.11.5 Combined License Information Item for Equipment Qualification File . .... . . .. ..... . . 3.11-5 3.11.6 References .. . . .. . . .... .. . 3.11-6 1
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| Revision: 10 December 20,1996 vi 3 Westirighouse
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| U/ MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 1
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| APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS . . . . . . ..... . .... . 3A-1 3A.1 Codes and Standards . . . . ....... .. .... . ........ . . 3A-1 l 3A.2 Loads and Load Combinations . . ........ ... ... ....... .. . 3A-1 !
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| 3 A.2.1 Loads .... ....... . .... ... .. . ... .. ... . 3A-1 3A.2.2 Load Combinations . . .. .. .. .... . . . . . . .. . 3A-3 l 3A.3 Analysis and Design ... .. . . . . . 3A-3 3 A.3.1 Response Due to Seismic Loads . . . . . . .
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| {
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| . . . ..... ... 3A-3 j 3A.3.2 Deflection Criteria . . .. . ... . . .. . . .. . .. 3A-3 l 3A.3.3 Reh Uve Movement . .
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| l
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| . .. . .. . . .. ....... 3A-3 i 3A.3.4 Allowable Stresses . . . . ...... . . ....... 3A-4 3A.3.5 Connections . . . . . . . . . . . . . ..... .... .. . 3A-4 l
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| APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . . . . . 3B-1 3B.1 Leak-Before-Break Criteria for AP600 Piping . . . ... . 3B-2 3B.2 Potential Failure Mechanisms for AP600 Piping .. . ....... . . . . . . 3B-2 3B.2.1 Erosion-Corrosion Induced Wall Thinning ... ....... . . . . 3B-2 3B.2.2 Stress Corrosion Cracking ...... .... .. ...... .. 3B-3 3B.2.3 Water Hammer ...... . . .... .. .. .... ..... . 3B-5 3B.2.4 Fatigue .. . ...... ......... .. . ... .. . . . 3B-9 3B.2.5 Thermal Aging .. ... ..
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| (V
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| .... . . . .... .... . . . 3B-9 :
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| 3B.2.6 Thermal Stratification . .. ... ........ .... .. ... . 3B-10 !
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| 3B.2.7 Other Mechanisms . . . . . . . . . .. .... ..... . . . . 3B-13 3B.3 Leak-Before-Break Bounding Analysis ...... . . . . . . 3B-13 I 3B.3.1 Procedure for Stainless Steel Piping . . .... ...... ...... 3B-13 3B.3.2 Procedure for Non-Stainless Steel Piping . . . . . . . . . . . . . .. .. . 3B-16 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . . 3B-17 3B.3.4 Bounding Analysis Results ......... . .. .. .. . . 3B-21 j 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe . ..... ..... .... .. . . . . . . . 3B-21 3B.5 Differences in Inspection Criteria for Class 1, 2, and 3 Systems . . . . 3B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2. and Class 3 Piping . . .... ... .. .. .. . .. . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Unes ... . 3B-21 A 3B.8 Augmented In-Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators ..... .. .... . 3B-21 A 3B.9 References ...... . . .. .. . ... . .. 3B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS . .. ... . 3C-1 3C.) Reactor Coolant Loop Model Description . . . . . . .... 3C-1 3C.1.1 Steam Generator Model . .. . . . . ... . . . 3C-1 3C.I .2 Reactor Coolant Pump Model . . . . . .. . . 3C-2 3C. I .3 Reactor Pressure Vessel Model . . .. . 3C-2 I
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| v Resision: 10 3 Westiligh0USB vi December 20,1996
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| Section Title Page 3C.1.4 Containment Interior Building Structure Model . . ............. 3C-3 3C.1.5 Reactor Coolant Loop Piping Model . .. ..... .... , . . . . . 3C-3 3C.2 Design Requirements . . ...... . ..... .. .. . .. ... . 3C-3 3C.3 Static Analyses . . . . . ... .. .. . . ..... ... . . 3C-4 3C 3.1 Deadweight Analysis . . . . . ... . . ........ . 3C-4 3C.3.2 Intemal Pressure Analysis ... ..... . . ..... .... . . 3C-4 3C.3.3 Thermal Expansion Analysis .... .. . ......... .. . 3C-4 3C.4 Seismic Analyses .. . . . ........ . ... .. .. , ..... . 3C-4 3C.5 Reactor Coolant Loop Piping Stresses . ... . . ...... . .. . 3C-5 3C.6 Description of Computer Programs . . . . ..... . .. . ... . . . . 3C-5 APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL RQUIPMENT . .. . ...... 3D-1 3D.1 Purpose . . . . . . ..... ...... . .... ........ . . . 3D-2 3D.2 Scope. .... . .. . .. ....... .. ................ . . 3D-2 3D.3 Introduction ... . . ... ...... . .. ...... . . . . . . . . . . 3 D-3 3D.4 Qualification Criteria .. ....... . . .... ... . . . . . 3D-3 3D.4.1 Qualification Guides . .... .... . . . ... ........ . 3D-3 3D.4.2 Definitions . . .. . . ..... . ..... ... ... . . . . . 3 D-7 3D.4.3 Mild versus Harsh Environments ......... ..... ... . 3D-7 3D.4.4 Test Sequence ... . .. . . . ...... .. .. . . ... 3D-8 3D.4.5 Aging . . ......... . .. . ...... ... . . . . . . . . 3 D-9 3D.4.6 Operability Time ...... .. ..... . .. . ..... . 3D-12 3D.4.7 Performance Criterion . . . . . . .... .. . . .. . . . . . . . . . . . 3 D- 12 3D.4.8 Margin ... ... .... . .. . . .. .. 3D-12 3D.4.9 Treatment of Failures . . . . . . . .... .. ... ... . 3D-15 3D.4.10 Traceability . . .... .. . . . . ....... . . . 3D-16 3D.5 Design Specifications . . . . . . . . . . . . . . . ... .. 3D-17 3D.5.1 Normal Operating Conditions . . .. . .. .. .. .. 3D-18 3D.5.2 Abnormal Operating Conditions .. .. . .. . 3D-19 3D.5.3 Seismic Events . .... .. . . . . .. . 3D-20 30.5.4 Containment Test Environment .. ..... . . 3D-20 3D.5.5 Design Basis Event Conditions . . . .. . .. . . . 3D-20 3D.6 Qualification Methods . ..... .. . .. ... 3D-24 3D.6.1 Type Test .. ........ . . .. . .. 3D-25 3 D.6.2 Analysis ..... .. . . . .. .. . 3D-25 3D.6.3 Operating Experience . . .. .. . . 3D-30 3D.6.4 On-Going Qualification . . .. . . 3D-30 3D.6.5 Combinations of Methods . . . . . ... 3D-30 0
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| Revision: 10
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| ,o (k '') MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pye 3D.7 Documentation . ............... . .... ......... . . . 3D-31 3D.7.1 Equipment Qualification Data Package . ..... . . . . . . . 3D-32 3D.7.2 Specifications . . . . . . . . . .. ... . .. ..... ...... . . . . 3D-32 3D.7.3 Qualification Program . .... . . . . . . . .. . . 3D-34 ,
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| 3D.7.4 Qualification by Test . . .. ..... .. .. . . . . 3D-34 j 3D.7.5 Qualification by Analysis . ...... .......... ... . . 3D-37 3D.7.6 Qualification by Experience . . . . ... . ..... .. . 3D-37 3D.7.7 Qualification Program Conclusions . . . . . . . . ... .... 3D-37 ,
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| 3D.7.8 Combined License Information . . . .. ....... .. .. . 3D-38 l 3D.8 References ...... .... .......... .... . .. ...... ... . 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package . ... . . . . 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program . ... . . .... 3D-87 B.1 Introduction . . ..... .... ...... . ... ... ... . . 3D-87 B.2 Objectives ..... .......... .. . . . . . .. . . . 3D-87 B.3 Basic Approach . . . . . ......... . ... . . . . . . . . . . 3 D-87 B.4 Subprogram A . ....... . .... .. . ..... ... . . . . . . 3D-88 j"N., B.4.1 Scope ... ......... .... . ... .. . .... .. . . . 3D-88
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| () B.4.2 Aging Mechanisms . . . . .... . ....... . . ..... . . . . . 3D-88 l B.4.3 Time . . . . .. ..... ........... . . . . . . . . . . 3D-88 i B.4.4 Operational Stresses . . . . . . . . .. . . . . . . . . . . . . . 3 D-8 9 )
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| B.4.5 Extemal Stresses .......... ... . .. . . . . . . . . 3D-89 l B.4.6 Synergism . . . ... ... .... . ....... ... . .. . 3D-91 j B.4.7 Design Basis Event Testing . . . . . . . ...... . . . . . . . . 3D-91 l B.4.8 Aging Sequence . . . . ....... ......... . .. . .. . 3D-91 l B.4.9 Performance Criterion .. . . ... .. .. .. .. . 3D-91 l B.4.10 Failure Treatment . . ...... .. ....... . . . . . . 3D-91 l B.5 Subprogram B .. .. ....... . . . . .. ...... .. . 3D-92 B.5.1 Scope . .. . . . .... ... .... .. ...... .. 3D-93 B.5.2 Performance Criteria . . . .. .. .. . . .. .. . . 3D-93 B.5.3 Failure Treatment . . . . .. . .. ......... . ..... . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials . . .. .. .. . 3D-96 C.1 Introduction . . . ..... . . .. . . . .. . . 3D-96 C.2 Scope. . . . . . ........ . .... . .... . . . . 3D-97 C.3 Discussion . . . . . . . .. . . . . . 3D-97 l
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| C.4 Conclusions . . .... . .. . . . . . . .. ... . 3D-98 C.5 References . . ... .. .. . . . . . 3D-98 f)'i i
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| l Section Title Page I l
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| 1 Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . .... .. . . 3D-103 I D.1 Introduction . . . . . ....... ... .... .. .. ... ...... 3D-103 D.2 Arrhenius Model . ... . .... ... . . . . .... ... 3D-103 ,
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| 1 D.3 Activation Energy . .... . . .. . . . .. . . . . . 3D-105 l D.4 Thermal Aging (Normal / Abnormal Operating Conditions) .. .. . . 3D-106 '
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| D.4.1 Normal Operation Temperature .. . .. . . ... . 3D-106 D.4.2 Accelerated Aging Temperature . .. .. . . . . 3D-107 l D.4.3 Examples of Arrhenius Calculations . ... . ... . . 3D-107 i D.5 Post-Accident Thermal Aging . ..... .. . ..... ..... . .. 3D-108 l D.5.1 Post-Accident Operating Temperatures .. . .. . .... . 3D-108 l D.5.2 Accelerated Thermal Aging Parameters for Post-Accident Conditions . .. .. . . . ... . . . . 3D-109 D.6 References . . . . . . ... ..... .. . . ... . . . . 3D-109 Appendix 3D-Attachment E - Seismic Qualification Techniques .. . ....... . 3D-115 j E.1 Purpose .. . . . ... . . . . ..... ..... 3D-Il5 l
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| E.2 Definitions . . . . . . . . . . .. .. .... .... . . .. . 3D-Il5 i E.2.1 1/2 Safe Shutdown Earthquake . . . .. ... ...... . . 3D-115 )
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| E.2.2 Seismic Category I Equipment . . . ... . ... . . . 3D-Il5 j E.2.3 Active Equipment . . ........... . . . .,. . ...... 3D-115 )
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| E.2.4 Passive Equipment . . ............. . ... .. ... 3D-115 )
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| E.3 Qualification Methods . ...... ... . . . .......... . . 3D-116 i E.3.1 Use of Qualification by Testing ... ... .. .. ....... 3D-116 !
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| E.3.2 Use of Qualification by Analysis .. . ..... .... .. 3D-116 E.4 Requirements . . . . .. .. ... . . . .... .... 3D-Il7 E.4.1 Damping ..... . .... . . . ........ . 3D-Il7 E.4.2 Interface Requirements .. .. .. .. .. 3D-117 E.4.3 Mounting Simulation . . ... . . . .. . . .. . . 3D-118 E.4.4 1/2 Safe Shutdown Earthquake . .. .. . .. ... 3D-118 E.4.5 Safe Shutdown Earthquake . . . .. . .. . 3D-118 j E.4.6 Other Dynamic Loads . . . . .... . ... . 3D-118 :
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| E.5 Qualification by Test . . . .. .. . . .. . . . . 3D-118 E.5.1 Qualification of Hard-Mounted Equipment . . . . 3D-Il9 E.5.2 Qualification of Line-Mounted Equipment . . . . . . 3D-120 E.5.3 Operational Conditions . . . 3D-122 E.5.4 Resonant Search Testing .. . ... . . 3D-123 E.6 Qualification by Analysis . .. . . .. 3D-123 E.6.1 Modeling . .... . . .. . . .. . 3D-124 E.6.2 Qualification by Static Analysis .. . 3D-124 E.6.3 Qualification by Dynamic Analysis . . . 3D-124 O
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| Revision: 10 December 20,1996 x W85tiflgh0USB
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| Section Title Page E.7 Performance Criteria . . . . . . . . . . . . . .. . .............. . . 3D-126 E.7.1 Equipment Qualification by Test . .... ... ....... . .. 3D-126 E.7.2 Equipment Qualification by Analysis .. . ..... ......... 3D-126 APPENDIX 3E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND . . . . . . . . .. 3E-1 APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS . . . .. . . . . 3F-1 3F.1 Codes and Standards . . . . . . . . .... . . . .... .. . . .... 3F-1 3F.2 Loads and Load Combinations ..... . . ... . .. . .. ..... 3F-1 3F.2.1 Loads . . . . . .... ..... .. . ..... ... . . . . 3F-1 3F.2.2 Load Combinations . . . . . . . .. ... .. .. . . .. .. . 3F-2 3F.3 Analysis and Design . . . . . . . . . . . . . . ... ..... .... . 3F-2 3F.3.1 Damping . . . . . . . . . . ..... .. . ... .... . . . . . . . . . 3 F-2 3F.3.2 Seismic Analysis ... .. ... .... ... . .. ..... 3F-3 3F.3.3 Allowable Stresses . . . . . . . . .. .. ... ....... ... . 3F-3 3F.3.4 Connections . . ...... . .. . . . .. ..... .... . 3F-3 CHAPTER 4 REACTOR., . ..... . ...... . . . . .. ..... .... . 4.1-1 O 4.1 Summary Description ....... . . . .. . .. .... . . 4.1-1 4.1.1 Combined License Information . . ...... ........ ... 4.1-4 4.1.2 References . ....... ...... . .. . . ...... .... 4.1-4 4.2 Fuel System Design . .. .... . . ........... .. . . . 4.2-1 4.2.1 Design Basis . . . . . . . . . . . . . . ......... . . 4.2-2 4.2.2 Description and Design Drawings . . . . .. ...... .... . .. 4.2-9 4.2.3 Design Evaluation . . . . . ... .. . .. . .. ... .... 4.2-20 4.2.4 Testing and Inspection Plan . . ... .... . . ... . . . 4.2-32 4.2.5 Combined License Information .. .. . . . . . . 4.2-37 4.2.6 References . . . . . . . . . . . . . . .. .. .... .... ..... . 4.2-37 4.3 Nuclear Design . . . . . . . . . . . . . ... . . . . ... ... ... . 4.3-1 4.3.2 Description ... .. . . . .. . . ..... ... .. . .. 4.3-7 4.3.3 Analytical Methods . . . . . . . .... ... .... . . .. . 4.3-39 4.3.4 Combined License Information . . . .. .. .. . . . 4.3-42 4.3.5 References . ... . . . . . . 4.3-42 4.4 Thermal and Hydraulic Design . . ... ... .. .. . ... .. . 4.4-1 4.4.1 Design Basis ... . ...... .. .. .... . . ... .. 4.4-1 4.4.2 Description of Thermal and Hydraulic Design of the Reactor Core . . 4.4-4 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System . . . . . . . .. ... .. . . 4.4-201 4.4.4 Evaluation . ... ...... ... . ... . . 4.4-21 4.4.5 Testing and Verifiestion . .. . .. . . 4.4 30 l 4.4.6 Instrumentation Requirements ... . . . 4.4-31 l
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| /~N 4.4.7 Combined License Information . .. . . . 4.4-35 l
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| Section Title h 4.4.8 References . . .. .... .... .... . .. .. . ... . 4.4-35 4.5 Reactor Materials .. ..... . ... ......... . . .. . . . . 4.5-1 4.5.1 Control Rod and Drive System Structural Materials . . . . .... 4.5-1 4.5.2 Reactor Internal and Core Support Materials ...... ... .. . 4.5-3 4.5.3 Combined License Information .. . . ... ......... . 4.5-4 4.5.4 References . . . ....... .... . . .. ........ 4.5-4 4.6 Functional Design of Reactivity Control Systems . . . .. ........ . 4.6-1 4.6.1 Information for Control Rod Drive System . . . . . ...... 4.6-1 4.6.2 Evaluations of the Control Rod Drive System . . . .... ...... 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System ..... . 4.6-2 4.6.4 Infonnation for Combined Performance of Reactivity Systems ..... 4.6-2 4.6.5 Evaluation of Combined Performance . . .. . . .. . .. 4.6-3 4.6.6 Combined License Information . . . . . . . .... ... . 4.6-4 Volume 4 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS . . ..... 5.1-1 5.1 Summary Description ...... . . .... . . .. ... . .... . 5.1-1 5.1.1 Design Bases ... ... .. .......... ... . . . . . . . .. 5.1-1 5.1.2 Design D.'scription . .... .... . ... .. .. .. . . . . . .. .. 5.1 2 5.1.3 System Cocnponents ....... ... .. .... . . . .... 5.1-4 5.1.4 System Pen'ormance Characteristics . .. . ... ...... 5.1-7 5.1.5 Combined License Information . . . . . .. . ..... . .. . 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary .. ...... . ... .. .. 5.2-1 5.2.1 Compliance with Codes and Code Cases . . . ... . .. 5.2-1 5.2.2 Overpressure Protection . .. . .. . .. . .. .. 5.2-2 5.2.3 Reactor Coolant Pressure Boundary Materials . . .. . . . . ... 5.2-7 5.2.4 Inservice Inspection and Testing of Class 1 Components . . . 5.2-17 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary 5.2-20 5.2.6 Combined License Information Items . . .. .... . 5.2-29 5.2.7 References . .. . . .. . .. .. . . .. . 5.2-29 5.3 Reactor Vessel .... . . .. .. . . . . .. . . 5.3-1 5.3.1 Reactor Vessel Design . .. . . . . . 5.3-1 5.3.2 Reactor Vessel Materials . . .. . . . 5.3-4 5.3.3 Pressure-Temperature Limits ..... .. 5.3-13 5.3.4 Reactor Vessel Integrity . ,. .. . . . 5.3-14 5.3.5 Combined License Information . . 5.3-19 5.3.6 References . . . . . ... . . . . . . 5.3-20
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| ; 5.4 Component and Subsystem Design .. . . . . . 5.4-1 j 5.4.1 Reactor Coolant Pump Assembly . .. . 5.4-1 l 9 Revision: 10 December 20,1996 xi Westingh00SC
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| ,n f T U MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pm 5.4.2 Steam Generators . . . . . . . . . . . . . . . . . . . ... ... .. . 5.4-10 5.4.3 Reactor Coolant System Piping . . .... . . .. .. .... 5.4-23 5.4.4 Main Steam Line Flow Restriction . . . . . . ..... ........ 5.4-28 5.4.5 Pressurizer . . . . . . . . .. .... ...... ......... . . . 5.4-29 5.4.6 Automatic Depressurization System Valves . . .... . . 5.4-36 5.4.7 Normal Residual Heat Removal System .. .. . . . . . . . . 5.4-3 8 5.4.8 Valves . . . . . . ............ . . . ..... . ... . . 5.4-51 5.4.9 Reactor Coolant System Pressure Relief Devices . ... . . . . . 5.4-57 5.4.10 Component Suppons .. .... ... ... ... . . .. . 5.4-60 5.4.11 Pressurizer Relief Discharge . .. . .. . . ... . .. .. 5.4-63 5.4.12 Reactor Coolant System High Point Vents . .... .. .. . 5.4-65 5.4.13 Core Makeup Tank . . . .. .... . .. . ... . 5.4-68 5.4.14 Passive Residual Heat Removal Heat Exchanger .. .. .. 5.4-71 5.4.15 Combined License Information . .. . .. . .... .... . 5.4-74 5.4.16 References ........ .... . . . . ... ... . ... . 5.4-74 CHAFTER 6 ENGINEERED SAFETY FEATURES . . . . . . . . . . ... ........ . . 6.0-1 6.1 Engineered Safety Features Materials . ... .. .... ..... . 6.1-1 A 6.1.1 Metallic Materials . ..... . .. . ... . .... . . 6.1 -1
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| ) 6.1.2 Organic Materials . . . . ... ... .. ..... .. . ..... 6.1-5 6.1.3 Combined License Information Items .. ... . . ....... 6.1-11 6.1.4 References . . . . . ....... .. ..... ... ..... . .. 6.1-12 6.2 Containment Systems . . . . ... . .. .. . ... .. . . 6.2-1 6.2.1 Containment Functional Design .... .............. .... . 6.2-1 6.2.2 Passive Containment Cooling System . .. . . . . . . . . . . . . . . 6.2-20 6.2.3 Containment Isolation System . . . . . . . ... .. . .. . 6.2-28 6.2.4 Containment Hydrogen Control System ............ . . . . 6.2-378 6.2.5 Containment Leak Rate Test System . ......... .... . . . . . 6.2-48 6.2.6 References . . ... . . .... . . ... .. ..... ... .. 6.2-55 6.3 Passive Core Cooling System .. .......... . .. ..... .. . . 6.3-1 6.3.1 Design Basis . . . . ....... . . ... . . . 6.3-2 6.3.2 System Design . . . . ... . .. . ... ... . 6.3-6 6.3.3 Performance Evaluation . . . . . . . ..... .. 6.3-28 6.3.4 Post-72 Hour Actions . . . . . ... .. . 6.3-41 6.3.5 Limits on System Parameters .. . . . . 6.3-41 6.3.6 Inspection and Testing Requirements . . . .... .. 6.3-42 6.3.7 Instrumentation Requirements ... . .. .. . . 6.3-43 6.3.8 Combined License Information . . ... .... . . 6.3-48 6.3.9 References . ... . ... . . . . . . 6.3-48 6.4 Habitability Systems . . . . .... ..... . ... .. . . 6.4-1 6.4.1 Safety Design Basis . .. . .... . .... . .. 6.4-1 6.4.2 System Description . .... .. . . . . 6.4-2 6.4.3 System Operation . . . .. . . . . . . 6.4-6 Revision: 10 W85dngt10US8 xi i December 20,1996
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| Section Title Pace 6.4.4 System Safety Evaluation . . .. . . .. . . . . . 6.4-8 6.4.5 Inservice Inspection / Inservice Testing . . . .. . ... . . 6.4-10 6.4.6 Instrumentation Requirements .. .. ... . .. . .. .. 6.4-10 l 6.4.7 Combined License Information , . . .... .... 6.4-11 6.4.8 References ......... ... ... ... . . ..... 6.4-11 6.5 Fission Product Removal and Control Systems ... . .. .... ... 6.5-1 6.5.1 Engineered Safety Feature (ESF) Filter Systems . . . . 6.5-1 1 6.5.2 Containment Spray System .. ... . . . . . . . 6.5-1 !
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| 6.5.3 Fission Product Control Systems . . . . .. ... 6.5-1 l 6.5.4 Combined License Information . . .... ..... ... .. ... . 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components . . . . . . . . ..... . . 6.6-1 6.6.1 Components Subject to Examination . . . .. . .... 6.6-1 l 6.6.2 Accessibility ........ . .. .... . .... . 6.6-1 1 6.6.3 Examination Techniques and Procedures . .. ... ... . 6.6-2 6.6.4 Inspection Intervals . . . . . . .. .. .. .. ... 6.6-3 I 6.6.5 Examination Categories and Requirements . . . .. . .. . . 6.6-3 i 6.6.6 Evaluation of Examination Results . .. .... .. . ..... . 6.6-3 6.6.7 System Pressure Tests . ... . ..... . . . . 6.6-3 j 6.6.8 Augmented Inservice Inspection to Protect against Postulated j Piping Failures . . .. . .. . . . . .... . . 6.6-3 '
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| 6.6.9 Combined License Inform?? ion Items . . .. . . . 6.6-4 l
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| CHAPTER 7 INSTRUMENTATION AND CONTROLS . . . . . ... ... 7.1-1 7.1 Introduction . . . . . ....... ... . . ..... . . . . . 7.1-1 7.1.1 The AP600 Instrumentation and Control Architecture . ... . 7.1-2 7.1.2 General Protection Subsystem Configuration . . . . .. . 7.1-6 7.1.3 Plant Control System ..... . .. . .. ... . . . 7.1-27 7.1.4 Identification of Safety Criteria . . .. . . .... . 7.1-32 7.1.5 AP600 Protective Functions . . . . .. .... 7.1-48 7.1.6 Combined License Info, nation . . . . . .. .. . 7.1-48 7.1.7 References . .... . .. ... .. . 7.1-49 7.2 Reactor Trip . . . .. . . ... .. 7.2-1 7.2.1 Description . .. .. . . . . . . . . 7.2-14 7.2.2 Analyses .. . . .. . .. . . 7.2-14 7.2.3 Combined License Information . . . . . . . 7.2-17 7.2.4 References . .. .. . . . . . 7.2-17 7.3 Engineered Safety Features . . .. . . .. 7.3-1 7.3.1 Description ...... . . . . .. ... . . . . 7.3-1 i 7.3.2 Analysis for Engineered Safety Features Actuation . . . . . 7.3-19 7.3.3 Combined License Information . .. . . 7.3-22 7.4 Systems Required for Safe Shutdown . . . . . . . 7.4-1 O
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| Revision: 10 December 20,1996 xiv 3 Westiligt100Se l
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| :- L Master Table of Contents
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| (d' MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 7.4.1 Safe Shutdown . . . . ... ... .... ... . ........ .... 7.4-3 7.4.2 Safe Shutdown Systems . . . . . . . . . . .. . . ......... . . 7.4-10 7.4.3 Safe Shutdown from Outside the Main Control Room . . .... .. 7.4-11 7.4.4 Combined License Information . . . . . . ..... . 7.4-14 7.4.5 References . . .. ... .. ......... ...... . . . . . 7.4-14 7.5 Safety-Related Display Information ..... . ...... . . .... .. .. 7.5-1 7.5.1 Introduction . . . . . . . . . . . ..... . . . ......... . . 7.5-1 7.5.2 Variable Classifications and Requirements ....... .... ... .. 7.5-1 7.5.3 Description of Variables . . . . . . . . . . . . . .. ... .... .. . 7.5-9 7.5.4 Processing and Display Equipment . . . ... .. .. ....... . 7.5-11 7.5.5 Combined License Information . . . . . . ..... .. . 7.5-13 7.6 Interlock Systems Important to Safety . . ,.. ... ... ..... .. ... . 7.6-1 1 7.6.1 Prevention of Overpressurization of Low-Pressure Systems . . . . . 7.6-1 7.6.2 Availability of Engineered Safety Features . .. .. .. .. 7.6 2 7.6.3 Combined License Information . . .. . .. . ........ .. . 7.6-5 7.7 Control and Instrumentation Systems . ......... . ... .... .. . 7.7-1 .
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| 7.7.1 Description .. . . ....... . . ... . 7.7-2 7.7.2 Analysis . ..... ...... . .. ..... ...... .. . . 7.7 20 i 7.7.3
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| /7) Combined License Information . .. ..... . '
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| ...... 7.7-21 C/
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| Volume 5 '
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| CHAPTER 8 ELECTRIC POWER . . . . . . ..... . .... ... ... .. . ... .. 8.1-1 8.1 Introduction . . .... . . .. .... .... .. ........ . 8.).-l 8.1.1 Utility Grid Description . . . ... .. ... .. ... .. .8.11 8.1.2 Onsite Power System Description . ....... . . .... ... 8.1-1 8.1.3 Safety-Related Loads . . ...... .... . ... . . . 8.1-2 8.1.4 Design Basis ............... . . ...... ....... 8.1-2 !
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| 8.1.5 Combined License Information . .... .. .. ... ... . . 8.1-5 l 8.2 Offsite Power System . . . ..... . ..... ..... ... .. . 8.2-1 !
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| 8.2.1 System Description . . ... . .. .. . ......... . . 8.2-1 ;
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| 8.2.2 Conformance to Criteria . . . . . .... . ..... . . 8.2-2 I 8.2.3 Standards and Guides ........ . . . . ... . . . 8.2-2 !
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| 8.2.4 Combined License Information for Offsite Electrical Power . . 8.2-2 l 8.2.5 References .. .... . .. .. . ... . 8.2-2 l 8.3 Onsite Power Systems . . . . . ... . . . .. .. 8.3-1 8.3.1 AC Power Systems . . . .... .. .. . . . 8.3-11 8.3.2 DC Power Systems . . ...... ... .. ... . ... . 8.3-13 l 8.3.3 Combined License Information for Onsite Electrical Power . 8.3-21 8.3.4 References . . . .. . . . .. .. . . 8.3-22
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| , O Revision: 10 3 Westingt!3USB xy December 20,19%
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| a Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page CHAlrTER 9 AUXILIARY SYSTEMS . . . . . . . . . . . .. ... .. ....... . . . 9.1-1 9.1 Fuel Storage and Handling . . . . . . . .. .... .... . .. . . . 9.1-1 9.1.1 New Fuel Storage . . . ........ ... . . . . ...... . . . 9.1-1 9.1.2 Spent Fuel Storage . . . . . .. ... .. . . . . .. . ... 9.1-5 9.1.3 Spent Fuel Pool Cooling System .... .. . . . 9.1-10 9.1.4 Light Load Handling System (Related to Refueling) . . . . .. . . . . 9.1-21 9.1.5 Overhead Heavy Load Handling Systems .. .. ... ... . 9.1-34 9.1.6 Combined License Information for Fuel Starage Handling . .. . 9.1-40 9.1.7 References . . ..... . ..... .. . . ... .. . 9.1-40 9.2 Water Systems . . .. . ... .. ... . . . .. . . 9.2-1 9.2.1 Service Water System . .. . .... . . .. . ... . . 9.2-1 9.2.2 Component Cooling Water System ...... ... ..... . . 9.2-7 9.2.3 Demineralized Water Treatment System . . . . . . . . ... . . . 9.2-16 9.2.4 Demineralized Water Transfer and Storage System . . ... . . 9.2-20 9.2.5 Potable Water System ..... .. . .. .. . . . . . 9.2-25 9.2.6 Sanitary Drainage System . . . .. . . .. . .. . 9.2-28 9.2.7 Central Chilled Water System ... .... .. . ..... .. . . 9.2-30 9.2.8 Tubine Building Closed Cooling Water System . .... . . . . . 9.2-36 9.2.9 Waste Water System . . . . . . . . ....... . ... . . 9.2-40 9.2.10 Hot Water Heating System ...... . .. . ..... . . . 9.2-44 9.2.11 Combined License Information . .... . .... . .. . . . 9.2-47 9.2.12 References . ..... ........ ... . .. .. .. . . . 9.2-48 9.3 Process Auxiliaries ............ .. . . . .. .... ..... . 9.3-1 9.3.1 Compressed and Instrument Air System ..... . . ... . . . 9.3-1 l 9.3.2 Plant Gas System . . . . . . . . . . . . . . .. ... .. . . . 9.3-7 j 9.3.3 Primary Sampling System . . . . . . . . . . ..... .. . . 9.3-10 !
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| 9.3.4 Secondary Sampling System . . .... . . .. . . . 9.3-15 j 9.3.5 Equipment and Floor Drainage Systems . ... .. . . . 9.3-17 9.3.6 Chemical and Volume Control System ... . . . .. . . 9.3-22 9.3.7 Combined License Information ..... . . .. . 9.3-43 l 9.3.8 References . . . . . .. . . . .. .. . . . . 9.3-43 Volume 6 l 9.4 Air-Conditioning, Heating, Cooling, and Ventilation System . .. 9.4-1 !
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| l 9.4.1 Nuclear Island Nonradioactive Ventilation System ... . . .. 9.4-1 l 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System . 9.4-15 9.4.3 Radiologically Controlled Area Ventilation System . . . . 9.4-26 i 9.4.4 Balance-of-Plant Interface . . . . .. .. . ... .. . . 9.4-36 l 9.4.5 Engineered Safety Features Ventilation System . . ... . 9.4-36 l 9 l
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| Revision: 10 December 20,1996 xy Westingh0USS l
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| Section Title Pagc,,
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| 9.4.6 Containment Recirculation Cooling System ........ ..... . . 9.4-36 9.4.7 Containment Air Filtration System .. ............... . . 9.4-41 9.4.8 l
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| Radwaste Building HVAC System ... ...... ... .... . 9.4-49 1 9.4.9 Turbine Building Ventilation System ........ ...... . . 9.4-54 9.4.10 Diesel Generator Building Heating and Ventilation System ... . 9.4-59 l 9.4.11 Health Physics and Hot Machine Shop HVAC System .. . . . . 9.4-65 9.4.12 Combined License Information . . . ......... .... . . . 9.4-70 9.4.13 References ..... ... .. .. . ........... . . 9.4-70 I 9.5 Other Auxiliary Systems . . . . . . .... . ....... .. ..... . 9.5-1 9.5.1 9.5.2 Fire Protection System .....
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| Communication System ..
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| . . 9.5-1
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| . 9.5-14
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| l 9.5.3 Plant Lighting System . . . ... . ... .. . .. . .... 9.5-18 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System . .... . . 9.5-21 9.5.5 References . . . .... .. . . . .. ... ..... . 9.5-27 APPENDIX 9A FIRE PROTECTION ANALYSIS . . .. . .... . . 9A-1 9A.! Introduction . . . . . . . ........... . . .. . . . 9A-1 9A.2 Fire Protection Analysis Methodology . . . . .. ... . . 9A-1 9A.2.1 Fire Area Description . . . .
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| {/}
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| u 9A.2.2 Combustible Material Survey . . . .
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| . . . 9A- 1
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| . 9A-2 9A.2.3 Fire Severity Categorization . . . . . . . ... ... ........ . . 9A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations . . . . . . . . . . . .. .... ... . ....... . . . 9A-2 9A.2.5 Fire Protection Adequacy .. .. ...... .... . . .. 9A-3 9A.2.6 Fire Protection System Integrity ........... . ......... 9A-4 9A.2.7 Safe Shutdown Evaluation . ...... .. . . .. .. ... . 9A-4 9A.3 Fire Protection Analysis Results . . .. . . . . . . . .. . 9A-8 9A.3.1 Nuclear lsland ...... ... .. . .... ........ . . . . . . 9A-9 9A.3.2 Turbine Building . . . ...... .. ... ...... .. .. . 9A-61 9A.3.3 Yard Area And Outlying Buildings .. . ..... . .. 9A-72 9A.3.4 Annex I and Il Buildings . . . . . . .. .. .... .. . . 9A-72 9A.3.5 Radwaste Building .. .. .. . . . . . . . 9A-88 9A.3.6 Diesel Generator Building . ... . .. .. .. 9A-90 9A.3.7 Special Topics . . . . . . . . ...... . . 9A-94 9A.4 References . ... .. . .. . .... .. ... . 9A-97 Volume 7 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM .... .. . . 10.1-1 10.1 Summary Description .. ... .... . . 10.1-1 10.1.1 Generai Descriptionn . . . . . . . . ... . . . 10.1-1 (gv
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| 10.1.2 Protective Features . . . . ... . ... . . . . .. . 10.1-2 Revision: 10
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| [ WBStingh00Se xvii December 20,1996
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| Section Title fage a
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| 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . . 10.1-4 i 10.2 Turbine-Generator . . . . . . . .... .. . . . .... .... . 10.2-1 10.2.1 Design Basis 10.2-1 10.2.2 System Description . . . . .... . .... ... .... . 10.2-1 l
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| 10.2.3 Turbine Rotor Integrity . . ... . .. .. . . ... . 10.2-11 !
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| 10.2.4 Evaluation . . . . . . ..... . . . ..... . . ...... . 10.2-17 10.2.5 Instrumentation Applications .. . ..... ... .... 10.2-17 I 10.2.6 Combined License Information on Turbine Maintenance l and inspection . . ...... ... . . . ...... .. ..... . 10.2-19 10.2.7 References . . ......
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| f
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| . . . .. . . ...... . 10.2-19 10.3 Main Steam Supply System . . . . . . ..... .. . . . 10.3-1 10.3.1 Design Basis .. ... . . . ..... . ...... 10.3-1 l
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| 10.3.2 System Description . . . . . . . . . . ... 10.3-4 '
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| 10.3.3 Safety Evaluation . . . . . . . .. .... . .. . . 10.3-10 10.3.4 Inspection and Testing Requirements . .. . .. .. ....... 10.3-12 10.3.5 Water Chemistry .. .... ... . . .. .. . .. .... 10.3-12 10.3.6 Steam and Feedwater System Materials . . . .... . .. 10.3-16 10.3.7 Combined License Information . . . . . . .. . . . . . 10.3-17 l 10.3.8 References . . . . . . . . . . . . . . . ..... . .... .. . 10.3-17 10.4 Other Features of Steam and Power Conversion System 10.4-1 l
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| 10.4.1 Main Condensers . . .. . .... . .. . .. . . . 10.4-1 10.4.2 Main Condenser Evacuation System . . . . . .. ..... . 10.4-4 10.4.3 Gland Seal System ... . . . . .. .... . . . . 10.4-6 l 10.4.4 Turbine Bypass System . .. ... . ............. . . . . 10.4-8 )
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| 10.4.5 Circulating Water System . . . . . . .. .. . . ... 10.4-12 10 4.6 Condensate Polishing System . . ...... ... . . . . .. 10.4-17 10.4.7 Condensate and Feedwater Systems ... .. . ... .. . 10.4-20 10.4.8 Steam Generator Blowdown System . . 10.4-35
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| )
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| 10.4.9 Startup Feedwater System .. . . ... . . .. . 10.4-44 ;
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| 10.4.10 Auxiliary Steam System . . . . . . . ... .. . .... . . . 10.4-53 l 10.4.11 Turbine Island Chemical Feed . . . . . ..... . 10.4-56 I 10.4.12 Combined License Information . .. . .. . .. 10.4-59 I 10.4.13 References . . . ... . 10.4-59 i
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| CHAl'TER 11 RADIOACTIVE WASTE MANAGEMENT . . .. . .. . . I1.1-1 I i1.1 Source Terms .. ... . . ... . ... . .. . I1.1-1 11.1.1 Design Basis Reactor Coolant Activity . . ... . .. I1.1-1 11.1.2 Design Basis Secondary Coolant Activity ... .. . 11.1-3 11.1.3 Reahstic Reactor Coolant and Secondary Coolant Activity .. I1.1-4 )
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| 11.1.4 Core Source Term . . .. .. . . I1.1-4 O
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| Resision: 10 !
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| December 20,1996 xviij Westinghouse l
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| 1 Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 11.1.5 Process Leakage Sources .... . . . . . ...... .. . I1.1-4 11.1.6 Combined License Information . .. . . . . .... . . ... I1.1-4 11.1.7 Re0rences . .. .. .. .. ....... . .. . . 11.1-5 i 11.2 Liquid Waste Management Systems .. ... .. ... . . . . .. 11.2-1 11.2.1 Design Basis . . . .... .. . . . ... . . ..... 11.2-1 i 11.2.2 System Description . . . . . . . . . .. . .. .... .... 11.2-6
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| .2.3 Radioactive Releases . . . . . ... . .. .. .... .. I1.2-18 11.2.4 Combined License Information . ... ..... . ... .. .. I1.2-20 l 11.2.5 References . . . . ... .. ........ . .. .... .... 11.2-20 11.3 Gaseous Waste Management System . ... .... . . . .. .. 11.3-1 11.3.1 Design Basis . . . . . . . . . . . .. . . .. .... .. 11.3-1 11.3.2 System Description . . . .... . . .. . .. . . ... .. 11.3-4 11.3.3 Radioactive Releases . . . . . . .. . I1.3-9 11.3.4 Combined License Information .... .. .. I1.3-11 11.3.5 References . . . ....... . .. . . . . . 11.3-11 11.4 Solid Waste Management ... . . . . . . .. . . .. I1.4-1 11.4.1 Design Basis . .. . . .. . . . . 11.4-1 11.4.2 System Description . . . . . . . . . ... . I1.4-3 (3 11.4.3 System Safety Evaluatim . . . ....... .. . ..... . I1.4-13 V 11.4.4 Tests and Inspections . . .
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| 11.4.5 Quality Assurance . . . . . .
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| ... . .. ..... . . . . 11.4-13
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| . . . .... . . .. . 11.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program ... .. .. ... .. I1.4-13 11.4.7 References . . . . . . . . . .. . ... .... . . . 11.4-14 l 11.5 Radiation Monitoring . . . . . . . .. . .. . . . . . .... . 11.5-1 I 11.5.1 Design Basis . ......... ..... . . ... ...... .. 11.5-1 !
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| 11.5.2 System Description . .. .... ..... .. . . . . . . 11.5-2 11.5.3 Effluent Monitoring and Sampling .. .. . .... .. .. I1.5-13 11.5.4 Process and Airbome Monitoring and Sampling . .. .. I1.5-13 11.5.5 Post-Accident Radiation Monitoring . . .. . . . 11.5-14 11.5.6 Area Radiation Monitors .. . .... .... .. .. . 11.5-14 l 11.5.7 Combined License Information . . . . .. .... . .. . 11.5-17 CHAPTER 12 RADIATION PROTECTION ..... .... . ... . . . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As-Low-As-Reasonably Achievable (ALARA) . . . . .. .. . .. 12.1-1 12.1.1 Policy Considerations . . . . . . . .. . . ..... ... . 12.1-1 12.1.2 Design Considerations . . ... . . . .. . ..... . 12.1-2 12.1.3 Combined License Information . . . . . . . . . ..... . . . . . . . 12.1-6 12.2 Radiation Sources . . . . . .... .. ... .. ... .. .. .. 12.2-1 12.2.1 Contained Sources . ......... . . ..... .. . 12.2-1 12.2.2 Airbome Radioactive Material Sources . . ... .. . .. . 12.2-6 i
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| Revision: 10
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| [ W85tingt10USB xix December 20,1996
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| musman:=
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pse 12.2.3 Combined License Information . .... .... .. ....... . 12.2-8 12.2.4 References .... ........ .. ..... ... . ...... 12.2-8 12.3 Radiation Protection Design Features . ........... .. . . .. .. 12.3-1 12.3.1 Facility Design Features . . . . .. . ..... . .... . .. 12.3-1 12.3.2 Shielding . .... .. .. . .. . ....... .. .. . 12.3-9 12.3.3 Ventilation . . . . . . . . . ...... ... . . . 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instmmentation . ..... .. .. .. . .. 12.3-19 12.3.5 Combined License Information . . ... . . .... 12.3.19 12.3.6 References ........ . . . . . .. . 12.3-19 12.4 Dose Assessment .. .... . .. . . . . . . 12.4-1 12.4.1 Occupational Radintion Exposure . . . .. .... 12.4-1 ;
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| 12.4.2 Radiation Exposure at the Site Boundary . . .... . 12.4-4 12.4.3 Combined License Information . ..... . . ... 12.4-4 i
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| 12.5 Health Physics Facilities Design . . . . ... .. 12.5-1 12.5.1 Objectives ...... ... . .. .. ... 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities . . . .. . . . . . . 12.5-1 12.5.3 Other Design Features . .... .. . . ... ..... 12.5-3 12.5.4 Controlling Access and Stay Time ... .. . . .. . . 12.5-4 12.5.5 Combined License Information . . . ...... . . .. 12.5-5 I
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| Volume 8 '
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| CHAPTER 13 CONDUCT OF OPERA' HON . . . .. . . . . . . 13-1 13.1 Organizational Structure of Applicant . ......... . . .... . 13-1
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| {
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| 13.1.1 Combined License lnformation item . . . . . . . . ... .. 13-1 '
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| 13.2 Training ... . ....... . . .... . ... 13-1 13.2.1 Combined License Information Item . . ... .. 13-1 13.3 Emergency Planning . .... . . . . .. ... .. . 13-1 13.3.1 Combined License Information Item . . . . .... 13-2 i 13.4 Operational Review ..... . . 13-2
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| {
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| 13.4.1 Combined License Information Item . . .. . ... . 13-2 l 13.5 Plant Procedures .... . . . . . 13-2 l 13.5.1 Administrative Procedures . . . .. . . . . 13-2 i 13.6 Industrial Security ..... .. ... . . . . . . . . . . . 13-3 13.6.1 Preliminary Planning . . . . ... . .. . . 13-3 13.6.2 Security Plan ...... . . .. . ... . .. .. 13-3 13.6.3 Plant Protection System . . . . . 13-3 13.6.4 Physical Security Organization . . 13-5 13.6.5 Physical Barriers . . .. . . . 13-5 e i Resision: 10 ;
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| December 20,1996 xx 3 Westiflgh00Se I
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| Section Title Page 13.6.6 Access Requirements ... . .... .. .. . . ..... . . .. 13-6 13.6.7 Detection Aids . . . . . . . ........ ... ........ .. . 13-7 13.6.8 Security Lighting . . . . . . .. .... ... .. ........ .. .. 13-7 13.6.9 Security Power Supply System ... . . . ..... . . . 13-7 13.6.10 Communications . . . ... . . . . .... ..... 13-7 13.6.11 Testing and Maintenance . . .. . .... . .. ... . 13-8 13.6.12 Response Requirements .... . . . ......... .. 13-8 13.6.13 Combined License Information Item . . . ... 13-8 13.7 References . . . .. ....... . .... . . . . .. . . 13-8 CHAPTER 14 INITIAL TEST PROGRAM ..... .... . ........... . 14.1-1 14.1 Specific Information to be Included in Preliminary / Final Safety Analysis Reports . ...... . ... . .. ... . . .. . . 14.1-1 l 14.2 Specific Information to be Included in Standard Safety Analysis Reports . . 14.2-1 l 14.2.1 Summary of Test Program and Objectives . . . . . . . 14.2-1 14.2.2 Organization, Staffing, and Responsibilities . .. . .. . 14.2-4 ;
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| 14.2.3 Test Specifications and Test Procedures . . . .. .......... . 14.2-4 1 14.2.4 Compliance of Test Program with Regulatory Guides ..... ... 14.2-6
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| (~T 14.2.5 Utilization of Reactor Operating and Testing Experience in the
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| () Development of Test Program - .. . ... . .... . . 14.2-6 14.2.6 Use of Plant Operatirg and Emergency Procedures . . . . . . 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality . . .. ..... . . 14.2-7 14.2.8 Test Program Schedule .. .... . .. . . . . .. . 14.2-10 .
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| 14.2.9 Preoperational Test Descriptions .... . .... . . . 14.2-10 14.2.10 Startup Test Procedures . . . . ..... .. .......... . 14.2-80 14.3 Ce:tified Design Material . . . . ... . .. .. . . .... . . . . 14.3-1 14.3.1 CDM Section 1.0, Introduction . . . .... . . 14.3-2 14.3.2 CDM Section 2.0, System Based Design Descriptions and ITAAC . . . . . .... . . ... . .. . 14.3-3 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC . ... ..... . ... .... .. . 14.3-9 14.3.4 Certified Design Material Section, 4.0 Interface R.equirements . 14.3-10 14.3.5 CDM Section 10, Site Parameters . ..... 14.3-10 14.3.6 Initial Test Program . .... .. . . . . . . ... . 14.3-10 14.3.7 Summary . . ..... ..... . .. . . ... . . .. . 14.3 11 14.3.8 References . . . .. ...... . . . . ... 14.3-11 14.4 Combined License Applicant Responsibilities . . . .. .... . 14.4-1 14.4.1 Organization and Staffing . . . . ... .. . . . .... 14.4-1 14.4.2 Test Specifications and Procedures . . . .. . .. 14.4-1 14.4.3 Conduct of Test Program . . . ... .. . .. 14.4-1 14.4.4 Review and Evaluation of Test Results . . . . 14.4-1 rh (V !
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| Revision: 10 W Westirighouse xxi December 20,1996 l
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| M Master Table of Contents n-MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page CHAPTER 15 ACCIDENT ANALYSES . . .. . . . ......... . .. . . . 15.0-1 15.0.1 Classification of Plant Conditions . . ....... ........ . . .. . 15.0-1 15.0.2 Optimization of Control Systems . . . . . . . ....... ........ ... . 15.0-5 15.0.3 Plant Characteristics and Initial Conditions Assumed in the Accident Analyses . . . . .. .. . . ..... .... . . . . . . 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysis . . . ... .. . 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics . . . . . 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses ..... . 15.0-8 15.0.7 Instrumentation Drift and Calorimetric Errors, Power Range Neutron Flux . . . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . . . .. .. . .... .. .. .. . 15.0-10 15.0.10 Residual Decay Heat . .... .. . .. .. . . . . . 15.0-10 15.0.11 Computer Codes Utilized . . . . . . ... . .. .. .. . 15.0-11 15.0.12 Component Failures .. .... ., ,.. ... ... ... . . . 15.0-13 15.0.13 Operator Actions .. ... . .. .. ... ..... ... . .... . 15.0-14 15.0.14 Combined License Information . . .. .. ........ . . . 15.0-14 15.0.15 References . . . . . ........... . .. . . .... . ....... 15.0-14 15.1 Increase in Heat Removal from the Primary System . . . . . . . . 15.1-1 15.1.1 Feedwater System Malfunctions that Result in a Decrease in Feedwater Temperature . .. .. . ... ... . .. .. 15.1-1 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow ... . ... ..... .. ..... .. . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow . . . . .. ..... . 15.1-5 15.1.4 Inadvertent Opening of a Steam Generator Relief or Safety Valve . . 15.1-8 15.1.5 Steam System Piping Failure . . . .. ...... . .. . .. 15.1-11 15.1.6 Inadvertent Operation of the Passive Reridual Heat Removal Heat Exchanger . . . . .. . . . ...... . . .. .. 15.1-20 15.1.7 Combined License Information . . . .. .. . ... .. 15.1-24 1 15.1.8 References . . ... .. .. .. ..... . 15.1-24 l 15.2 Decrease in Heat Removal by the Secondary Systera . . ... .... . 15.2-1 i 15.2.1 Steam Pressure Regulatc r Malfunction or Failure that Results in j Decreasing Steam Flow .. . .. .... .. . 15.2-1 l 15.2.2 Loss of Extemal Electrica1 Load . ... . . .. . 15.2-1 j 15.2.3 Turbine Trip . ... .. ... .... . . . . . 15.2-3 15.2.4 Inadvertent Closure of Main Steam Isolation Valves . . . . . . 15.2-7 15.2.5 Loss of Condenser Vacuura and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries . . . . . .. .. . 15.2-8 15.2.7 Loss of Normal Feedwater Flow . ... ...... . . . ... 15.2-12 15.2.8 Feedwater System Pipe Break . . . .. .. 15.2-16 15.2.9 Combined License Information . . . .. . . .. . 15.2-21 0:i Revision: 10 December 20,1996 xxii 3 W85tifigt10US8 1
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| Master Table of Contents -
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| k/ MASTER TABLE OF CONTENTS (Cont.)
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| Section Title ,P_ age 15.2.10 References . . . . .. ..... . .... ... . 15.2-21 15.3 Decrease in Reactor Coolant System Flow Rate . .... ....... 15.3-1 15.3.1 Partial Loss of Forced Reactor Coolant Flow ... . .. . . 15.3-1 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . . .. . . 15.3-3 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . . . . . 15.3-5 15.3.4 Reactor Coolant Pump Shaft Break . . ..... . .. .... . 15.3-10 15.3.5 Combined License Information . . ..... . .. . ... . 15.3-10 15.3.6 References . .. .... . . . ..... . . . . .. 15.3-11 15.4 Reactivity and Power Distribution Anomalies . . . . . . . 15.4-1 .
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| 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Suberitical or Low-Power Startup Condition ..... . . . . 15.4-1 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power . . . .... .. . . . 15.4-5 15.4.3 Rod Cluster Control Assembly Misalignment (System Malfunction or Operator Error) .......... .. . .... . 15.4-11 15.4.4 Startup of an Inactive Reactor Coolant Pump at an incorrect l
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| Temperature .....,............ .. .. . 15.4-17 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling Water Reactor Loop that Results in an Increased Reactor
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| ('~)S
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| ( Coolant Flow Rate .. . .... .... . . . ..... 15.4-19 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant ......... . . . .. . . . . 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position . . . ... ....... . .. .. .... 15.4-25 15.4.8 Spectmm of Rod Cluster Control Assembly Ejection Accidents ... 15.4-28 15.4.9 Combined License Information . .. ..... .. .. . . 15.4-39 15.4.10 References . . . . .... . .. ..... .. ... .. 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory . . . . . . . . . . 15.5-1 15.5.1 Inadvertent Operation of the Core Makeup Tanks (CMT) During Power Operation . ...... ... .. ... .. 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory . ... . .. . ... 15.5-4 15.5.3 Boiling Water Reactor Transients . . .. . . . . . 15.5-8 15.5.4 Combined License Information . . . .. ... ... .. . 15.5-8 15.5.5 References . ... .... ...... .. .. . . .. . .. 15.5-8 15.6 Decrease in Reactor Coolant Inventory ... .. . . .. . .. 15.6-1 15.6.1 Inadvertent Opening of a Pressurizer Safety Valve or
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| , Inadvertent Operation of the ADS .. . . 15.6-1 Revision: 10 3 W85tillgt10tlSe xxii December 20,1996
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| u--L Master Table of Contents m-MASTER TABLE OF CONTENTS (Cont.)
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| Section Title .P_ age 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . . . ..... ... ....... . . . . . . . . 15.6-4 15.6.3 Steam Generator Tube Rupture . .. . . . .. .. . 15.6-5 15.6.4 Spectrum of BWR Steam System Piping Failures Outside of Containment . .... . . ... . . . ... 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . . . . . . . . . .. 15.6-15 15.6.6 References . . .. . .. . .. . . . .. ... . 15.6-64 15.7 Radioactive Release From a Subsystem or Component . .... . . 15.''-l 15.7.1 Gas Waste Management System Leak or Failure . . . ... .... . 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) .. ... ..... . . . . . . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure . . .... .. . .... . . ..... 15.7-1 15.7.4 Fuel Handling Accident . .. . .. . .... . . . 15.7-1 15.7.5 Spent Fuel Cask Drop Accident . . . .. .. . 15.7-6 15.7.6 Combined License Information . .. . .. ... . 15.7-6 15.7.7 References . . . . . . ..... . ... . . . . 15.7-7 15.8 Anticipated Transients without Scram .. . . . ....... . 15.8-1 15.8.1 General Background . ...... . .. . .. .. . . 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . . . . . . . .. 15.8-1 15.8.3 Conclusion . . . . . .. ...... ... . .. . . . . . . 15.8-1 15.8.4 Combined License Information . . ... ... .. . 15.8-1 15.8.5 References .... ..... . .. . . . . ... ... .. 15.8-1 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS . . . 15A-1 15A.1 Offsite Dose Calculation Models . .. .. .. . . 15A-1 15A.l .1 Immersion Dose Models . . . . . . . . 15A-1 15A.1.2 Inhalation Dose (Committed Effective Dose Equivalent) . 15A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) . . . . . . 15 A-2 15A.2 Main Control Room Dose Models . . . . . . . . . . .. .. . 15A-2 15A.2.1 Immersion Dose Models . ... . . . . . . . 15A-2 15A.2.2 Inhalation Dose ...... . ... . . 15A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) . ... . . 15A-4 15A.3 General Analysis Parameters . . .... . ... . . . . 15A-4 15A.3.1 Source Terms . .. . . . ...... . 15A-4 15A.3.2 Nuclide Parameters ... . . . . . . . 15A-6 15A.3.3 Atmospheric Dispersion Factors .. . . . ... . . 15 A-6 15A.4 References .. . ..... . . . . 15A-6 O\
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| Revision: 10 December 20,1996 xxiv T Westingh0use J
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| Master Table of Contents
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| ('v) MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page !
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| Volume 10 l
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| CHAITER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS . . . . . .. . . ............ 16.1-1 16.1.1 Introduction to Technical Specifications . .. ...... . . . . 16.1 -1 1.0 Use and Application .... . . . . .. .. ... .. . ... 1.1-1 l 1.1 Defm' itions . . . .. .. ... . ... .. .. . . . . 1.1-1 l 1.2 Logical Connectors . . . . . . ....... ..... 1.2-1 1 1.3 Completion Times . . . . . . . . ..... 1.3-1 l.4 Frequency .... .. . .. . . ... . . ... 1.4-1 i 2.0 Safety Limits (SLs) . ..... .... . .... . . ... 2.0-1 2.1 SLs .. .... .. . . . ... .. . .. 2.0-1 2.2 SL Violations .... . . . . . . ... ... . 2.0-1 !
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| 3.0 Limiting Conditions for Operation (LCO) Applicability . .... 3.0-1 I 3.0 Surveillance Requirement (SR) Applicability . . . . .... 3.0-4 3.1 Reactivity Control Systems .. .... . ......... . .. . 3.1-1 l 3.1.1 Shutdown Margin (SDM) .. .... .. . ...... . 3.1-1 3.1.2 Core Reactivity . .. .. ... ..... . .... . 3.1-2
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| ~} 3.1.3 Moderator Temperature Coefficient (MTC) 3.1 -4
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| {V 3.1.4 Rod Group Alignment Limits .... ............ 3.1-6 )'
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| 3.1.5 Shutdown Bank Insertion Limits .... . ........ 3.1-11 3.1.6 Control Bank Insertion Limits .. ... .. . . . . . . . . 3.1 - 13 3.1.7 Rod Position Indication ..... ..... .... .. 3.1-16 3.1.8 Physics Tests Exceptions - Mode 2 . .... .. . . . . . 3.1-18 3.1.9 Chemical and Volume Cor.*rol System (CVS) Demineralized Water Isolation Valves . ... . . . 3.1-20 3.2 Power Distribution Limits . . . . . . . . . . ....... .... . 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fq (Z)) ;
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| (FqMethodology) ... . ... . ... . . 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) . .. . ... ... . .. . .. 3.2-5 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . . . .. . 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . . . . .. . 3.2-10 3.2.5 OPDMS-Monitored Power Distribution Parameters . . . . . . . . .. . .. ... 3.2-14 3.3 Instrumentation . ..... .. .. .. . .... .. . . 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation . . . 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instmmentation . . ... . . 3.3-17 1 3.3.3 Post Accident Monitoring (PAM) Instrumentation .. 3.3-45 3.3.4 Remote Shutdown Workstation .... .... . ... . 3.3-48 C
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| Revision: 10
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| [ W85tiligh0US6 xxy December 20,1996
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| e--n Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.4 Reactor Coolant System (RCS) . . . ......... . . . 3.4-1 3.4.1 RCS Pressure. Temperature, and Flow Depanure from Nucleate Boiling (DNB) Limits .. .. .. 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . .. . . 3.4-3 3.4.3 RCS Pressure and Temperature (P/F) Limits . .. .... 3.4-4 3.4.4 RCS Loops - Modes 1 and 2 ... . . .. . .. . 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . . 3.4-7 3.4.6 Pressurizer . . .. . . .. . . 3.4-9 3.4.7 Pressurizer Safety Valves . . . 3.4-10 3.4.8 RCS Operational Leakage . . . . . . 3.4-12 3.4.9 Minimum RCS Flow . .. .. 3.4-14 3.4.10 RCS Leakage Detection Instrumentation . . . . ... 3.4-15 3.4.11 RCS Specific Activity . . . .. .. . . . 3.4-18
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| ' 4.i2 Automatic Depressurization System (ADS) - Operating . 3.4-20 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Intact . . .. . . .. .. .. .... . . . 3.4-22 3.4.14 Automatic Depressurization System (ADS) - Shutdown, RCS Open . . . . .. ... . . ... . 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . .... . . . . .. 3.4-26 3.5 Passive Core Cooling System (PXS) . .... .... .. . 3.5-1 3.5.1 Accumulators . . .. .... ... ... ... .. 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating ....... .. . 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . .. 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX)- Operating .... ..... . ...... 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . . . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST) -
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| Operating . . ..... . . . . . . 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory High . . .. . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low . ... .. .... 3.5-18 3.6 Containment Systems . . . . . ...... . .. . . 3.6-1 3.6.1 Containment . . . .. ..... . .. ... .. . 3.6-1 3.6.2 Containment Air Locks . . . . . . . .... ..... 3.6-3 3.6.3 Containment Isolation Valves ... .. . . ... . 3.6-7 3.6.4 Containment Pressure . . . . . 3.6-12 3.6.5 Containment Air Temperature . . ... . . 3.6-13 O
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| Revision: 10 December 20,1996 xxvi [ W8@WS8
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| Section Title Pm 3.6.6 Passive Containment Cooling System (PCS) - Operation . 3.6-14 1 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . 3.6-17 I 3.6.8 Containment Penetrations . . .......... . . . . 3.6-19 3.6.9 pH Adjustment . . . . ....... ......... . . 3.6-22 3.7 Plant Systems . . . . . . . ... .......... .. . ... . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) .. ... .... . 3.7-1 j 3.7.2 Maia Steam Isolation Valves (MSIVs) . . .. . . . . 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves I 1
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| (MFIV and MFCV) . . . . ....... .. . . . . 3.7-7 3.7.4 Secondary Specific Activity . . ....... .. ... . . 3.7-9 3.7.5 Spent Fuel Pool Water Level . . . . .. . . . .. .. .. 3.7 10 3.7.6 Main Control Room Habitability System (VES) . . . . . . 3.7-11 3.7.7 Startup Feedwater Isolation and Control Valves . . .... 3.7-15 ,
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| 3.8 Electrical Power Systems . . . . .. . ... . . . 3.8-1 l 3.8.1 DC Sources - Operating . . . . ...... . 3.8-1 3.8.2 DC Sources - Snutdown . . . ..... . ......... 3.8-5 3.8.3 Inverters - Operating . .... . .. .. .. ... ... 3.8-7 3.8.4 Inveners - Shutdown . . . . . ... ...... .... 3.8-9
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| (] 3.8.5 Distribution Systems - Operating ...... .. .. . . . 3.8-11
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| (/ 3.8.6 Distribution Systems - Shutdown ... ...... . . . . . 3.8-13 3.8.7 Battery Cell Parameters . . ....... ...... . 3.8-15 j 3.9 Refueling Operations .... . . . . ........ ..... 3.9-1 3.9.1 Boron Concentration . . . . .... . .... ..... ... 3.9-1 3.9.2 Unborated Water Source Flow Paths . . . . .... . . 3.9-2 3.9.3 Nuclear Instrumentation . . . . ... .. .... .. .. 3.9-4 3.9.4 Refueling Cavity Water Level . . . . . ..... .. . . 3.9-6 4.0 Design Features ... . .. .. ..... .... . .. 4.0-1 4.1 Site . ....... ... .... ........ .... . 4.0-1 4.1.1 Site and Exclusion Boundaries . . .. . . . 4.0-1 4.1.2 Low Population Zone (LPZ) . . . . . .. . . 4.0-1 4.2 Reactor Core ..... ... ... .. . . .... . . 4.0 1 4.2.1 Fuel Assemblies . . . . . .. ... . . . 4.0-1 ;
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| 4.2.2 Control Rod and Gray Rod Assemblies . . .... 4.0-1 4.3 Fuel Storage . . . .. . . ...... . . . 4.0-2 4.3.1 Criticality . . .. .... . . . . . 4.0-2 4.3.2 Drainage . . . .......... . .. . . 4.0-2 4.3.3 Capacity . . .. . ... . . .. . 4.0-2 !
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| 4.4 Hydrogen Control . . . ... . .. . 4.0-3 l 4.4.1 Passive Autocatalytic Recombiners (PARS) .. . 4.0-3 I 5.0 Administrative Centrols ... .. ... . .. ... . . . 5.0-1 l 5.1 Responsibility . . ... . . . . . ... .. . . 5.0-1 g 5.2 Organization . . . . ... .. .. ... ... .... 5.0-2 i ) l C/
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| Revision: 10 3 W85tilighouse xxvii December 20,1996
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| 1 E-- J l Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 5.3 Unit Staff Qualifications ... . . . .. . . . . . 5.0-5 5.4 Procedures ... .... .. . ..... . 5.0-6 5.5 Programs and Manuals . . .. . . . . . .. 5.0-7 5.6 Reponing Requirements . . . .. . .. . . 5.0-15 B 2.0 Safety Limits (SLs) . ... ... . . . . .. . . . B 2.0-1 B 2.1.1 Reactor Core Safety Limits (SLs) . . . . . B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . B 2.0-6 l B 3.0 Limiting Conditions for Operation (LCO) Applicability .. . . . B 3.0-1 B 3.0 Surveillance Requicment (SR) Applicability .. .. . B 3.0-12 B 3.1 Reactivity Control Systems . ...... . . ... . . B 3.1-1 l B 3.1.1 Shutdown Margin (SDM) ........ B 3.1-1 B 3.1.2 Core Reactivity . .. ... . B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) B 3.1-13 !
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| B 3.1.4 Rod Group Alignment Limits . B 3.1-19 l
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| B 3.1.5 Shutdown Bank Insenion Limits .. . . B 3.1-29 1 B 3.1.6 Control Bank Insenion Limits . .. . . B 3.1-34 B 3.1.7 Rod Position Indication . . .. . B 3.1-40 B 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . . B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS) l Demineralized Water Isolation Valves . . . . B 3.1-53 I B 3.2 Power Distribution Limits . . . .. ... B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (Fn (Z))
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| (FoMethodology) . .. . . . . . . . B 3.2-1 l B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor !'
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| (F%) . . ... . . .... B 3.2-10 B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . . B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QPTR) .. .. B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters . . . .. ... . . B 3.2-28 B 3.3 Instrumentation . . ... . . . ... . . . . B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation . B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation . . . . B 3.3-53 B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation ..... ... . . B 3.3-115 B ? 3.4 Remote Shutdown Workstation . . . . . . B 3.3-125 B 3.4 Reactor Coolant System (RCS) . . . ... B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Depanure from Nucleate Boiling (DNB) Limits . . . B 3.4-1 O
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| Revision: 10 December 20,1996 xxviii 3 Westinghouse
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| l Master Table of Contents
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| ,n.
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| V' MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age i
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| B 3.4.2 RCS Minimum Temperature for Criticality . . . . B 3.4-6 I B 3.4.3 RCS Pressure and Temperature (P/r) Limit; . . B 3.4-9 '
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| B 3.4.4 RCS Loops - Modes 1 and 2 . ... . .. B 3.4-17 B 3.4.5 RCS Loops - Modes 3,4, and 5 ... B 3.4-21 B 3.4.6 Pressurizer ................. .. . . . B 3.4-25 B 3.4.7 Pressurizer Safety Valves . . .. . .... . B 3.4-28 i B 3.4.8 RCS Operational Leakage . . ... . . B 3.4-32 l B 3.4.9 Minimum RCS Flow . . . . . . . . .. B 3.4-38 l B 3.4.10 RCS Leakage Detection Instrumentatior B 3.4-41 i B 3.4.11 RCS Specific Activity . . . . . . . .. . . B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)- ,
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| Operating . . . .. ..... . .. B 3.4-50 i B 3.4.13 Automatic Depressurization System (ADS)- l Shutdown, RCS Intact ..... ..... . . . B 3.4-54 i B 3.4.14 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Open . . . . . ..... ... B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . .. ... . . . . . . . . . B 3.4-60 I
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| (~~N B 3.5 Passive Core Cooling System (PXS) . . . . . . . . . . . . B 3.5- 1 l
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| Q) B 3.5.1 Accumulators ... . . ... .... . . B 3.5-1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . . . . . B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . ....... . . . . . . . . . B 3.5- 15 B 3.5.4 Passive Residual Heat Removal Hest Exchanger (PRHR HX) - Operating . .. . B 3.5-18 B 3.5.5 Passive Residual Heat Removal Heat Exchanger 1 (PRHR HX) - Shutdown, RCS Intact . . . . . B 3.5-24 I B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating ... .. . . . . B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory High B 3.5-34 B 3.5.8 In-containtnent Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low .. .. .. .... ... . .. . . . . . B 3.5-38 B 3.6 Containment Systems . ....... ........... B 3.6-1 B 3.6.1 Containment . . . . ......... . . . . . . B 3.6-1 B 3.6.2 Containment Air Locks .... ... . . B 3.6-6 B 3.6.3 Containment Isolation Valves ..... . B 3.6-13 B 3.6.4 Containment Pressure .. ..... .. B 3.6-23 B 3.6.5 Containment Air Temperatore . .. B 3.6-26 B 3.6.6 Passive Containment Cooling System (PCS) - Operating . .. .. . B 3.6-30 s
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| a)
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| Revision: 10 Westingh0tJse xxix December 20,1996
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| l 1
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) e\ l Section Title Pa_ge.
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| B 3.6.7 Passive Containment Cooling System l (PCS) - Shutdown . . . .. . .... . . .. B 3.6-37 B 3.6.8 Containment Penetrations . . .. . .. . B 3.6-40 B 3.6.9 pH Adjustment . . . . . . . . ......... . B 3.6-47 l B 3.7 Plant Systems . .. .. ......... ... .. B 3.7-1 I B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . B 3.7.7 l B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) . . . ... ... B 3.7-13 l B 3.7.4 Secondary Specific Activity . . . . . B 3.7-18 I B 3.7.5 Spent Fuel Pool Water Level . . . . . . B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability !
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| System . . . . . . . . . . . .. . . . . B 3.7-24 i B 3.7.7 Stanup Feedwater Isolation and Control Valves B 3.7-30 l B 3.8 Electrical Power Systems .. ... . .. ..... . B 3.8-1 i B 3.8.1 DC Sources - Operating . . . .. . .. . B 3.8-1 !
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| B 3.8.2 DC Sources - Shutdown . .. . .. ..... B 3.8-11 - !
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| B 3.8.3 Inverters - Operating . . .... ... .... B 3.8-15 i B 3.8.4 Inveners - Shutdown . ... .... B 3.8-20 l
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| B 3.8.5 Distribution Systems - Operating .. .. B 3.8-24 B 3.8.6 Distribution Systems - Shutdown .... . . . . . B 3.8.33 B 3.8.7 Battery Cell Parameters . . . .. ...... . B 3.8-37 I B 3.9 Refueling Operations . ... . . .. . ... . . B 3.9-1 ;
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| B 3.9.1 Baron Concentration . . ... . ...... B 3.9-1 B 3.9.2 Unborated Water Source Flow Paths . . . . B 3.9-5 B 3.9.3 Nuclear Instrumentation . . . . . . . ........ B 3.9-8 l B 3.9.4 Refueling Cavity Water Level ... .. B 3.9-11 Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM . .... . 16.2-1 16.2.1 Introduction . .... . . .. ... . .. . . .. . 16.2-1 16.2.2 Scope ......... .. .. ... . . ... . . ....... 16.2-1 16.2.3 Design Considerations . . .... ........ . . . . 16.2-1 16.2.4 Relationship to Other Administrative Programs ... .. . . 16.2-2 16.2.5 The AP600 Design Organization . .. . ....... ..... . 16.2-2 16.2.6 Ob;ective . . . ... ........ .. . ... . .... . . . 16.2-3 16.2.7 D RAP, Phase I . . . .... ... .. .. .. ... . . 16.2-4 16.2.8 Combined License Activities RAP . . . . . . . . 16.2-9 16.2.9 Olossary of Terms . ... . ....... ... . . . . 16.2-10 0
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| Revision: 10 December 20,1996 xxx WB5fingh0USB
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| Mast;r Tchte of Contents 1
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| lg s '
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| V MASTER TABLE OF CONTENTS (Cont.) I 1
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| Section Title P.,. age l
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| 16.2.10 References . . . . .. ...... .. . . . ...... . . 16.2-11 i CHAPTER 17 QUALITY ASSURANCE . ............... .. ....... .. . . 17.1-1 17.1 Quality Assurance During the Design and Constmetion Phases . . . . . . . . 17.1 -1 17.2 Quality Assurance During the Operations Phase . . . ... ..... . . . 17.1-1 l 17.3 Quality Assurance During Design. Procurement, Fabrication, Inspection l and/or Testing of Nuclear Power Plant Items and Services . . ... . . . . . 17.1 -1 17.4 Combined License Information Items ... . . . .. .. . . . 17.1-2 l 17.5 References .... ... ... . . .. ....... .. .. . . . . . . . 17.1 -2 l
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| 1 CHAPTER 18 HUMAN FACTORS ENGINEERING . . .... . ....... . . . . . . 18.1 - 1 l 18.1 Overview .... ........ . . .. ... .. . . . . . . . . . . 18.1 -1 !
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| 18.1.1 References . . . . . . . ........ .... ....... . . 18.1-4 18.2 Human Factors Engineering Program Management .. .... . I8.2-1 l 18.2.1 Human Factors Engineering Program Goals, Scope, l
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| Assumptions, and Constraints . . . . .. . .... . ........ . 18 2-1 l 18.2.2 Human System Interfaces Design Team and Organization ...... 18.2-4 l
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| 18.2.3 Human Factors Engineering Processes and Procedures . . . . .. .. I8.2-11 18.2.4 Human Factors Engineering Issues Tracking . . . . . . . . . . .... 18.2-17
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| () 18.2.5 Human Factors Engineering Technical Programs and ;
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| Milestones . . . .. .. .. ........ . .. . . . 18.2.18 18.2.6 Combined License lnformation . .. ... . . .. . . . . . . 18.2-19 18.2.7 References . . . . ... ..... . . . . . ..... . 18.2-19 18.3 Operating Experience Review . . .... .... ........ . 18.3-1 l 18.3.1 Combined License Information .. . .. ........ . . . . . 18.3-1 *i 18.3.2 References . . .. ....... .. .. . ...... .. . 18.3-1 18.4 Functional Requirements Analysis and Allocation . ..... .. . ...... I8.4-1 18.4.1 Combined License Information . . . . ... . ..... I8.4-2 18.4.2 References . . . . . . . . . . . . . . . . . . .... . . . . . . . 18.4-2 18.5 AP600 Task Analysis Implementation Plan . ... ...... . 18.5-1 18.5.1 Task Analysis Scope . ....... . . . . .. . 18.5-1 18.5.2 Task Analysis Implementation Plan . .. .. .. .... I8.5-2 18.5.3 Job Design Factors . ....... . . . .. . . . I8.5-5 18.5.4 Combined License Information Item . . .. ..... I8.5-5 18.5.5 References . . . . . . . . . .. .. . . . ... .. 18.5-5 18.6 Staffing ..... ....... . . .. .. . . .. . 18.6-1 18.6.1 Combined License Information Item . ... .... . .. . 18.6-1 18.6.2 References . . . . . . . . ... ..... . ....... .. . . 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering . 18.7-1 18.7.1 Combined License Information . . . . .. ....... .... . . . 18.7-1 18.7.2 References . .... . . . . .... . 18.7-1 18.8 Human System Interface Design . . . ... ... . . . . ... I8.8-1 (v)
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| Revision: 10 W85tilgh0US8 xxxi December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 18.8.1 Implementation Plan for the Human System Interface Design . . 18.8-3 18.8.2 Safety Parameter Display System (SPDS) . .... ... .. 18.8-11 18.8.3 Operation and Control Centers . .. .. . .... .. ..... 18.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Portion of the Plant . . ....... .. .... . .. .. . .. 18.8-20 18.8.5 Combined License Information . .. ... . . .. 18.8-23 18.8.6 References . . . . .. .... .. . ... . .. 18.8-23 18.9 Procedure Development . . . . .... .. . . . . . . . 18.9-1 18.9.1 Combined License Information . . . . ... . ... . ... . 18.9-1 18.9.2 References . . . . . . . . . . . . . . 18.9-1 18.10 Training Program Development .... . . . . . ... 18.10-1 18.10.1 Combined License Information . . . . ... . .. .. 18.10-1 18.10.2 References . . . . . .. . . . 18.10-1 18.11 Human System Interface Design Tes: Program ... . . . 18.11-1 18.11.1 Combined License Information . . .. ... . .. ... .. 18.11-2 18.11.2 References ...... ... . . ... . . . I8.11-2 18.12 Displays, Alarms, and Controls . . . . . . ... ...... . . . . .. .. I8.12-1 18.12.1 Inventory of Displays, Alarms, and Controls . . . ... 18.12-1 18.12.2 Minimum Inventory of Main Control Room Fixed Displays, Alarms, and Controls ... . .. ...... . . . .... 18.12-1 18.12.3 Remote Shutdown Workstation Displays, Alarms, and Controls ... 18.12-7 l 18.12.4 Combined License Information . . . .... . . . ... I8.12-7 1 18.12.5 References ..... . . ... ... ..... . ..... . . 18.12-8 l
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| O Revision: 10 December 20,1996 xxx [ Westiligh00S9
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| [ W85tinghouse 1 December 20,1996
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| List of Effective Pages APm List of Effective Pages Volume 1 Page Revision Page Revision Page Revision Page Revision 1.9-31 10 1.9-73 9 1.9-117 9 1.9-161 9 1.9-31 A 10 1.9-74 9 1.9-118 9 1.9-162 9 1.9-31 B 10 1.9-75 9 1.9-119 9 1.9-163 9 1.9-32 10 1.9-76 9 1.9-120 9 1.9-164 9 1.9-33 9 1.9-77 9 1.9-121 9 1.9-165 9 1.9-34 9 1.9-78 9 1.9-122 9 1.9-166 9 1.9-35 9 1.9-79 9 1.9-123 9 1.9-167 9 1.9-36 9 1.9-80 9 1.9-124 9 1.9-168 9 1.9-37 9 1.9-81 9 1.9-125 9 1.9-169 9 1.9-38 9 1.9-82 9 1.9-126 9 1.9-170 9 1.9-39 9 1.9-83 9 1.9-127 9 1.9-171 9 1.9-40 10 1.9-84 9 1.9- W 9 1.9-172 9 1.9-41 9 1.9-85 9 1.9-R < 9 1.9-173 9 1.9-42 9 1.9 86 9 1.9-130 9 1.9-174 9 1.9-43 9 1.9-87 9 1.9-131 9 1.9-175 9 1.9-44 9 1.9 88 9 1.9-132 9 1.9-176 9 1.9-45 9 1.9-89 9 1.9-133 9 1.9-177 9 1.9-46 9 1.9-90 9 1.9-134 9 1.9-178 9 1.9-47 9 1.9-91 9 1.9-135 10 1.9-179 9 4 1.9-48 9 1.9-92 9 1.9-136 9 1.9-180 9 1.9-49 9 1.9-93 9 1.9-137 9 1.9-181 9 1.9-50 9 1.9-94 9 1.9-138 9 1.9-182 9 j 1.9-51 9 1.9-95 9 1.9-139 9 1.9-183 9 :
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| 1.9-52 9 1.9-96 9 1.9-140 9 1.9-53 9 1.9-97 9 1.9-141 9 1 A-1 9 1.9-54 9 1.9-98 9 1.9-142 9 1A-2 9 l 1.9-55 9 1.9-99 9 1.9-143 9 1 A-3 9 l 1.9-56 9 1.9-100 9 1.9-144 9 1 A-4 9 1.9-57 9 1.9-101 9 1.9-145 9 1 A-5 9 1.9-58 9 1.9-102 9 1.9-146 9 1A-6 9 1.9-59 9 1.9-103 9 1.9-147 9 1 A-7 9 j 1.9-60 9 1.9-104 9 1.9-148 9 1 A-8 9 !
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| 1.9-66 9 1.9-110 9 1.9-154 9 1 A-14 9 1.9-67 9 1.9-111 9 1.9-155 9 1 A-15 9 1.9-68 9 1.9-112 9 1.9-156 9 1A-16 9 1.9-69 9 1.9-113 9 1.9-157 9 1A-17 9 l
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| 1.9-70 9 1.9-114 9 1.9-158 9 1 A-18 9 1 1.9-71 9 1.9-115 9 1.9-159 9 1 A-10 9 1.9-72 9 1.9-116 9 1.9-160 9 1A-20 9 Revision: 10 December 20,19% 2 [ WBStiflgt100Se
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| l List of Effective Pages f
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| (~N i AP600 List of Effective Pages Volume 1 Page Revision Page Revision Page Revision Page Revision lA-21 9 1A-62 9 2-v 10 2A-21 3 1A-22 9 1A-63 9 2-vi 10 2A-22 3 1A-23 9 1A-64 9 2-vii 10 2A-23 3 ,
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| 1 A-49 9 IB-9 1 2A-8 . 2A-51 3 l 1A-50 9 1B-10 1 2A-9 3 2A-52 3 1 A-51 9 1B-11 1 2A-10 3 2A-53 3 1 A-52 9 IB-12 1 2A-ll 3 2A-54 3 1A-53 9 1B-13 1 2A-12 3 2A-55 3 1 A-54 10 IB-14 1 2A-13 3 2A-56 3 IA-55 9 IB-15 1 2A-14 3 2A-57 3 i 1 A-56 9 IB-16 1 2A-15 3 2A-58 3 l 1A-57 9 2A-16 3 2A-59 3 l 1 A-58 9 2-i 10 ?A-17 3 2A-60 3 1 A-59 9 2-ii 10 2A-18 3 2A-61 3 i 1A-60 9 2-iii 10 2A-19 3 2A-62 3 g 1 A-61 9 2-iv 10 2A-20 3 2A-63 3 Revision: 10 3 W85tingt10USS 3 December 20,1996
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| : l. M List of Effective Pages AP600 List of Effective Pages Volume 1 Page Revision Page Revision Page Revision Page Revision 2A-64 3 2B-15 5 2B-59 3 2B-103 3 2A-65 3 2B-16 5 2B-60 3 2B-104 3 2A-66 3 2B-17 5 2B-61 3 2B-105 3 2A-67 3 2B-18 5 2B-62 3 2B-106 3 2A-68 3 2B-19 5 2B-63 3 2B-107 3 2A-69 3 2B-20 5 2B-64 3 2B-108 3 2A-70 3 2B-21 3 2B-65 3 2B-109 3 2A-71 3 2B-22 3 2B-66 3 2B-110 3 2A-72 3 2B-23 3 2B-67 3 2B-111 3 2A-73 3 2B-24 3 2B-68 3 2B-112 3 2A-74 3 2B-25 3 2B-69 3 2B-113 3 2A-75 3 2B-26 3 2B-70 3 2B-ll4 3 l 2A-76 3 2B-27 3 2B-71 3 2B-ll5 3 1 2A-77 3 2B-28 3 2B-72 3 2B-ll6 3 2A-78 3 2B-29 3 2B-73 3 2B-ll7 3 2A-79 3 2B-30 3 2B-74 3 2A-80 3 2B-31 3 2B-75 3 2A-81 3 2B-32 3 2B-76 3 2A-82 3 2B-33 3 2B-77 3 2A-83 3 2B-34 3 2B-78 3 4 2A-84 3 2B-35 3 2B-79 3 2A-85 3 2B-36 3 2B-80 3 2A-86 3 2B-37 3 2B-81 3 2A-87 3 2B-38 3 2B-82 3 2A-88 3 2B-39 3 2B-83 3 I 2A-89 3 2B-40 3 2B-84 3 2A-90 3 2B-41 3 2B-85 3 1 2B42 3 2B-86 3 I 2B-1 5 2B-43 3 2B-87 3 2B-2 5 2B-44 3 2B-88 3 2B-3 5 2B-45 3 2B-89 3 2B-4 5 2B-46 3 2B-90 3 2B-5 5 2B-47 3 2B-91 3 2B-6 5 2B-48 3 2B-92 3 1 2B-7 5 2B-49 3 2B-93 3 2B-8 5 2B-50 3 2B-94 3 2B-9 10 2B-51 3 2B-95 3 2B-9A 10 2B-52 3 2B-96 3 2B-9B 10 2B-53 3 2B-97 3 2B-10 5 2B-54 3 2B-98 3 2B-11 5 2B-55 3 2B-99 3 2B-12 5 2B-56 3 2B-100 3 2B-13 5 2B-57 3 2B-101 3 2B-14 5 2B-58 3 2B-102 3 Resision: 10 December 20,1996 4 W Westinghouse
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| 1 AP600 l List of Effective Pages Volume 2 Page Revision Page Revision Page Revision Page Revision 2C-1 5 3.1-3 7 3.2-9 8 3.2-53 10 2C-2 3 3.1-4 7 3.2-10 8 3.2-54 10 2C-3 5 3.1-5 7 3.2-11 8 3.2-55 10 2C-4 5 3.1-6 7 3.2-12 8 3.2-56 10 ,
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| [ W85tingh0Lise 5 December 20,1996
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| l AP600 List of Effective Pages Volume 2 Page Revision Page Revision Page Revision Page Revision 3.4 11 6 3.6-13 10 3.7-5 9 3.7-49 9 3.4-12 6 3.6-14 10 3.7-6 9 3.7-50 9 3.4-13 6 3.6-15 10 3.7-7 9 3.7-51 9 3.4-14 6 3.6-16 10 3.7-8 9 3.7-52 10 3.4-15 6 3.6-17 10 3.7-9 9 3.7-53 7 3.4-16 6 3.6-18 10 3.7-10 9 3.7-54 7 3.4-17 6 3.6-19 10 3.7-11 9 3.7-55 8 3.4-18 6 3.6-20 10 3.7-12 9 3.7-56 8 3.4-19 6 3.6-21 10 3.7-13 9 3.7-57 8 3.4-20 6 3.6-22 10 3.7-14 9 3.7-58 8 3.4-21 6 3.6-23 10 3.7-15 9 3.7-59 8 3.4-22 7 3.6-24 10 3.7-16 9 3.7-60 7 3.4-23 7 3.6-25 10 3.7-17 9 3.7-61 8 I 3.4-24 6 3.6-26 10 3.7-18 9 3.7-62 7 3.6-27 10 3.7-19 9 3.7-63 7 3.5-1 5 3.6-28 10 3.7-20 9 3.7-64 7 3.5-2 5 3.6-29 10 3.7-21 9 3.7-65 7 3.5-3 5 3.6-30 10 3.7-22 9 3.7-66 7 3.5-4 5 3.6-31 10 3.7-23 9 3.7-67 7 3.5-5 5 3.6-32 10 3.7-24 9 3.7-68 7 l 3.5-6 5 3.6-33 10 3.7-25 9 3.7-69 7 3.5-7 5 3.6-34 10 3.7-26 9 3.7-70 7 !
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| 3.5-8 5 3.6-35 10 3.7-27 9 3.7-71 7 l 3.5-9 5 3.6-36 10 3.7-28 9 3.7-72 7 l 3.5-10 5 3.6-37 10 3.7-29 9 3.7-73 7 I 3.5-11 5 3.6-38 10 3.7-30 9 3.7-74 7 3.5-12 5 3.6-39 10 3.7-31 9 3.7-75 7 3.5-13 5 3.6-40 10 3.7-32 9 3.7-76 7 1 3.5-14 5 3.6-41 10 3.7-33 9 3.7-77 7 3.5-15 5 3.6-42 10 3.7-34 9 3.7-78 7 3.5-16 5 3.6-43 10 3.7-35 9 3.7-79 7 3.6-44 10 3.7-36 9 3.7-80 7 1 3.6-1 7 3.6-45 10 3.7-37 9 3.7-81 7 l 3.6-2 7 3.6-46 10 3.7-38 9 3.7-82 7 l
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| 3.6-3 7 3.6-47 10 3.7-39 9 3.7-83 7 3.6-4 7 3.6-48 10 3.7-40 9 3.7-84 7 3.6-5 7 3.6-49 10 3.7-41 9 3.7-85 7 3.6-6 7 3.6-50 10 3.7-42 9 3.7-86 7 3.6-7 10 3.6-51 10 3.7-43 9 3.7-87 7 3.6-8 10 3.7-44 10 3.7-88 7 3.6-9 10 3.7-1 10 3.7-45 10 3.7-89 7 3.6-10 10 3.7-2 9 3.7-46 9 3.7-90 7 ,
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| 3.6-11 10 3.7-3 9 3.7-47 9 3.7-91 7 3.6-12 10 3.7-4 9 3.7-48 9 3.7-92 7 9
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| Revision: 10 Deceml>er 20,19% 6 [ Westingh0USB
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| I List of Effective Pages 1
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| AP600 List of Effective Pages Volume 2 Page Revision Page Revision Page Revision Page Revision 3.7-93 9 3.7-137 2 3.7-185 7 3.8-4 7 !
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| 3.7-94 9 3.7-138 9 3.7-187 7 3.8-5 7 i 3.7-95 9 3.7-139 9 3.7-189 7 3.8-6 7 l 3.7-96 .9 3.7-140 7 3.7-191 7 3.8-7 7 3.7-97 9 3.7-141 9 3.7-193 7 3.8-8 7 3.7-98 9 3.7-142 9 3.7-195 7 3.8-9 7 3.7-99 l
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| 7 3.7-143 2 3.7-197 7 3.8-10 7 3.7-100 7 3.7-144 2 3.7-199 7 3.8-11 7 l 3.7-101 9 3.7-145 7 3.7-201 9 3.8-12 7 3.7-102 9 3.7-146 7 3.7-202 9 3.8-13 7 3.7-103 9 3.7 147 7 3.7-203 9 3.8-14 7 3.7-104 9 3.7-148 7 3.7-204 7 3.8-15 7 3.7-105 9 3.7-149 7 3.7-205 7 3.8-16 7 I 3.7-106 9 3.7-150 7 3.7-2% 7 3.8-17 7 I 3.7-107 9 3.7-151 7 3.7-207 7 3.8-18 7 3.7-108 9 3.7-152 7 3.7-208 7 3.8-19 7 !
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| 3.7-121 7 3.7-165 7 3.7 221 7 3.8-32 7 3.7-122 2 3.7-166 7 3.7-222 7 3.8-33 7 3.7-123 2 3.7 167 7 3.7-223 7 3.8-34 7 3.7-124 2 3.7-168 7 3.7-224 7 3.8-35 7 3.7-125 2 3.7-169 7 3.7-225 7 3.8-36 7 3.7-126 2 3.7-170 7 3.7-226 7 3.8-37 7 i 3.7-127 2 3.7-171 7 3.7-227 7 3.8-38 7 3.7-128 2 3.7-172 7 3.7 228 7 3.8-39 7 3.7-129 2 3.7-173 7 3.7-229 9 3.8-40 7 3.7-130 2 3.7-174 7 3.7-230 9 3.8-41 7 3.7-131 7 3.7-175 7 3.7-231 2 3.8-42 7 3.7-132 7 3.7-176 7 3.7-232 7 3.8-43 7 3.7-133 7 3.7-177 9 3.8-44 7 3.7-134 2 3.7-179 7 3.8-1 7 3.8-45 7 3.7-135 2 3.7-181 7 3.8-2 7 3.8-46 7
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| List of Effective Pages AP600 List of Effective Pages Volume 2 Page Revision Page Revision Page Revision Page Revision l 3.8-48 7 3.8-97 7 3.8-158 7 3.8-49 7 3.8-98 7 3.8-159 7 3.8-50 7 3.8-99 7 3.8-161 7 i 3.8-51 7 3.8-100 7 3.8-163 7 3.8-52 7 3.8-101 7 3.8-164 7 3.8-53 7 3.8-102 7 3.8-165 7 3.8-54 7 3.8-103 7 3.8-166 7 3.8-55 7 3.8-104 7 3.8-167 7 3.8-56 7' 3.8-105 7 3.8-168 7 3.8-57 7 3.8-106 7 3.8-169 7 3.8-58 7 3.8-107 7 3.8-170 7 3.8-59 7 3.8-109 7 3.8-171 7 3.8-60 7 3.8-111 7 3.8-172 7 3.8< 61 7 3.8-113 7 3.8-173 7 3.8-62 7 3.8-115 7 3.8-175 7 3.8-63 7 3.8-116 7 3.8-176 7 3.8-64 7 3.8-117 7 3.8-177 7 3.8-65 7 3.8-118 7 3.8-178 7 3.8-66 7 3.8-119 7 3.8-179 7 3.8-67 7 3.8-121 7 3.8-181 7 ,
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| \ O Revision: 10 December 20,1996 8 [ WB5tirighouse
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| Page Revision Page Revision Page Revision 3.9-1 5 3.9-45 9 3.9-89 8 3.9-131 10 3.9-2 5 3.9-46 9 3.9-90 10 3.9-133 10 3.9-3 5 3.9-47 9 3.9-91 10 3.9-135 10 3.9-4 .5 3.9-48 9 3.9-92 10 3.9-137 10 ,
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| 3.9-30 5 3.9-74 8 3.9-118 9 3.10-1 8 3.9-31 5 3.9-75 8 3.9-119 9 3.10-2 5 3.9-32 5 3.9-76 8 3.9-120 10 3.10-3 8 3.9-33 5 3.9-77 8 3.9-120A 10 3.10-4 8 3.9-34 10 3.9-78 8 3.9-120B 10 3.10-5 10 3.9-35 5 3.9-79 8 3.9-121 10 3.10-6 10 3.9-36 5 3.9-80 10 3.9-122 10 3.10-7 7 i 3.9-37 5 3.9-81 10 3.9-123 10 3.10-8 10 3.9-38 5 3.9-82 8 3.9-124 10 3.9-39 5 3.9-83 8 3.9-125 8 3.11-1 8 3.9-40 5 3.9-84 8 3.9-126 8 3.11-2 8 3.9-41 5 3.9-85 8 3.9-127 8 3.I1-3 8 3.9-42 5 3.9-86 8 3.9-128 8 3.11-4 8 3.9-43 5 3.9-87 8 3.9-129 8 3.11-5 8
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| ,^ 3.9-44 5 3.9-88 8 3.9-130 8 3.11-6 8 Revision: 10 W Westinghouse 9 December 20,1996 l
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| List of Effective Pcges AP600 List of Effective Pages Volume 3 Page Revision Page Revision Page Revision Page Revision 3.11-7 8 3A-1 7 3B-38 7 3D-13 5 3.11-8 8 3A-2 7 3B-39 7 3D-14 5 3.11-9 8 3A-3 7 3B-40 7 3D-15 5 3.11-10 10 3A-4 7 3B-41 7 3D-16 5 3.11-11 10 3B-42 7 3D-17 5 3.11-12 10 3B-1 10 3B-43 7 3D-18 5 3.11-13 8 3B-2 10 3B-44 7 3D-19 5 3.11-14 8 3B-3 10 3B-45 7 3D-20 5 3.11-15 8 3B-4 10 3B-46 7 3D-21 5 3.11-16 10 3B-5 10 3B-47 7 3D-22 5 3.11-17 8 3B-6 10 3B-48 7 3D-23 8 3.11-18 8 3B-7 10 3B-49 7 3D-24 8 3.11-19 8 3B-8 10 3B-50 7 3D-25 5 3.11-20 8 3B-9 10 3B-51 7 3D-26 5 3.11-21 8 3B-10 10 3B-52 7 3D-27 5 3.11-22 10 ' 3B-11 10 3B-53 7 3D-28 5 3.11-23 10 3B-12 10 3B-54 7 3D-29 5 3.11-23A 10 3B-13 10 3B-55 7 3D-30 5 3.11-23B 10 3B-14 10 3B-56 7 3D-31 5 3.11-24 8 3B-15 10 3B-57 7 3D-32 5 3.11-25 8 3B-16 10 3B-58 7 3D-33 5 3.11-26 8 3B-17 10 3B-59 7 3D-34 5 3.11-27 8 3B-18 10 3B-60 7 3D-35 5 +
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| 3.11-28 8 3B-19 10 3B-61 7 3D-36 5 3.11-29 8 3B-20 10 3B-62 7 3D-37 5 3.11-30 8 3B-21 10 3D-38 5 3.11-31 8 3B-21A 10 3C-1 5 3D-39 5 3.11-32 8 3B-21B 10 3C-2 5 3D-40 5 3.11-33 8 3B-22 10 3C-3 5 3D-41 5 3.11-34 8 3B-23 10 3C-4 5 3D-42 5 3.11-35 8 3B-24 10 3C-5 5 3D-43 8 3.11-36 8 3B-25 7 3D-44 8 3.11-37 8 3B-26 7 3D-1 5 3D-45 8 3.11-38 8 3B-27 7 3D-2 8 3D-46 8 3.11-39 8 3B-28 7 3D-3 5 3D-47 8 3.11-40 8 3B-29 7 3D-4 5 3D-48 8 3.11-41 8 3B-30 7 3D-5 5 3D-49 8 3.11-42 8 3B-31 7 3D-6 5 3D-50 8 3.11-43 8 3B-32 7 3D-7 5 3D-51 5 3.11-44 8 3B-33 7 3D-8 8 3D-52 5 ;
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| 3.11-45 8 3B-34 7 3D-9 8 3D-53 5 l 3.11-46 8 3B-35 7 3D-10 5 3D-54 5 l 3.11-47 8 3B-36 7 3D-11 5 3D-55 5 3.11-48 8 3B-37 7 3D-12 5 3D-56 5 Revision: 10 l December 20,1996 10 W Westirighouse 1
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| V' AP600 List of Effective Pages Volume 3 Page Revision Page Revision Page Revision Page Revision 3D-57 5 3D-101 5 4-ii 10 4.2-27 3 3D-58 5 3D-102 0 4-iii 10 4.2-28 3 3D-59 5 3D-103 5 4-iv 10 4.2-29 3 3D-60 5 3D-lG4 5 4-v 10 4.2-30 3 3D-61 5 3D-105 5 4-vi 10 4.2-31 3 3D-62 0 3D-106 5 4-vii 10 4.2-32 3 3D-63 0 3D-107 5 4.2-33 3 3D-64 0 3D-108 5 4.1-1 3 4.2-34 3 3D-65 0 3D-109 5 4.1-2 3 4.2-35 3 3D-66 0 3D-110 5 4.1-3 3 4.2-36 3 3D-67 0 3D-111 5 4.1-4 3 4.2-37 3 3D-68 0 3D-112 0 4.1-5 3 4.2-38 3 3D-69 5 3D-113 0 4.1-6 3 4.2-39 3 3D-70 5 3D-114 0 4.1-7 3 4.2-40 3 3D-71 5 3D-115 5 4.1-8 3 4.2-41 3 3D-72 5 3D-116 5 4.1-9 3 4.2-42 3 3D-73 5 3D-Il7 5 4.1-10 3 4.2-43 3 3D-74 5 3D-115 5 4.2-44 3 3D-75 5 3D-119 5 4.2-1 3 4.2-45 6
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| /_'') 3D-76 5 3D-120 5 4.2-2 3 4.2-46 3 V 3D-77 5 3D-121 5 4.2-3 3 4.2-47 3 3D-78 5 3D-122 5 4.2-4 3 4.2-48 3 3D-79 5 3D-123 5 4.2-5 3 4.2-49 3 3D-80 5 3D-124 5 4.2-6 3 4.2-50 3 3D-81 5 3D-125 5 4.2-7 3 4.2-51 3 3D-82 5 3D-126 5 4.2-8 3 4.2-52 3 3D-83 5 4.2-9 3 4.2-53 3 3D-84 5 3E-1 7 4.2-10 3 4.2-54 3 3D-85 5 3E-2 7 4.2-11 3 4.2-55 3 3D-86 5 3E-3 7 4.2-12 3 3D-87 5 3E-5 7 4.2-13 3 4.3-1 3 3D-88 5 3E-7 7 4.2-14 3 4.3-2 3 3D-89 5 3E-9 7 4.2-15 3 4.3-3 3 3D-90 5 3E-11 7 4.2-16 3 4.3-4 3 3D-91 5 3E-13 7 4.2-17 3 4.3-5 3 3D-92 5 3E-15 7 4.2-18 3 4.3-6 3 3D-93 5 3E-17 7 4.2-19 3 4.3-7 3
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| ; 3D-94 5 3E-19 7 4.2-20 3 4.3-8 3 3D-95 5 4.2-21 3 4.3-9 3 l 3D-96 5 3F-1 7 4.2-22 3 4.3-10 3 l 3D-97 5 3F-2 7 4.2-23 3 4.3-11 3 3D-98 5 3F-3 7 4.2-24 3 4.3-12 3 3D-99 5 4.2-25 3 4.3-13 3
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| ,3 3D-100 5 4-i 10 4.2-26 3 4.3-14 3 Revision: 10
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| [ W85tiflgh0USe 11 December 20,1996
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| AP600 List of Effective Pages Volume 3 Page Revision Page Revision Page Revision Page Revision l
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| 4.3-15 3 4.3-59 3 4.4-10 3 4.6-2 3 4.3-16 8 4.3-60 3 4.4-11 3 4.6-3 3 4.3-17 8 4.3-61 3 4.4-12 3 4.6-4 3 4.3-18 8 4.3-62 3 4.4-13 3 4.3-19 8 4.3-63 3 4.4-14 3 4.3-20 8 4.3-64 3 4.4-15 3 4.3-21 8 4.3-65 3 4.4-16 3 4.3-22 8 4.3-66 3 4.4-17 3 4.3-23 8 4.3-67 3 4.4-18 3 4.3-24 8 4.3-68 3 4.4-19 3 l 4.3-25 8 4.3-69 3 4.4-20 3 4.3-26 8 4.3-70 3 4.4-21 3 4.3-27 8 4.3-71 3 4.4-22 3 4.3-28 8 4.3-72 3 4.4-23 3 4.3-29 8 4.3-73 3 4.4-24 3 4.3-30 8 4.3-74 8 4.4-25 3 4.3-31 8 4.3-75 8 4.4-26 3 4.3-32 8 4.3-76 8 4.4-27 3 l 4.3-33 8 4.3-77 8 4.4-28 3 !
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| 4.3-37 8 4.3-81 8 4.4-32 10 4.3-38 8 4.3-82 8 4.4-33 10 4.3-39 8 4.3-83 8 4.4-34 5 4.3-40 8 4.3-84 8 4.4-35 3 4.3-41 3 4.3-85 8 4.4-36 3 4.3-42 3 4.3-86 8 4.4-37 3 4.3-43 3 4.3-87 8 4.4-38 3 4.3-44 3 4.3-88 8 4.4-39 3 4.3-45 3 4.3-89 8 4.4 40 3 4.3-46 3 4.3-90 8 4.4-41 3 4.3-47 3 4.3-91 8 4.4-42 3 4.3-48 3 4.3-92 8 4.4-43 3 4.3-49 3 4.4-44 3 4.3-50 3 4.4-1 3 4.4-45 3 4.3-51 3 4.4-2 5 4.4-46 3 4.3-52 3 4.4-3 3 4.3-53 3 4.4-4 10 4.5-1 5 4.3-54 3 4.4 5 5 4.5-2 5 4.3-55 3 4.4-6 3 4.5-3 5 4.3-56 3 4.4-7 3 4.5-4 5 4.3-57 3 4.4-8 3 4.3-58 3 4.4 9 3 4.6-1 3 Revision: 10 December 20,1996 12 3 W85tingh0US8 1
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| [l E AP600 List of Effective Pages Volume 4 Page Revision Page Revision Pa;;e Revision Page Revision 5-i 10 5.2-16 5 5.3-22 5 5.4-33 5 5-ii 10 5.2-17 5 5.3-23 5 5.4-34 5 5-iii 10 5.2-18 5 5.3-24 5 5.4-35 5 5-iv 10 5.2-19 5 5.3-25 5 5.4-36 5 5-v 10 5.2-20 5 5.3-26 5 5.4-37 5 5-vi 10 5.2-21 10 5.3-27 3 5.4-38 5 5-vii 10 5.2-22 10 5.3-28 5 5.4-39 5 5.2 23 5 5.3-29 5 5.4-40 5 5.1-1 5 5.2-24 5 5.3-30 3 5.4-41 5 5.1-2 5 5.2-25 5 5.3-31 3 5.4-42 5 5.1-3 5 5.2-26 7 5.3-32 3 5.4-43 5 5.1-4 5 5.2-27 7 5.4-44 5 5.1-5 5 5.2-28 10 5.4-1 5 5.4-45 5 5.1-6 5 5.2-29 5 5.4-2 10 5.4-46 5 5.1-7 5 5.2-30 5 5.4-3 5 5.4-47 5 5.1-8 5 5.2-31 5 5.4-4 5 5.4-48 5 5.1-9 5 5.2-32 5 5.4-5 5 5.4-49 5 5.1-10 5 5.2-33 5 5.4-6 5 5.4-50 5 5.1-11 5 5.2-34 5 5.4-7 5 5.4-51 5 5.1-12 5.2-35
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| I List of Effective Pages AP600 G, List of Effective Pages Volume 5 Page Revision Page Revision Page Revision Page Revision 8-i 10 8.3-26 8 9-xi 10 9.1 42 7 8-ii 10 8.3-27 8 10-xii 10 9.1-43 7 8-iii 10 8.3-28 8 9.ld4 7 8.3-29 8 9.1-1 7 9.1-45 7 8.1-1 3 8.3-30 8 9.1-2 8 9.1-46 7 8.1-2 3 8.3-31 8 9.1-3 7 9.1-47 7 8.1-3 3 8.3-32 8 9.1-4 7 9.1-48 7 8.1-4 3 8.3-33 8 9.1-5 7 9.1-49 7 8.1-5 3 8.3-34 8 9.1-6 7 9.1-50 7 8.1-6 3 8.3-35 8 9.1-7 7 9.1-51 7 8.1-7 3 8.3-36 8 9.1-8 7 9.1-52 5 8.1-8 3 8.3-37 10 9.1-9 7 9.1-53 5 8.1-9 3 8.3-38 10 9.1-10 7 9.1-54 5 8.1-10 3 8.3-39 10 9.1-11 7 9.1-55 7 8.3-40 8 9.1-12 7 9.1-56 5 8.2-1 7 8.3-41 8 9.1-13 7 9.1-57 7 l 8.2-2 7 8.3-42 8 9.114 7 9.1-58 5 8.2-3 7 8.3-43 8 9.1-15 7 9.1-59 7 8.3-44 8 9.1-16 7 9.1-61 7 8.3-1 8 8.3-45 8 9.1-17 7 i 8.3-2 8 8.3-46 8 9.1-18 7 9.2-1 6 '
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| o V AP600 List of Effective Pages Volume 6 Page Revision Page Revision Page Revision Page Revision 9.5-73 7 9A-42 8 9A-86 8 9A-130 8 9.5-75 7 9A-43 8 9A-87 8 9A-131 8 9A-44 8 9A-88 8 9A-132 8 9A-1 8 9A-45 8 9A-89 8 9A-133 8 9A-2 8 9A-46 8 9A-90 8 9A-134 8 9A-3 8 9A-47 8 9A-91 8 9A-135 8 9A-4 8 9A-48 8 9A-92 8 9A-136 8 9A-5 8 9A-49 8 9A-93 8 9A-137 8 9A-6 8 9A-50 8 9A-94 8 9A-138 8 9A-7 8 9A-51 8 9A-95 8 9A-139 8 9A-8 8 9A-52 8 9A-96 8 9A 140 8 9A-9 8 9A-53 8 9A-97 8 9A-141 8 i 9A-10 8 9A-54 8 9A-98 8 9A-143 8 )
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| AP600 List of Effective Pages Volume 7 Page Revision Page Revision Page Revision Page Revision 11.1-15 9 11.2-41 8 11.4-13 8 11.5-22 6 11.1-16 9 11.2-42 8 11.4-14 9 11.5-23 6 11.1-17 9 11.2-43 6 11.4-15 8 11.5-24 6 11.2-45 10 11.4-16 8 11.5-25 6 11.2-1 8 11.2-47 8 11.4-17 8 11.5-26 6 11.2-2 8 11.2.49 8 11.4-18 8 11.5-27 6 11.2-3 8 11.2.51 8 11.4-19 8 11.5-28 6 11.2-4 9 11.2.53 8 11.4-20 8 11.5-29 6 11.2-5 9 11.2.55 8 11.4-21 8 11.2-6 8 11.4-22 8 12-i 9 11.2-7 8 11.3-1 8 11.4-23 8 12-ii 9 1 11.2-8 8 11.3-2 8 11.4-24 8 12-iii 9 l 11.2-9 8 11.3-3 9 11.4-25 8 12-iv 9 11.2-10 8 11.3-4 8 11.4-26 8 12-v 9 ,
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| Resision: 10 3 W95tiligt100Se 23 December 20,1996
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| List of Effective Pcges AP600 List of Effective Pages Volume 7 Page Revision Page Revision Page Revision Page Revision 12.2-21 7 12.3-13 7 12.3-86 7 12.2-22 3 12.3-14 7 12.3-87 7 12.2-23 3 12.3-15 7 12.3-89 7 12.2-24 7 12.3-16 7 12.3-91 7 i 12.2-25 3 12.3-17 7 12.3-93 7 12.2-26 3 12.3-18 7 12.3-95 7 12.2-27 3 12.3-19 7 12.3-97 7 12.2-28 7 12.3-20 7 12.3-99 7 12.2-29 7 12.3-21 7 12.3-101 7 12.2-30 3 12.3-22 7 12.3-103 7 i 12.2-31 7 12.3-23 7 12.3-105 7 ;
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| List of Effective Pcges AP600 List of Effective Pages Volume 9 Page Revision Page Revision Page Revision Page Revision 15.5-1 5 15.6-18 5 15.6-62 5 15.6-106 5 15.5-2 5 15.6-19 5 15.6-63 5 15.6-107 5 15.5-3 5 15.6-20 5 M.6-64 5 15.6-108 5 15.5-4 5 15.6-21 5 15.6-65 5 15.6-109 5 15.5-5 5 15.6-22 5 15.6-66 5 15.6-110 5 15.5-6 5 15.6-23 5 15.6-67 5 15.6-111 5 15.5-7 5 15.6-24 5 15.6-68 5 15.6-112 5 15.5-8 5 15.6-25 5 15.6-69 5 15.6-113 5 15.5-9 5 15.6-26 5 15.6-70 5 15.6-114 5 15.5-10 5 15.6-27 5 15.6-71 5 15.6-115 5 15.5-11 5 15.6-28 5 15.6-72 5 15.6-116 5 15.5-12 5 15.6-29 5 15.6-73 5 15.6-117 5 15.5-13 5 15.6-30 5 15.6-74 5 15.6-118 5 15.5-14 5 15.6-31 5 15.6-75 5 15.6-119 5 15.5-15 5 15.6-32 5 15.6-76 5 15.6-120 5 15.5-16 5 15.6-33 5 15.6-77 5 15.6-121 5 15.5-17 5 15.6-34 5 15.6-78 5 15.6-122 5 15.5-18 5 15.6-35 5 15.6-79 5 15.6-123 5 15.5-19 5 15.6-36 5 15.6-80 5 15.6-124 5 15.5-20 5 15.6-37 5 15.6-81 5 15.6-125 5 15.5-21 5 15.6-38 5 15.6-82 5 15.6-126 5 i 15.5-22 5 15.6-39 5 15.6-83 5 15.6-127 5 l 15.5-23 5 15.6-40 5 15.6-84 5 15.6-128 5 i 15.5-24 5 15.6-41 5 15.6-85 5 15.6-129 5 15.5-25 5 15.6-42 5 15.6-86 5 15.6-130 5 15.5-26 5 15.6-43 5 15.6-87 5 15.6-131 5 ,
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| 15.6-44 5 15.6-88 5 15.6-132 5 15.6-1 5 15.6-45 5 15.6-89 5 15.6-133 5 15.6-2 5 15.6-46 5 15.6-90 5 15.6-134 5 l 15.6-3 5 15.6-47 5 15.6-91 5 15.6-135 5 15.6-4 5 15.6-48 5 15.6-92 5 15.6-136 5 15.6-5 5 15.6-49 5 15.6-93 5 15.6-137 5 15.6-6 5 15.6-50 5 15.6-94 5 15.6-138 5 15.6-7 5 15.6-51 5 15.6-95 5 15.6-139 5 15.6-8 5 15.6-52 5 15.6-96 5 15.6-140 5 15.6-9 5 15.6-53 5 15.6-97 5 15.6-141 5 15.6-10 5 15.6-54 5 15.6-98 5 15.6-142 5 15.6-11 5 15.6-55 5 15.6-99 5 15.6 143 5 15.6-12 5 15.6-56 5 15.6-100 5 15.6-144 5 15.6-13 5 15.6-57 5 15.6-101 5 15.6-145 5 15.6-14 5 15.6-58 5 15.6-102 5 15.6-146 5 15.6-15 5 15.6-59 5 15.6-103 5 15.6-147 5 15.6-16 5 15.6-60 5 15.6-104 5 15.6-148 5 15.6-17 5 15.6-61 5 15.6-105 5 15.6-149 5 O
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| Resision: 10 December 20,1996 28 3 W85tingh0USB
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| _, AP600 List of Effective Pages Volume 9 Page Revision Page Revision Page Revision Page Revision i 15.6-150 5 15.6-194 5 15.8-1 9 15.6-151 5 15.6-195 l
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| 15.6-152 5 15.6-196 5 15A-1 7 l 15.6-153 5 15.6-197 5 15A-2 7 15.6-154 5 15.6-198 5 15A-3 7 15.6-155 5 15.6-199 5 15A-4 7 15.6-156 5 15.6-200 5 15A-5 7 15.6-157 5 15.6-201 5 15A-6 7 15.6-158 5 15.6-202 5 15A-7 7 15.6-159 5 15.6-203 5 15A-8 7 15.6-160 5 15.6-204 5 15A-9 7 15.6-161 5 15.6-205 5 15A-10 7 15.6-162 5 15.6-206 5 15A-ll 7 j 15.6-163 5 15.6-207 5 15A-12 7 l 15.6-164 5 15.6-208 5 15A-13 7 15.6-165 5 15.6-209 5 15A-14 7 15.6-166 5 15.6-210 5 15A-15 7 15.6-167 5 15.6-211 5 15A-16 7 15.6-168 5 15.6-212 5 !
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| \ 15.6-170 5 15.6-214 5 15.6-171 5 15.6-215 5 15.6-172 5 15.6-216 5 15.6-173 5 15.6-217 5 I 15.6-174 5 15.6-218 5 15.6-175 5 15.6-219 5 l 15.6-176 5 15.6-220 5 15.6-177 5 15.6-221 5 15.6-178 5 15.6-222 5 15.6-179 5 15.6-223 5 15.6-180 5 15.6-224 5 15.6-181 5 15.6-225 5 15.6-182 5 15.6-226 5 15.6-183 5 15.6-227 5 15.6-184 5 15.6-185 5 15.7-1 9 15.6-186 5 15.7-2 9 15.6-I87 5 15.7-3 9 15.6-188 5 15.7-4 9 15.6-189 5 15.7-5 9 15.6-190 5 15.7-6 9 15.6-191 5 15.7-7 9 15.6-192 5 15.7-8 5
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| List of Effective Pcges AP&,0 List of Effective Pages l Volume 10 l Page Revision Page Revision Page Revision Page Revision 1 16-i 10 1.4-4 9 3.3-1 9 3.3-45 9 16-ii 10 2.0-1 9 3.3-2 9 3.3-46 9 16-iii 10 2.0-2 9 3.3-3 9 3.3-47 9 16-iv 10 3.0-1 9 3.3-4 9 3.3-48 9 16-v 10 3.0-2 9 3.3-5 9 3.3-49 9 16-vi 10 3.0-3 9 3.3-6 9 3.4-1 9 16-vii 10 3.0-4 9 3.3-7 9 3.4-2 9 16-viii 10 3.0-5 9 3.3-8 9 3.4-3 9 1
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| 16-ix 10 3.1-1 9 3.3-9 9 3.4-4 9 3.1-2 9 3.3-10 9 3.4-5 9 i 9 3.1-3 9 3.3-11 9 3.4-6 9 ii 9 3.1-4 9 3.3-12 9 ''4-7 9 iii 9 3.1-5 9 3.3-13 9 3.4-8 9 iv 9 3.1-6 9 3.3-14 9 3.4-9 9 v 9 3.1-7 9 3.3-15 9 3.4-10 9 vi 9 3.1-8 9 3.3-16 9 3.4-11 9 vii 9 3.1-9 9 3.3-17 9 3.4-12 9 16.1-1 9 3.1-10 9 3.3-18 9 3.4-13 9 16.1-2 9 3.1-11 9 3.3-19 9 3.4-14 9 :
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| 1.1-1 9 3.1-12 9 3.3-20 9 3.4-15 9 1.1-2 9 3.1-13 9 3.3-21 9 3.4-16 9 l.1-3 9 3.1-14 9 3.3-22 9 3.4-17 9 1.1-4 9 3.1-15 9 3.3-23 9 3.4-18 9 1.1-5 9 3.1-16 9 3.3-24 9 3.4-19 9 1.1-6 9 3.1-17 9 3.3-25 9 3.4-20 9 1.1-7 9 3.1-18 9 3.3-26 9 3.4-21 9 l 1.2-1 9 3.1-19 9 3.3-27 9 3.4-22 9 1.2-2
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| 1.3-5 9 3.2-5 9 3.3-34 9 3.5-1 9 l.3-6 9 3.2-6 9 3.3-35 9 3.5-2 9 1.3-7 9 3.2-7 9 3.3-36 9 3.5-3 9 I 1.3-8 9 3.2-8 9 3.3-37 9 3.5-4 9 1.3-9 9 3.2-9 9 3.3-38 9 3.5-5 9 1.3-10 9 3.2-10 9 3.3-39 9 3.5-6 9 1.3-11 9 3.2-11 9 3.3-40 9 3.5-7 9 1.3-12 9 3.2-12 9 3.3-41 9 3.5-8 9 1.4-1 9 3.2-13 9 3.3-42 9 3.5-9 9 1.4-2 9 3.2-14 9 3.3-43 9 3.5-10 9 l 1.4-3 9 3.2-15 9 3.3-44 9 3.5-11 9 O
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| List of Effective Pages C AP600 List of Effective Pages Volume 10 Page Revision Page Revision Page Revision Page Revision 3.5-12 9 3.7-13 9 5.0-14 9 B 3.1-12 9 3.5-13 9 3.7-14 9 5.0-15 9 B 3.1-13 9 3.5-14 9 3.7-15 9 5.0-16 9 B 3.1-14 9 3.5-15 9 3.7-16 9 5.0-17 9 B 3.1-15 9 3.5-16 9 3.8-1 9 5.0-18 9 B 3.1-16 9 3.5-17 9 3.8-2 9 5.0-19 9 B 3.1-17 9 3.5-18 9 3.8-3 9 5.0-20 9 B 3.1-18 9 3.5-19 9 3.8-4 9 B 2.0-1 9 B 3.1-19 9 3.5-20 9 3.8-5 9 B 2.0-2 9 B 3.1-20 9 3.6-1 9 3.8-6 9 B 2.0-3 9 B 3.1-21 9 3.6-2 9 3.8-7 9 B 2.0-4 9 B 3.1-22 9 3.6-3 9 3.8-8 9 B 2.0-5 9 B 3.1-23 9 3.6-4 9 3.8-9 9 B 2.0-6 9 B 3.1-24 9 3.6-5 9 3.8-10 9 B 2.0-7 9 B 3.1-25 9 3.6-6 9 3.8-11 9 B 2.0-8 9 B 3.1-26 9 3.6-7 9 3.8-12 9 B 2.0-9 9 B 3.1-27 9 3.6-8 9 3.8-13 9 B 2.0-10 9 B 3.1-28 9 3.6-9 9 3.8-14 9 B 3.0-1 9 B 3.1-29 9 3.6-10 9 3.8-15 9 B 3.0-2 9 B 3.130 9
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| U 3.6-11 3.6-12 9 3.8-16 3.8-17 9 B 3.0-3 9 B 3.1-31 9 9 9 B 3.0-5 9 B 3.1-32 9 3.6-13 9 3.8-18 9 B 3.0-6 9 B 3.1-33 9 3.6-14 9 3.9-1 9 B 3.0-7 9 B 3.1-34 9 3.6-15 9 3.9-2 9 B 3.0-8 9 B 3.1-35 9 3.6-16 9 3.9-3 9 B 3.0-9 9 B 3.1-36 9 3.6-17 9 3.9-4 9 B 3.0-10 9 B 3.1-37 9 3.6-18 9 3.9-5 9 B 3.0-11 9 B 3.1-38 9 3.6-19 9 3.9-6 9 B 3.0-12 9 B 3.1-39 9 3.6-20 9 4.0-1 9 B 3.0-13 9 B 3.1-40 9 3.6-21 9 4.0-2 9 B 3.0-14 9 B 3.1-41 9 3.6-22 9 4.0-3 9 B 3.0-15 9 B 7,.1-42 9 3.6-23 9 5.0-1 9 B 3.0-16 9 B 3.1-43 9 3.7-1 9 5.0-2 9 B 3.0-17 9 5 3.1-44 9 3.7-2 9 5.0-3 9 B 3.1-1 9 B 3.1-45 9 3.7-3 9 5.0-4 9 B 3.1-2 9 B 3.1-46 9 3.7-4 9 5.0-5 9 B 3.1-3 9 B 3.1-47 9 3.7-5 9 5.0-6 9 B 3.1-4 9 B 3.1-48 9 3.7-6 9 5.0-7 9 B 3.1-5 9 B 3.1-49 9 3.7-7 9 5.0-8 9 B 3.1-6 9 B 3.1-50 9 l 3.7-8 9 5.0-9 9 B 3.1-7 9 B 3.1-51 9 i 3.7-9 9 5.0-10 9 B 3.1-8 9 B 3.1-52 9 3.7-10 9 5.0-11 9 B 3.1-9 9 B 3.1-53 9 3.7-11 9 5.0-12 9 B 3.1-10 9 B 3.1-54 9 n 3.7-12 9 5.0-13 9 B 3.1-11 9 B 3.1-55 9
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| ! Revision: 10 W Westinghouse 31 December 20,1996 i
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| List of Effective Pages AP600 List of Effective Pages i Volume 10 Page Revision .Page Revision Page Revision Pag,e Revision B 3.2-1 9 B 3.3-13 9 B 3.3-57 9 B 3.3-101 9 B 3.2-2 9 B 3.3-14 9 B 3.3-58 9 B 3.3-102 9 B 3.2-3 9 B 3.3-15 9 B 3.3-59 9 B 3.3-103 9 B 3.2-4 9 B 3.3-16 9 B 3.3-60 9 B 3.3-104 9 B 3.2-5 9 B 3.3-17 9 B 3.3-61 9 B 3.3-105 9 B 3.2-6 9 B 3.3-18 9 B 3.3-62 9 B 3.3-106 9 B 3.2-7 9 B 3.3-19 9 B 3.3-63 9 B 3.3-107 9 B 3.2-8 9 B 3.3-20 9 B 3.3-64 9 B 3.3-108 9 B 3.2-9 9 B 3.3-21 9 B 3.3-65 9 B 3.3-109 9 B 3.2-10 9 B 3.3-22 9 B 3.3-66 9 B 3.3-110 9 B 3.2-11 9 B 3.3-23 9 B 3.3-67 9 B 3.3-111 9 B 3.2-12 9 B 3.3-24 9 B 3.3-68 9 B 3.3-112 9 B 3.2-13 9 B 3.3-25 9 B 3.3-69 9 B 3.3-113 9 B 3.2-14 9 B 3.3-26 9 B 3.3-70 9 B 3.3-114 9 B 3.2-15 9 B 3.3-27 9 B 3.3-71 9 B 3.3-115 9 B 3.2-16 9 B 3.3-28 9 B 3.3-72 9 B 3.3-116 9 B 3.2-17 9 B 3.3-29 9 B 3.3-73 9 B 3.3-117 9 B 3.2-18 9 B 3.3-30 9 B 3.3-74 9 B 3.3-118 9 B 3.2-19 9 B 3.3-31 9 B 3.3-75 9 B 3.3-119 9 B 3.2-20 9 B 3.3-32 9 B 3.3-76 9 B 3.3-120 9 B 3.2-21 9 B 3.3-33 9 B 3.3-77 9 B 3.3-121 9 B 3.2-22 9 B 3.3-34 9 B 3.3-78 9 B 3.3-122 9 B 3.2-23 9 B 3.3-35 9 B 3.3-79 9 B 3.3-123 9 B 3.2-24 9 B 3.3-36 9 B 3.3-80 9 B 3.3-124 9 B 3.2-25 9 B 3.3-37 9 B 3.3-81 9 B 3.3-125 9 B 3.2-26 9 B 3.3-38 9 B 3.3-82 9 B 3.3-126 9 B 3.2-27 9 B 3.3-39 9 B 3.3-83 9 B 3.3-127 9 B 3.2-28 9 B 3.3-40 9 B 3.3-84 9 B 3.3-128 9 B 3.2-29 9 B 3.3-41 9 B 3.3-85 9 B 3.4-1 9 B 3.2-30 9 B 3.3-42 9 B 3.3-86 9 B 3.4-2 9 B 3.2-31 9 B 3.3-43 9 B 3.3-87 9 B 3.4-3 9 B 3.2-32 9 B 3.3-44 9 B 3.3-88 9 B 3.4-4 9 B 3.3-1 9 B 3.3-45 9 B 3.3-89 9 B 3.4-5 9 B 3.3-2 9 B 3.3-46 9 B 3.3-90 9 B 3.-4-6 9 B 3.3-3 9 B 3.3-47 9 B 3.3-91 9 B 3.4-7 9 l B 3.3-4 9 B 3.3-48 9 B 3.3-92 9 B 3.4-8 9 I B 3.3-5 9 B 3.3-49 9 B 3.3-93 9 B 3.4-9 9 !
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| B 3.3-6 9 B 3.3-50 9 B 3.3-94 9 B 3.4-10 9 i B 3.3-7 9 B 3.3-51 9 B 3.3-95 9 B 3.4-11 9 B 3.3-8 9 B 3.3-52 9 B 3.3-96 9 B 3.4-12 9 !
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| B 3.3-9 9 B 3.3-53 9 B 3.3-97 9 B 3.4-13 9 B 3.3-10 9 B 3.3-54 9 B 3.3-98 9 B 3.4-14 9 B 3.3-11 9 B 3.3-55 9 B 3.3-99 9 B 3.4-15 9 I B 3.3-12 9 B 3.3-56 9 B 3.3-100 9 B 3.4-16 9 9;
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| Revisior.: 10 December 20,1996 32 T Westinghouse
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| kM AP600 List of Effective Pages Volume 10 Page Revision Page Revision Page ReWion Page Revision B 3.4-17 9 B 3.4-61 9 B 3.5-38 9 B 3.6-41 9 B 3.4-18 9 B 3.4-62 9 B 3.5-39 9 B 3.6-42 9 B 3.4-19 9 B 3.4-63 9 B 3.5-40 9 B 35-43 9 B 3.4-20 9 B 3.4-64 9 B 3.5-41 9 B 3.'<44 9 B 3.4-21 9 B 3.4-65 9 B 3.6-1 9 B 3.6-45 9 B 3.4-22 9 B 3.4-66 9 B 3.6-2 9 B 3.6-46 9 ,
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| B 3.4-23 9 B 3.4-67 9 B 3.6-3 9 B 3.6-47 9 I B 3.4-24 9 B 3.5-1 9 B 3.6-4 9 B 3.6-48 9 I B 3.4-25 9 B 3.5-2 9 B 3.6-5 9 B 3.6-49 9 i B 3.4-26 9 B 3.5-3 9 B 3.6-6 9 B 3.7-1 9 B 3.4-27 9 B 3.5-4 9 B 3.6-7 9 B 3.7-2 9 B 3.4-28 9 B 3.5-5 9 B 3.6-8 9 B 3.7-3 9 B 3.4-29 9 B 3.5-6 9 B 3.6-9 9 B 3.7-4 9 B 3.4-30 9 B 3.5-7 9 B 3.6-10 9 B 3.7-5 9 i B 3.4-31 9 B 3.5-8 9 B 3.6-11 9 B 3.7-6 9 B 3.4-32 9 B 3.5-9 9 B 3.6-12 9 B 3.7-7 9 B 3.4-33 9 B 3.5-10 9 B 3.6-13 9 B 3.7-8 9 B 3.4-34 9 B 3.5-11 9 B 3.6-14 9 B 3.7-9 9 B 3.4-35 9 B 3.5-12 9 B 3.6-15 9 B 3.710 9 B 3.4-36 9 B 3.5-13 9 B 3.6-16 9 B 3.711 9
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| [mC') B 3.4-37 9 B 3.5-14 9 B 3.6-17 9 B 3.7-12 9 B 3.4-38 9 B 3.5-15 9 B 3.6-18 9 B 3.7-13 9 B 3.4-39 9 B 3.5-16 9 B 3.6-19 9 B 3.7-14 9 j B 3.4-40 9 B 3.5-17 9 B 3.6-20 9 B 3.7-15 9 i B 3.4-41 9 B 3.5-18 9 B 3.6-21 9 B 3.7-16 9 B 3.4-42 9 B 3.5-19 9 B 3.6-22 9 B 3.7-17 9 B 3.4-43 0 B 3.5-20 9 B 3.6-23 9 B 3.7-18 9 B 3.4-44 B 3.5-21 9 B 3.6-24 9 B 3.7-19 9 B 3.4-45 B 3.5-22 9 B 3.6-25 9 B 3.7-20 9 B 3.4-46 - B 3.5-23 9 B 3.6-26 9 B 3.7-21 9 B 3.4-47 9 B 3.5-24 9 B 3.6-27 9 B 3.7-22 9 B 3.4-48 9 B 3.5-25 9 B 3.6-28 9 B 3.7-23 9 B 3.4-49 9 B 3.5-26 9 B 3.6-29 9 B 3.7-24 9 B 3.4-50 9 B 3.5-27 9 B 3.6-30 9 B 3.7-25 9 B 3.4-51 9 B 3.5-28 9 B 3.6-31 9 B 3.7-26 9 B 3.4-52 9 B 3.5-29 9 B 3.6-32 9 B 3.7-27 9 B 3.4-53 9 B 3.5-30 9 B 3.6-33 9 B 3.7-28 9 B 3.4-54 9 B 3.5-31 9 B 3.6-34 9 B 3.7-29 9 B 3.4-55 9 B 3.5-32 9 B 3.6-35 9 B 3.7-30 9 B 3.4-56 9 B 3.5-33 9 B 3.6-36 9 B 3.7-31 9 B 3.4-57 9 B 3.5-34 9 B 3.6-37 9 B 3.7-32 9 B 3.4-58 9 B 3.5-35 9 B 3.6-38 9 B 3.7-33 9 B 3.4-59 9 B 3.5-36 9 B 3.6-39 9 B 3.8-1 9
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| ,m B 3.4-60 9 B 3.5-37 9 B 3.6-40 9 B 3.8-2 9 (v)
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| List of Effectiv2 Pages AP600 List of Effective Pages Volume 10 Page Revision Page Revision Page Revision Page Revision B 3.8-3 9 B 3.9-4 9 B 3.8-4 9 B 3.9-5 9 B 3.8-5 9 B 3.9-6 9 B 3.8-6 9 B 3.9-7 9 B 3.8-7 9 B 3.9-8 9 B 3.8-8 9 B 3.9-9 9 B 3.8-9 9 B 3.9-10 9 B 3.8-10 9 B 3.9-11 9 B 3.8-11 9 B 3.9-12 9 B 3.8-12 9 B 3.9-13 9 B 3.8-13 9 B 3.8-14 9 B 3.8-15 9 B 3.8-16 9 B 3.8-17 9 B 3.8-18 9 B 3.0-19 9 B 3.8-20 9 B 3.8-21 9 B 3.8-22 9 B 3.8-23 9 B 3.8-24 9 B 3.8-25 9 B 3.8-26 9 B 3.8-27 9 B 3.8-28 9 B 3.8-29 9 B 3.8-30 9 B 3.8 31 9 B 3.8-32 9 B 3.8-33 9 B 3.8-34 9 B 3.8-35 9 B 3.8-36 9 B 3.8-37 9 B 3.8-38 9 B 3.8-39 9 l B 3.8-40 9 j
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| AP600 List of Effective Pages Volume 11 Page Revision Page Revision Page Revision Page Revision 16.2-1 10 18.2-1 9 18.8-3 10 18.12-7 9 16.2-2 10 18.2-2 9 18.8-4 10 18.12-8 9 16.2-3 10 18.2-3 9 18.8-5 10 18.12-9 9 16.2-4 10 18.2-4 9 18.8-6 10 18.12-10 9 16.2-5 10 18.2-5 9 18.8-7 10 16.2-6 10 18.2-6 9 18.8-8 10 16.2-7 10 18.2-7 9 18.8-9 10 16.2-8 10 18.2-8 9 18.8-10 10 16.2-9 10 18.2-9 9 18.8-11 10 l 16.2-10 10 18.2-10 9 18.8-12 10 16.2-11 10 18.2 11 9 18.8-13 10 16.2-12 10 18.2-12 9 18.8-14 10 16.2-13 10 18.2-13 9 18.8-15 10 16.2-14 10 18.2-14 9 18.8-16 10 16.2-15 10 18.2-15 9 18.8-17 10 16.2-16 10 18.2-16 9 18.8-18 10 l 16.2-17 10 18.2-17 9 18.8-19 10 i 16.2-18 10 18.2-18 9 18.8-20 10 cs 16.2-19 10 18.2-19 9 18.8-21 10
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| ('' ) 16.2-20 10 18.2-20 9 18.8-22 10 16.2-21 10 18.2-21 9 18.8-23 10 16.2-22 10 18.2-22 9 18.8-24 10 16.2-23 10 18.8-25 10 16.2-24 10 18.3-1 10 18.8-26 10 16.2-25 10 18.8-27 9 16.2-26 10 18.4-1 9 18.8-28 9 16.2-27 10 18.4-2 9 18.8-29 9 18.4-3 9 17-i 10 18.9-1 9 18.5-1 10 17.1-1 8 18.5-2 10 18.10-1 9 17.1-2 8 18.5-3 9 18.5-4 9 18.11-1 9 18-i 10 18.5-5 9 18.11-2 10 18-ii 10 18.5-6 10 18,11-3 9 18-iii 10 18.5-7 10 18.11-4 9 18-iv 10 18.5-9 9 13.11-5 9 .
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| 18-v 10 l 18.6-1 9 18.12-1 10 i 18.1-1 9 18.12-2 9
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| ! 18.1-2 9 18.7-1 10 18.12-3 9 18.1-3 10 18.12-4 9 18.1-4 9 18.8-1 10 18.12-5 9 A 18.1-5 9 18.8-2 10 18.12-6 9 Revision: 10 T Westinghouse 35 December 20,1996 l
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| ,,7+ g-- ..
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| List of Effectiv: P;ges AM List of Effective Pages Proprietary Volume Page Revision Page Revision Page Revision Page Revision Pi 9 Pii 9 Piii 9 P6.2- 1 0 P6.2-2 0 P6.2-3 0 P6.2-4 0 P6.2-5 0 P6.2-6 0 l
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| P6.2-7 0 P6.2-8 0 P6.2-9 0 P6.2-10 0 P6.2-11 0 P6.2-12 0 P6.2-13 0 P6.2-14 0 l P6.2-15 0 i P6.2-16 0 j P6.2-17 0
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| Resision: 10 l December 20,1996 36 W Westingh0USS
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| Change Roadmap l
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| p
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| 't)
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| CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1 Introduction
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| : 1. Table 1.1-2:
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| Deleted Pump House Building Ventilation system.
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| 1.2 General Plant Description
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| : 1. Section 1.2:
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| * Added a sentence to second paragraph about location of safety-related systems structures and equipment. j i
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| Added a statement that site specific stmetures are not safety-related of seismic I Category I.
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| : 2. Subsection 1.2.2:
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| A
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| ']
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| \
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| * Revised the characterization of parameters described in Chapter 2.
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| 1.8 Interfaces for Standard Design
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| : 1. Table 1.8-2: ,
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| l
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| =
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| Added items 18.3-1 and 18.5-1.
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| 1.9 Compliance with Regulatory Criteria
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| : 1. Subsection 1.9.4.2.1:
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| . Added Item I.G.I.
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| : 2. Subsectior.1.9.4.2.2:
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| Revised the response to Item A-26 to discuss failure of non-Class IE equipment.
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| : 3. Subsection 1.9.4.2.3:
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| * Revised Item 87 to correct the title of the ASME
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| * Code for Operation and Maintenance of Nuclear Power Plants."
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| Resision: 10 W Westingh0use R-1 December 20,1996
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| rmw-Charge Roadmap
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| : 4. Table 1.9-2:
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| e
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| +
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| Revised the applicable screening criteria and notes in Item 1.G.I.
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| IA Conformance with Regulatory Guides
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| : 1. Reg. Guide 1.68:
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| Added a position and summary for position App. A.4.T.
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| : 2. Reg. Guide 1.124:
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| Revised the summary description for position C.8.
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| O i
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| Resision: 10 December 20,1996 R-2 T Westinghouse
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| Change Roadmap o CIIAPTER 2 SITE CHARACTERISTICS
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| : 1. Revised second sentence of first paragraph to identify the parameter in Table 21 as the basis for design certification.
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| : 2. Table 2-1:
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| Revised the title.
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| 1 2A Design Soil Profiles
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| : 1. Subsection 2B.3.6: l Added Soil Density.
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| 1 i
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| (
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| O Resision: 10
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| [ WBStingh0USS R-3 December 20,19%
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| Change Roadmap CHAPTER 3 e
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| DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS 3.2 Classification of Structures, Components, and Systems
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| : 1. Subsection 3.2.1.1.2:
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| Identified the QA requirements for seismic Category II.
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| : 2. Subsection 3.2.2.5:
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| Specified that Appendix B and 10 CFR Part 21 apply to safety-related Section VII air tanks.
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| : 3. Subsection 3.2.2.6:
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| Specified that Appendix B and 10 CFR Part 21 apply to Class D seismic Category I components.
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| : 4. Subsection 3.2.4:
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| Deleted Pump House Building Ventilation system from list of systems.
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| : 5. Table 3.2-3:
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| Added the incore instrumentation systetu and the incore guide tubes.
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| Deleted the comment from valve PCS-PL-V014B.
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| Revised the nonsafety-related reactor vessel internals to seismic Category II.
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| Added the integrated head package shroud and seismic support plate (RXS). .
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| Auded CRDM latch housings and CRDM rod travel housing (RX3).
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| Revised the total number of sheets.
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| Revised the equipment class to containment penetrations in the steam generator system.
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| e Revision: 10 December 20,1996 R-4 3 Westinghouse
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| l 1
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| Change Roadmap f
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| lQ
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| '\_)
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| 3.6 Protection Against the Dynarnic Effects Associated with the Postulated Rupture of Piping i
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| : 1. Subsection 3.6.1.3.2:
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| Revised the discussion of the order of preference of protection mechanisms.
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| : 2. Subsection 3.6.1.3.2: )
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| Added discussion on the evaluation of separating structures. ,
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| \
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| Added the break locations to be considered under Barriers and Shields. l
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| : 3. Subsection 3.6.2.1.1.4:
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| Added CVS makeup piping at the containment penetration to the list of break i exclusion piping.
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| : 4. Subsection 3.6.2.5:
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| 1 Rewritten and expanded to provide additional information on the pipe rupture n hazard evaluation being done for design certification.
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| i ) \
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| : 5. Subsection 3.6.3.2:
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| Added a statement on the conformance with NRC guidance. )
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| Revised to add Class 1 and delete the reference to Appendix 3E.
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| Revised to clarify how the bounding analysis curves are used.
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| Revised and expanded the description of the bounding analysis curves.
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| : 6. Subsection 3.6.3.3:
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| Revised the description of the leakage flaw.
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| * Added the method of e"aluating local failure for ferritic steel.
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| Revised the descriptic.i of the acceptance criteria.
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| * Clarified the use of the bounding analysis curve by the Combined License applicant.
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| ' f~h
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| Revision: 10
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| [ WBStinghouse R-5 December 20,1996
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| Change Roadmap
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| ]
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| : 7. Subsection 3.6.3.4:
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| e Added the references to information in other sections.
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| : 8. Subsection 3.6.4.2:
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| Clarified the activities of the Combined License applicant.
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| : 9. Subsection 3.6.5:
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| Added Reference 12.
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| : 10. Table 3.6-2:
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| Changed the size of the SG nozzle to 4 inches in Rooms 11401 and 11402.
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| Moved the 4 in. ADS and associated valve and branch tee to the right hand column in Rooms 11603 and 11702 Deleted the CCS valve room (12561) and the rail car bay / filter storage area (12371).
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| I1 Table 3.6-3: .
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| Added.
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| 3.7 Seismic Design
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| : 1. Section 3.7:
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| Added an operating basis earthquake for the purpose of shutdown criteria to the fourth paragraph.
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| : 2. Subsection 3.7.3.15:
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| Revised the description of damping values.
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| : 3. Subsection 3.7.3.17:
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| * Revised the description of how the four soil cases are considered.
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| : 4. Table 3.7.1-1:
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| Deleted separate line for reactor coolant loop damping and changed " piping systems" to " piping" in next two lines.
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| e Revision: 10 December 20,1996 R-6 3 W85tingh00S8
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| =-> l Change Roadmap l
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| f3 Q l 3.9 Mechanical Systems and Components
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| : 1. Subsection 3.9.2.3: i Added reference to WCAP-14761. l
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| : 2. Subsection 3.9.3.1.5:
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| i a
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| Added reference to References 19 and 20.
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| : 3. Subsection 3.9.4.3:
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| +
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| Added a paragraph about the functional capability of the CRDMs. l
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| : 4. Subsection 3.9.6.2:
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| Revised the discussion about the inservice testing of RTNSS important valves.
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| : 5. Subsection 3.9.6.2.2:
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| Deleted the bullets about pressure isolation and temperature isolation under l
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| ,m- valves leakage inservice test, since these tests are not applicable.
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| t )
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| Added statements that these tests are not required.
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| Revised the discussion about check valve low differential pressure tests.
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| Added requirements on service life for explosive charges.
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| Added main steam line safety valves to 5 year test treguency and modified 3
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| requirement for nonreclosing valves.
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| : 6. Subsection 3.9.6.2.3:
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| Added this subsection, Valve Disassembly and Inspection. l
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| : 7. Subsection 3.9.6.3:
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| i Revised reference to ASME OM Code. l 1
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| : 8. Subsection 3.9.7.2: . j Added information on the resistance ofincore thimble tubes to vibration and wear.
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| (~h t i w
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| Reiision: 10 Y W8Stingh00Se R-7 December 20,1996
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| L-5 Change Roadmap n- ;
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| : 9. Subsection 3.9.9: 1 l
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| - Added References 18,19, and 20.
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| : 10. Table 3.9-11: l i
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| l Deleted line for DW.
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| i
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| * Revised Notes 2,3, and 4. i Added criteria for piping components.
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| ]
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| l
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| * Added Notes 5, 6, 7, 8, 9.10 and 11.
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| l l
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| : 11. Table 3.9-12: l Deleted repeated entries under passive containment cooling system. ;
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| l Added RNS-PL-V045. l
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| : 12. Table 3.9-16:
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| Revised table information and notes in response to NRC comments.
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| l
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| : 13. Table 3.9-17 l Revised frequency for VES testing.
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| Revised Note 8.
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| 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment
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| , 1. Subsection 3.10.2.2:
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| Added information on evaluation of feedwater valve disks.
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| : 2. Subsection 3.10.6:
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| Revised the Combined License information item. .
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| O Revision: 10 December 20,1996 R-8 W Westinghouse
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| Change Roadmap Q_)
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| 3.11 Environmental Qualification of Mechanical and Electrical Equipment j
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| : 1. Table 3.11-1:
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| Changed IDSS Spare Penetration Box to IDSS Spare Termination Box.
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| Changed IDSA (etc) Regulating Transfer to IDSA Regulating Transformer. )
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| Changed the tag numbers for the Reactor Trip Switchgear.
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| Deleted extra spaces on sheet 10.
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| l Changed QDPS Processing Cabinet to QDPS Cabinet.
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| Added QDPS Thermocouple Panels, MCR/RSW Transfer Switch Panels, Source l Range Neutron Flux Preamplifier Panels, Intermediate Range Neutron Flux Preamplifier Panels, and Power Range Neutron Flux High Voltage Distribution ;
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| Boxes. l 3B Leak-Before-Break Evaluation of the AP600 Piping 1
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| : 1. Section 3B.2:
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| i g)
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| Added "Other mechanisms" to the list and identified the line that used Type 304 i L material. !
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| : 2. Subsection 3B.2.1:
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| Spelled out the acronym EPRI.
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| : 3. Subsection 3B.2.4: l 0
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| Added a discussion of stress range reduction factors for Class 2 and 3 lines.
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| Added the accumulator line to the line that do not have significant transients to cause thermal cycling fatigue.
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| : 4. Subsection 3B.2.5- I Added information about dynamic strain aging effects to main steam and main feedwater lines.
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| : 5. Subsection 3B.2.6:
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| Changed the lines identified as susceptible to Bulletin 88-08 adverse stresses to none.
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| ']
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| (V Revision: 10 3 W85Tingh0USS R-9 December 20,1996 l
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| l I
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| ; _=_ . ;
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| Change Roadmap Added pressurizer spray line to the not susceptible list.
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| e Added reference augmented feedwater line inspection.
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| : 6. Subsection 3B.2.7:
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| l
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| * Added, Other M hanisms.
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| : 7. Subtxtion 3B.3.1:
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| l Revised to address NRC comments.
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| 1
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| : 8. Subsection 3B.3.2:
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| Revised to address NRC comments.
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| : 9. Subsection 3B.3.3:
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| Revised to address NRC comments.
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| : 10. Section 3B.4:
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| Revised to address differences in stainless steel and fenitic steel pipe rather than differences in Class 1 and Class 2.
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| I1. Section 3B.5:
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| Added a discussion about inservice inspection.
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| : 12. Section 3B.6:
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| Revised to address Class 3 lines and reference the requirement for spot radiography of Class 3 lines.
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| : 13. Section 3B.8:
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| Defined the augmented inspection as at the weld of the pipe to the nozzle.
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| : 14. Table 3B-1:
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| Added pipe diameter and material.
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| deleted the ADS Stage I line.
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| O Revision: 10 December 20,1996 R-10 { Westinghouse
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| l Change Roadwp I
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| ;O
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| : 15. Table 3B-2:
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| * Deleted the ADS Stage I line.
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| i
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| : 16. Figure 3B-40:
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| * Deleted.
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| 4 i
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| l I
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| )
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| O 9
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| Revision: 10 3 W85tingh0US8 R-11 December 20,1996
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| Change Roadmap CHAPTER 4 REACTOR t 4.4 Thermal and Hydraulic Design
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| : 1. Subsection 4.4.2.2.1:
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| Revised the reference to the WRB-2 correlation.
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| : 2. Subsection 4.4.6.3:
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| Changed the intermediate range compensated ionization monitors to pulse fission monitors.
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| l l
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| m.
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| O-Revision: 10 December 20,1996 R-12 3 Westinghouse
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| 1 Chang: Roadmap N
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| CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTING SYSTEMS l
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| 5.2 Integrity of Reactor Coolant Pressure Boundary
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| : 1. Subsection 5.2.5: )
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| Revised the a:russion of leakage into auxiliary systems.
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| : 2. Subsection 5.2.5.1.2:
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| Changed the heading to Reactor Head Seal and deleted discussion of reactor coolant pump flange leakoff.
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| : 3. Subsection 5.2.5.7: j Changed reference to Technical Specification LCOs due to revisions in Chapter 16.
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| fG 5.4 Component and Subsystem Design O 1. Subsection 5.4.1.2.1- i Changed the reactor coolant pump flange seal to a canopy seal.
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| i I
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| Resision: 10 3 WB5tingh00Se R-13 December 20,1996 h
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| i- ..
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| Change Roadmap CHAPTER 6 e
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| ENGINEERED SAFETY FEATURES 6.1 Engineered Safety Features Materials
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| : 1. Subsection 6.1.1.1:
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| Added material requirements for air storage tanks.
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| : 2. Table 6.1-1:
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| Added air storage tanks.
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| 6.2 Containment Systems
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| : 1. Subsection 6.2.3.1.3:
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| Revised item C to address NRC comments on containment isolation.
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| Added Item L, pertaining to the diverse method of initiating closure of isolation valves.
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| 1
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| : 2. Subsection 6.2.3.3:
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| Revised Item A to address NRC comments.
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| : 3. Subsection 6.2.3.5:
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| Revised the discussion on how containment isolation signals are initiated.
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| : 4. Subsection 6.2.6:
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| * Added References 22,23, and 24.
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| 6.3 Passive Core Cooling System
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| : 1. Subsection 6.3.3.4.3:
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| Corrected the classification of the RCS hot leg level indication to safesei., ed from nonsafety-related.
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| O Revision: 10 December 20,1996 R-14 3 Westingh0LIS8
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| Change Roadmap j
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| O 6.4 Habitability Systems
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| : 1. Subsection 6.4.2.2:
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| Added the volume of the air storage tanks.
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| : 2. Subsection 6.4.2.3A Added the design pressure of the air storage tanks.
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| : 3. Subsection 6.4.5.3 )
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| I Added, Air Quality Testing.
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| l 1
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| 4 0
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| }
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| Resision: 10 W Westingh00S8 R-15 December 20,1996
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| Change Roadmap I
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| CHAPTER 7 O I i
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| INSTRUMENTATION AND CONTROLS l
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| 7.1 Introduction l
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| : 1. Subsection 7.1.2.8.2:
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| l Changed the intermediate range to a pulse fission chamber.
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| 1
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| : 2. Subsection 7.1.7: I l
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| Revised Reference 4.
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| I 7.2 Reactor Trip l
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| : 1. Figure 7.2-1 (Sheets 19 and 20) l DAS changes to be consistent with PRA. j i
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| 7.3 Engineered Safety Features
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| : 1. Subsection 7.3.1.2.15:
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| < . Added requirements for reset of CVS isolation.
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| : 2. Subsection 7.3.1.2.18:
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| Changed the pressurizer level setpoint to Low-1.
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| : 3. Table 7.3-1: ..
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| +
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| Changed the pressurizer level setpoint to Low-l in Item 17.
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| 7.5 Safety-Related Display Information
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| : 1. Table 7.5-1:
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| ~
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| +
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| Sheet 1 - deleted comment for Neutron flux.
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| Sheet 4 - added lines for diesel generator load, voltage to diesel-backed buses, power supply to diesel backed buses, and RCP bearing water temperature.
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| Sheet 5 - changed power supply for steam generator valve status to Non-1E and added lines for circulating water pump breaker status and condenser backpressure.
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| O Revision: 10 December 20,1996 R-16 T Westinghotise
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| Change Roadmap g3 ,
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| \ ) )
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| Sheet 6 - revised the description of the PCS water storage tank isolation valve statuses.
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| Sheet 7 - changed the power supply for the CMT discharge isolation valve status I to Non-Class IE and revised the description of the IRWST injection tank I isolation valve statuses.
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| Sheet 8 - revised the description of the PRHR HX control valve, IRWST gutter i bypass isolation valve, accumulator isolation valve and pressurizer spray valve I statuses and added the accumulator isolation valve status.
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| Sheet 9 - revised the description of the makeup blend valve status. I Sheet 10 - added a line for RN3 pump status.
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| 7.7 Control and Instrumentation Systems
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| : 1. Subsection 7.7.1.11:
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| DAS changes to be consistent with PRA.
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| Oi V
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| l O N U
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| Revision: 10
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| [ W85tiflgh00S8 R-17 December 20,1996
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| i Change Roadmap CHAPTER 8 e
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| ELECTRIC POWER 8.3 Onsite Power Systems
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| : 1. Table 8.3.2-2 and 8.3.2-3:
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| 4 Added panel lighting to emergency lighting.
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| Revised the power required for emergency lighting and panel light and subtotals and total for power required.
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| : 2. Table 8.3.2-4:
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| Revised the description under 125 Vdc Panel.
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| E
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| {
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| O 1
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| J N
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| O Revision: 10 December 20,1996 R-18 [ WB5tiligh00Se
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| I Change Roadmap l
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| ,m_
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| i )
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| tj CHAPTER 9 ,
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| i 1
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| AUXILIARY SYSTEMS l 9.1 Fuel Storage and Handling l
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| : 1. Revised to incorporate additional 6 -il and clarification requested by NRC. j 9.2 Water Systems
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC. l l
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| : 2. Figure 9.2.4-1:
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| Added to show containment isolation valves and penetration.
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| : 3. Figure 9.2.7-1: l Added sheet 3 to include containment isolation penetrations and valves.
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| 9.3 Process Auxiliaries (Qj 1. Revised to incorporate additional detail and clarification requested by NRC.
| |
| : 2. Figure 9.3.1-1:
| |
| I Revised to include valve numbers on containment isolation valves.
| |
| : 3. Figure 9.3.3-1:
| |
| Revised to include valve numbers and show individual valves.
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| 9.4 Air-Conditioning, Heating, Cooling and Ventilation System
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC.
| |
| : 2. Added reference callouts in text to be correct, consistent and complete.
| |
| 9.5 Other Auxiliary Systems
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC.
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| 9A Fire Protection Analysis
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC.
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| p d
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| Revision: 10 Westingh00Se R-19 December 20,1996
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| .:-~.~.
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| ~
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| Change Roadmap CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 10.1 Summary Description
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC.
| |
| l 10.4 Other Features of Steam and Power Conversion System
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| : 1. Revised to incorporate additional detail and clarification requested by NRC.
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| 91 i
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| l O
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| Revision: 10 December 20,1996 R-20 [ Westingh0USS
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| i-- n Change Roadmap
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| /"'N l
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| CIIAPTER 11 1
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| RADIOACTIVE WASTE MANAGEMENT 11.2 Liquid Waste Management Systems
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC. In addition,. valve position was changed to correct an error. !
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| : 1. Figure 11.2-2:
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| i
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| ~
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| Revised sheet I to include valve numbers on containment isolation valves. l l
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| 11.3 Gaseous Waste Management System
| |
| : 1. Revised to incorporate additional detail and clarification requested by NRC.
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| l i
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| f-i e i
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| d 1
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| 1 l
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| O Revision: 10
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| *8 WB5tiligh0USe R-21 Decernber 20,1996
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| ~
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| IIi Change Roadmap m-O CHAPTER 14 INITIAL TEST PROGRAM 14.2 Specific Information to be Included in Standard Safety Analysis Reports Revision 10 of the AP600 SSAR, Chapter 14 Initial Test Program incorporates changes made in response to NRC staff comments. These responses have been documented in two letters to the staff.
| |
| Westinghouse letter NSD-NRC-96-4857, dated October 23,1996 documents revisions made to Chapter 14 in response to the NRC {{letter dated|date=August 20, 1996|text=letter dated August 20,1996}} which contained questions on Revision 9 of the AP600 SSAR Chapter 14 from the Mechanical Engineering Brar,ch in the ECGB scope of review.
| |
| Westinghouse letter NSD-NRC-96-4902, dated December 6,1996 documents revisions made to Chapter 14 in response to the NRC {{letter dated|date=November 8, 1996|text=letter dated November 8,1996}} which contained staff comments on Revision 9 of the AP600 SSAR Chapter 14 from HQMB and included comments from HQMB and other branches.
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| Revision: 10 December 20,1996 R-22 [ Westingh0!!Se
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| i Change Roadmap
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| (^)
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| V CHAPTER 16 TECHNICAL SPECIFICATION 16.2 Reliability Assurance Program
| |
| : 1. Subsection 16.2.1: !
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| Modified the final paragraph grammatically.
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| : 2. Subsection 16.2.6: l l
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| Listed an additional goal.
| |
| l Clarified the goal related to baseline reliability values. j i
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| : 3. Subsection 16.2.8:
| |
| Added a paragraph to show the relationship between O-RAP and Combined j License applicant's QA program. 1 p 4. Subsection 16.2.9:
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| V -
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| Defined the term " risk-significant" in more detail.
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| : 5. Table 16.2-1:
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| Reorganized to show components grouped by system. l Provided system-level rationales and remarks.
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| : 6. Table 16.2-2:
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| Modified to show a higher level of influence of the expen panel on the decision-making process.
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| Revision: 10
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| [ Westingh0USe R-23 December 20,1996
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| Change Roadmap CHAPTER 18 e
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| HUMAN FACTORS ENGINEERING 18.1 Overview 4
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| : 1. Section 18.1:
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| Changed title of 18.11 to " Human System Interface Design Test Program" to be consistent with the title found on page 18.11-1.
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| 18.3 Operating Experience Review
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| , 1. Subsection 18.3.1:
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| Revised to help resolve DSER Open Item 18.3.3.1-2.
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| 18.5 AP600 Task Analysis Implementation Plan
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| : 1. Subsection 18.5.4:
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| Revised Combined License Information items to explicitly state that the completion of uncompleted human factors engineering program elements is the responsibility of trie Combined License applicant.
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| 4
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| =
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| Revised to address DSER Open Item 18.5.3-4.
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| : 2. Subsection 18.5.5:
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| Revised References 12 and 14.
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| 18.7 Integration of Human Reliability Analysis with Human Factors Engineering
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| : 1. Subsection 18.7.1:
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| Revised Combined License Information items to explicitly state that the completion of uncompleted human factors engineering program elements is the responsibility of the Combined License applicant.
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| 18.8 Human System Interfae: Design
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| : 1. Section 18.8:
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| Deleted last sentence.
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| O Revision: 10 December 20,1996 R-24 [ Westiligh0USB
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| Change Roadmap f
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| (D C/
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| : 2. Subsection 18.8.5:
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| Revised Combined License Information items to explicitly state that the completion of uncompleted human factors engineering program elements is the responsibility of the Combined License applicant..
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| 18.11 Iluman System Interface Design Test Program
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| : 1. Subsection 18.11.1:
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| Revised Combined License Information items to explicitly state that the completion of uncompleted human factors engineering program elements is the
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| , responsibility of the Combined License applicant.
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| 18.12 Inventory
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| : 1. Section 18.12:
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| * Changed title to " Inventory" to be consistent with the title listed on page 18.1-4.
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| Resision: 10
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| [ W85tingt100S8 R-25 December 20,1996
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| N' i
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| Volumes 2 through 11 i
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| l i 10 sets of Master Table of Contents i
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| r O
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| l.
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| (hisert in front of Volumes 2 through 11) i -
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| ; SSAR Revision 10 - December 20,1996 I' I
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| : i. i I
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| ! i E .,. .-..- . . - - . - - . . . , .. _
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| Master Table of Contents
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| /m Y )1 MASTER TABLE OF CONTENTS Section Title Page Volume 1 CHAI7TER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT . . 1.1-1 1.1 Introduction . ... ........... . . .. . . . .. . .. 1.1-1 1.1.1 Plant Location . . . . . . ..... ... . . ... . .. 1.1-1 1.1.2 Containment Type ..... ... .. .... ..... .. .. .. 1.1-1 1.1.3 Reactor Type ...... . . ......... .... ... .. .... 1.1-1 1.1.4 Power Output . . . . . .. . . .. .. .... ...... 1.1-1 1.1.5 Schedule . . . . . ......... ... .. .... ... . . . 1.1-1 1.1.6 Format and Content ....... . ... .... ...... .. 1.1-2 1.1.7 Combined License Information . ... . ..... . ....... . 1.1-3 1.2 General Plant Description . . . . . . . . . . .. . . .. . ........... ... 1.2-1 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 1.2.2 Site Description ........ . .... .. .. ... . . . 1.2-15 1.2.3 Plant Arrangement Description . . . .. . .... . .. 1.2-16 1.2.4 Nuclear Island . . . . . . . . . . . .. . . . , . . ... . .. 1.2-17 1.2.5 Annex Building . . . . . . . .. ... . . .. ..... 1.2-24 1.2.6 Diesel Generator Building . . .. . . .... ............ 1.2-25 Radwaste Building . . . . . . . . .
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| [O
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| \ 1.2.7 .. .. . ........ ... 1.2-26 1.2.8 Turbine Building .. ...... . ..... ... . ... 1.2-26 1.2.9 Combined License Information . .. . . . . .... . . 1.2-27 1.3 Comparisons with Similar Facility Designs ... . . . .... ... 1.3-1 1.4 Identification of Agents and Contractors . . . . ..... . . 1.4-1 1.4.1 Applicant - Program Manager .. . . . .... ... 1.4-1 1.4.2 Other Contractors and Participants . .. ..... . ..... . . 1.4-1 1.4.3 Combined License Information . . .. ... .. .. . . 1.4-3 1.5 Requirements for Further Technical Information . ... ... . . 1.5-1 1.5.1 AP600 Safety-Related Tests' . ... .. . . . 1.5-1 1.5.2 AP600 Component Design Tests .. .. .. . . . ... 1.5-7 1.5.3 Combined License Information . . ... ........ 1.5-8 1.5.4 References . ....... .. .. . .. . . ... .. 1.5-8 1.6 Material Referenced ........ .... .. ....... .. .. ..... . 1.6-1 1.7 Drawings and Other Detailed Information . .... ............... 1.7-1 1.7.1 Electrical and Instmmentation and Control Drawings . . . . 1.7-1 1.7.2 Piping and Instmmentation Diagrams . ... . ... . 1.7-1 1.7.3 Combined License Information .... . . ... . 1.7-1 1.8 Interfaces for Standard Design . . . . . . ... . . . 1.8-1 1.9 Compliance with Regulatory Criteria ... . ... .. .. . . 1.9-1 1.9.1 Regulatory Guides . ...... . .. .. ... . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) .. . 1.9-3 1.9.3 Three Mile Island Issues .... .. ... . 1.9-3
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| /"'N (v)
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| Revision: 10
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| [ W85tiligt10US8 i December 20,1996
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| , =
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| l l m- Master Table of Contents l
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| MASTER TABLE OF CONTENTS (Cont.)
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| l i
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| Section Title Pm l
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| 1.9.4 Unresolved Safety Issues and Generic Safety Issues . .. .. ... . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues ...... . 1.9-74 1.9.6 Combined License Information . . . . . . . ...... ..... 1.9-107 1.9.7 References . .. ..... ............ .. ... . . . . 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES ......... .. . . . 1 A- 1 1 A.1 References . .. . .. .... ... . .. ... ... . . .. lA-79 1 APPENDIX 1B SF. VERE ACCIDENT MITIGATION DESIGN ALTERNATIVES ...... IB-1 I B.1 Introduction . . . . . .. .. .. .. . . .. ... ... .... . . . . . . I B-1 I B.2 Summary . ....... ..... . ..... .......... . . . . . . . . I B-1 IB.3 Selection of SAMDAS . . . . . . .. . . .. ..... . ... IB-2 I B.4 Methodology . . . .... ......... .... . .. . .. .. .. . . IB-2 IB.4.1 Risk Reduction .. ..... ... .. .. . ... ... IB-2 IB.4.2 Capital Cost Estimates . . . . . . I B-3 l
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| 1B.4.3 Cost Benefit Analysis . . . . . .... .. ...... .. ....... IB-3 IB.5 PRA Release Categories . . .. . .. . . . . . ...... . IB-3 ;
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| IB.5.1 Release Category OK . . .... . . ... . ...... IB-4 !
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| 1B.S.2 Release Category OKP ... .. . ... . ... .. . . IB-4 '
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| 1B.5.3 Release Category CC . . .. . . .. .. . . . ,..... 1B-5 )
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| IB.5.4 Release Category CI . . . .. .. .. . ... . . . I B-5 i I B.6 Total Population Dose . . . .. . . . . . . ........ IB-5 !
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| 1B.7 SAMDA Description and Benefit . . .. . .. . ... . 1B-6 i 1B.7.1 Upgrade the CVCS for Small LOCAs . . . . .... .. ..... 1B-6 I IB.7.2 Filtered Vent . . . ... ... . .... ........ . IB-6 1 1B.7.3 Locate Normal RHR Inside Containment . . . . . . . . . . 1 B-7 l 1B.7.4 Self-Actuating Containment Isolation Valves . . . .. . .... IB-7 I 1B.7.5 Passive Containment Sprays ... .. .... ... . .. .1B 7 l 1B.7.6 Active High Pressure Safety Injection System . IB-7 l
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| IB.7.7 Steam Generator Shell-Side Heat Removal System . .... ... IB-8 l 1 B.7.8 Direct Steam Generator Relief Flow to the IRWST . . . . . . . . I B-8 IB.7.9 Increased Steam Generator Pressure Capability . . . ... . IB-8 IB.7.10 Secondary Contaioment Filtered Ventilation ... ...... . 1B-8 1 B.7.11 Diversify the IRWST Discharge Valves ... . . . . . . IB 9 1B.7.12 Ex-Vessel Core Catcher .. ... ... ...... . . 1B-9 1 B.7.13 High Pressure Conta' ament Design . . . . . . . . . .. . . . . I B-9 1 B.7.14 Increase Reliability of Diverse Actuation System . ..... . . 1B-9 1 B.8 Results ..... . ...... . ... ...... .. . . . .... . . . IB-9 IB.9 References .. . ... . ... ..... .. . . ..... . iB-ll O
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| Revision: 10 December 20,1996 i [ Westingh00S8
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| 1--e Master Table of Contents
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| [ l (d
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| )
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| MASTER TABLE OF CONTENTS (Cont.) i i
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| Section Title Page l CHAPTER 2 SITE CHARACTERISTICS . ...... . . .. .. ... .. . .. . 2-1 2.1 Geography and Demography . . . . . . . . . . . . . . .. .. . . .. . 2-1 2.1.1 Combined License Information for Geography and Demography . 2-1 2.2 Nearby Industrial, Transportation, and Military Facilities ........ ... 2-1 2.2.1 Combined License Information for Identification of Site-specific Potential )lazards . .. . . ..... . . ... . ... . ... 2-2 2.3 Meteorology . . .. .......... .. . .. . .. . . . 2-2 23 1 Regional Climatology .... .. . ... . . .. . . 2-3 ,
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| . 2.3.2 Local Meteorology .. .. ... ...... . .. . .. 2-3 2.3.3 Onsite Meteorological Measurement Programs .
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| ..., ... . 2-3 2.3.4 Short-Term Diffusion Estimates . ... .. . ... .. ... . 2-3 2.3.5 Long-Term Diffusion Estimates . ........ . ... . . 2-4 2.3.6 Combined Licensed Information . . ... . ..... .. ... 2-4 2.4 Hydrologic Engineering . . . .. .. .. .... .......... . 2-5 2.4.1 Combined License Information . . .. ....... . . . . 2-5 1 2.5 Geology, Seismology, and Geotechnical Engineering .... ... ... . . 2-6 l 2.5.1 Basic Geological and Seismic Combined License Information .. . 2-6 2.5.2 Vibratory Ground Motion . . . . .. . .. ..... . . . . . . 2-7
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| /^\ 2.5.3 Surface Faulting Combined License lnformation . .. .. . . 2-7 l C
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| 2.5.4 Stability of Subsurface Materials and Foundations . .... 2-8 l 2.5.5 Combined License Information for Stability of Slopes . . .. 2-12 l 2.5.6 Combined License Information for Embankments and Dams . .. 2-13 2.5.7 References . . . . .. ...... ... . . . .. 2-13 APPENDIX 2A DESIGN SOIL PROFILES . . . . . . . . ..... . .. .. . . 2A-1 l 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. 2A-1
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| {
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| 2A.2 Generic Soil Profiles . . . . .. .. ... . . .. . . . . 2A-2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . .. . 2A-4 2A.4 Free-Field Site Response Analysis . ... .... .. .. . 2A-5 2A.5 2D Soil-Structure Interaction Analysis . . ... . .... 2A-7 j 2A.6 AP600 Design Soil Profiles .... . .. . . . . 2A-12 2A.7 References . . . .... .... .. . . .. ... 2A-14 APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL PROFILES . .. . . ..... . . ..... ... .. 2B-1 2B.1 2D SSI Analysis Parameters and Procedures . . . .. ... . .. . 2B-2 2B.l.1 Structural Models . . . . . . . .. ... . . . . . 2B-2 2B.1.2 SASSI Foundation Models .. .. . .. . . . 2B-2 2B.I.3 Soil Properties for SSI Analysis . . . . ...... . . 2B-2 2B.1.4 Input Motion . . . . . ... . . .. . . 2B-3 2B.I .5 Two-Dimensional Enveloped SSI Results . .. . 2B-3
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| ,m 2B.2 Design Soil Profiles . . .. . . . 2B-3 (v)
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| Revision: 10 4
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| Westi$0USe i December 20,1996
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| 7:--1 Master Table of Contents l MASTER TABLE OF CONTENTS (Cont.)
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| 1 Section Title _P_ age 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . . .. 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) . .... .. .. . . . . . . 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . . . 2B-5 2B.2.4 Variation of Soil Properties and 60 Percent Requirement of Free-Field Spectra at Foundation Level . . . . .... . 2B-5 2B.2.5 AP600 Design Soil Profiles . . ... . ... . . .. . 2B-6 2B.3 Soil Profile Parametric Studies: ... .. .. ... .. . . . . 2B-6 2B.3.1 Depth-to-Base Rock . . . . . . . . .. .. ... .. . . 2B-7 2B.3.2 Soil Curves for Clay Material . .. . ... . .. ..... 2B-7 2B.3.3 Poisson's Ratio for Soil above Water Table . ... .... .... 2B-8 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site . . . . . . . . . . 2B-8 2B.3.5 Idriss 1990 Soil Curves . ... . ...... . . 2B-9 2B.3.5 Soil Densitys . .. .. . . . ..
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| .,. .... . 2B-9 2B.4 References . . . ........... . . .... .. ... .... 2B-9A ;
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| Volume 2 .
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| APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES . .... . ...... . 2C-1 2C.1 2D SASSI Analysis for Seismic Lateral Earth Pressure ....... . . . 2C-1 2C.1.1 Analysis Method . .... . ... .. ....... .. 2C-1 l 2C.1.2 Structural Models .. . . ... . . . .... . . 2C-1 2C.I.3 SASSI Foundation Models .. . .. . ...... 2C-1 '
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| 2C.I .4 Representation of Adjacent Stmetures .. . . . . .. .. 2C-2 .
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| 2C.1.5 Input Motion . . .. . .. ... . . ..... . 2C-2 l 2C. I .6 Soil Properties .. . ... . ... .... . .. .. 2C-2 l 2C.1.7 2D SASSI Analyses Results . . .. . . .. . 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island ... ... ... 2C-2 2C.3 Local Distribution of Lateral Earth Pressure .. . . . . . . .. . . 2C-3 2C.4 References . . .. ... .. . . . . . 2C-4 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS . . . . .. . ... ..... . ... 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria 3.1-1 3.1.1 Overall Requirements . . . .. . . ... 3.1-1 3.1.2 Protection by Multiple Fission Product Barrier: .. ... . 3.1-4 3.1.3 Protection and Reactivity Control Systems .. . . . 3.1-12 3.1.4 Fluid Systems .. .. . .. .... .... 3.1-18 3.1.5 Reactor Containment ...... .. . . . 3.1-30 3.1.6 Fuel and Reactivity Control .. . . ..... . 3.1-34 3.1.7 Combined License Information .. .. . . . . 3.1-37 3.1.8 References . . . . . .. ...... .. ... .. .. . . . 3.1-37 Revision: 10 December 20,1996 iv [ Westingh0USB
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| c--e Master Table of Contents
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| ( f
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| (
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| (.)s MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.2 Classification of Structures, Components, and Systems .... . .... 3.2-1 3.2.1 Seismic Classification . . . . . .. ........ .. .. .. . 3.2-1 3.2.2 AP600 Classification System . . . . .... ....... . . 3.2-3 3.2.3 Inspection Requirements . . . . . .. .. . .. . . 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System . ...... . ........ . . .. 3.2-13 3.2.5 Combined License Information .. .. . .. .... .. 3.2-16 3.2.6 References . . . . . . . .. ... ... . ........ 3.2-17 3.3 Wind and Tomado Loadings . .. . ..... . .... . .. . . 3.3-1 3.3.1 Wind Loadings . ... ........ .. ... . .. . . . 3.3-1 3.3.2 Tornado Loadings . . . . . .... . .. .. ............. 3.3-2 3.3.3 Combined License Information .. ... .. ..... .. . 3.3-4 3.3.4 References . . ... ... . . . .. .. ...... 3.3-4 3.4 Water Level (Flood) Design . ... . . . ........... 3.41 3.4.1 Flood Protection ... .. ... . .. . .. .. .. . 3.4-1 3.4.2 Analytical and Test Procedures .. . . . .... .. 3.4-24 3.4.3 Combined License Information . . . . . .... . . . . 3.4-24 3.4.4 References . . . . ... .. . ... .. ...... . 3.4-24 3.5 Missile Protection . ..... ....... . . ... . .. . . .. . . 3.5-1 I,,')
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| \
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| 3.5.1 Missile Selection and Description . . .. . ...... ... . 3.5-4 V 3.5.2 Protection from Externally Generated Missiles ..... . . . . . 3.5-13 3.5.3 Barrier Desi[;n Procedures . . . . .......... ... . . . 3.5-13 3.5.4 Combined License Information . . .. . . . 3.5-16 3.5.5 References . .. . .. .. . ..... .. ... . . .. 3.5-16 3.6 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping . ..... ....... ........ ..... . 3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment . . .... ... . . ... . . .. . . 3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping . . . . ...... 3.6-12 3.6.3 Leak-before-Break Evaluation Procedures ... ... . 3.6-31 3.6.4 Combined License Information .. . . .... ... 3.6-38 3.6.5 References . . ... . . .. .. ... . ..
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| .. .. 3.6-38 3.7 Seismic Design . .. .. ... .... . ... .. .. . 3.7-1 3.7.1 Seismic Input .. .. ..... . . . 3.7-1 3.7.2 Seismic System Analysis . . .. . . ... . . 3.7-6 3.7.3 Seismic Subsystem Analysis . . . . ... . . 3.7-20 3.7.4 Seismic Instrumentation .... . . . . . . . . . 3.7-46 3.7.5 Combined License Information ... ... . . . . . . .. . 3.7-48 3.7.6 References ....... . . . . . ...... . 3.7-49 3.8 Design of Category 1 Structures .. ... . .. .. .. . .. 3.8-1 3.8.1 Concrete Containment . .. . .. .. . . .. . 3.8-1 m
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| 3.8.2 Steel Containment . .. .... ... . 3.8-1 v
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| Revision: 10
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| [ W85tingt10LIS8 y December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h 3.8.3 Concrete and Steel Internal Stmetures of Steel Containment . 3.8-16 3.8.4 Other Category I Structures . .. ... . . . .. 3.8-39 3.8.5 Foundations ....... ..... . . ... . . 3.8-53 3.8.6 Combined License Information .. .. . .. . 3.8-60 3.8.7 References .... ........ .. ... .. .. . 3.8-60 Volume 3 3.9 Mechanical Systems and Compouents ... . ....... . . .. 3.9-1 3.9.1 Special Topics for Mechanical Components . . . . . . .. . . 3.9-1 3.9.2 Dynamic Testing and Analysis .. . ........ . . .. . 3.9-Su 3.9.3 ASME Code Classes 1,2, and 3 Components, Component Suppoits, and Core Support Structures .. . .. . . . 3.9-45 3.9.4 Control Rod Drive System (CRDS) . . .. . 3.9-71 3.9.5 Reactor Pressure Vessel Internals . . .. . . .. 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . . . 3.9-89 3.9.7 Integrated Head Package . . . . . .. . 3.9-97 3.9.8 Combined License Information . . ..... 3.9-102 3.9.9 References .... . .. ..... ... .. . . .. 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment . . ....... .. ... . .... .. . . .. . . 3.10-1 3.10.1 Seismic and Dynamic Qualification Criteria ....... . . 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Instmmentation, and Mechanical Components . . . . .. . 3.10-3 3.10.3 Method and Procedures for Qualifying Supports of Electrical Equipment, Instrumentation, and Mechanical Components . . 3.10-7 1 3.10.4 Documentation . . . .. . . . .... . . 3.10-7 l 3.10.5 Standard Review Plan Evaluation . . . . . 3.10-7 3.10.6 Combined License Information Item on Experienced-Based l Qualification ... . . .. .. . . 3.10-8 l 3.10.7 References . .. 3.10-8 l
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| 3.11 Environmental Qualification of Mechanical and Electrical Equipm:nt . . 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . 3.11-1 3.11 2 0,aalification Tests and Analysis . .,... . 3.11-3 3.11.3 Loss of Ventilation . .. . . . .. . . 3.11-4 3.11.4 Estimated Radiation and Chemical Environment .. . 3.11-5 l
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| 3.11.5 Combined License Information Item for Equipment Qualification File. . . ... .. . .. . . 3.11-5
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| , 3.11.6 References .... . . . ..... . . 3.11-6 O
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| l Resision: 10 i December 20,1996 vi * [ W85tiligh0US8
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| Master Tchte of Contents
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| (
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| b MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page l APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS . . . . . . . . 3A-1 3A.1 Codes and Standards . . ... . . ........ . . . . . . . . . . 3 A- 1 3A.2 Loads and Load Combinations . . . . . ..... . ......... 3A-1 1 3A.2.1 Loads ....... . . .. . . . . . .. ... . 3A-1 I 3A.2.2 Load Combinations . .. . . . . . .. . . 3A-3 3A.3 Analysis and Design . . . . . . ... .. .. ..... . . 3A-3 I 3 A.3.1 Response Due to Seismic Loads ... . ... .. .. . 3A-3 3A.3.2 Deflection Criteria . . . . . ... . . . . 3 A-3 3A.3.3 Relative Movement . . .. . . .. ... . . 3A-3 3A.3.4 Allowable Stresses . . ..... . . . . .... 3A-4 3A.3.5 Connections . .... .. . . . .... .. . . . 3 A-4 APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . . . 3B-1 3B.1 Leak-Before-Break Criteria for AP600 Piping . . . ... . . .. . 3B-2 3B.2 Potential Failure Mechanisms for AP600 Piping . . . .. .. . . . . 3B-2 3B.2.1 Erosion-Corrosion Induced Wall Thinning . . ... . .... . 3B-2 3B.2.2 Stress Corrosion Cracking . . .. . . . .. . . . . 3B-3 3B.2.3 Water Hammer .. ... . . . . .. . . . . . 3B-5 3B.2.4 Fatigue . . . . . . 3B-9
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| [s]
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| 3B.2.5 Thermal Aging .. . . .. .. .... . 3B-9 L' 3B.2.6 Thermal Stratification . .... .. . . . . 3B-10 3B.2.7 Other Mechanisms . . .. . . . 3B-13 3B.3 Leak-Before-Break Bounding Analysis . . .. .... . 3B-13 3B.3.1 Procedure for Stainless Steel Piping . . . .... . 3B-13 3B.3.2 Procedure for Non-Stainless Steel Piping . . . ....... . 3B-16 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . 3B-17 3B.3.4 Bounding Analysis Results .. . .. .. . .. .
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| . .. 3B-21 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe . . . . .. ... . . 3B-21 3B.5 Differences in Inspection Criteria for Class 1,2, and 3 Systems . 3B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping ... . . .... . . . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Lines 3B-21A 3B.8 Augmented In-Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators .. . . . ..... . . . 3B-21 A 3B.9 References . . . . . . . 3B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS . . 3C-1 3C.1 Reactor Coolant Loop Model Description . . . . ... . 3C-1 3C. l .1 Steam Generator Model . . ... .. 3C-1 3C.1.2 Reactor Coolant Pump Model .. .. . . . 3C-2 3C. I .3 Reactor Pressure Vessel Model . . .. . 3C-2 Q
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| V Resision: 10 WBStiligt10USB December 20,1996 vi
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| n--::
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) e1' Section Title Page l 3C.I .4 Containment Interior Building Stmeture Model . . .. ...... . 3C-3 3C.1.5 Reactor Coolant Loop Piping Model . ..... . . . . . 3C-3 3C.2 Design Requirements . .. .. .. . . . . . .. . 3C-3 !
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| 3C.3 Static Analyses .. ..... . . . . . . .... . . . . 3C-4 1
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| 3C.3.1 Deadweight Analysis . ... ... .... . . . 3C-4 !
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| 3C.3.2 Internal Pressure Analysis . . . . .. . .. . 3C-4 1 1
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| 3C.3.3 Thermal Expansion Analysis . . . .. . . . . 3C-4 3C.4 Seismic Analyses ... . ....... . . . . ... .. . ...... 3C-4 3C.5 Reactor Coolant Loop Piping Stresses ... .. . . .. . 3C-5 3C.6 Description of Computer Programs . .. . . ... .. . . 3C-5 l
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| APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED !
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| 1 ELECTRICAL AND MECHANICAL EQUIPMENT .. .. ..... 3D-1 3D.1 Purpose . . .. ...... .. . .. . . . . ... . .. 3D-2 3D.2 Scope. . .... .. .... . .... ... . ... .. . 3D-2 3D.3 Introduction .. . . .. . . . .. . . 3D-3 3D.4 Qualification Criteria . .... . .. . . . .... ... 3D-3 1 3D.4.1 Qualification Guides .. . ... . . ... . . ..... 3D-3 3D.4.2 Definitions . . . . . ... . . ... .. . . . 3D-7 I 3D.4.3 Mild versas Harsh Environments . . . .... . 3D-7 I 3D.4.4 Test Sequence . . ... . .. . . ...... 3D-8 3D.4.5 Aging . . . . . . .. . . . . .. . 3D-9 3D.4.6 Operability Time .... . .. .. .. ... 3D-12 3D.4.7 Performance Criterion ..... . . .... .. . 3D-12 l 3D.4.8 Margin .. ..... .. ... .... . . 3D-12 3D.4.9 Treatment of Failures . .. . . . . . .. . 3D-15 3D.4.10 Traceability . . . . .. . . . .. 3D-16 3D.5 Design Specifications . .... . .. . . . .. . . 3D-17
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| 3D.5.1 Normal Operating Conditions . . . . . . .. 3D-18 3D.5.2 Abnorinal Operating Conditions . .. . .. 3D-19 3D.5.3 Seismic Events . . .... . ... . 3D-20 3D.5.4 Containment Test Environment .. .. . .. 3D-20 3D.5.5 Design Basis Event Conditions . . .. . 3D-20 3D.6 Qualification Methods . .... . . . . . . . 3D-24 3D.6.1 Type Test . . . . .... .. . . .. . . . 3D-25 3D.6.2 Analysis . . ......... . .. . . . 3D-25 3D.6.3 Operating Experience . . . .... . .. . 3D-30 3D.6.4 On-Going Qualification . . ... . . . 3D-30 3D.6.5 Combinations of Methods . . . . .. . 3D-30 Revision: 10 December 20,1996 viii T Westinghouse
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| Section Title Page 3D.7 Documentation . ................ ........... ... ...... 3D-31 3D.7.1 Equipment Qualification Data Package . . . . . . . . . . . . . . . . . . . . 3 D-32 3D.7.2 Specifications . . . ...... . ......... . ....... . .. . 3D-32 3D.7.3 Qualification Program . . . . . . . . . . . . . . . . . ... . .. . . . 3D-34 3D.7.4 Qualification by Test . . . . .. ....... ........ . . . . 3D-34 3D.7.5 Qualification by Analysis ..... . ..... . . . .. . . . . 3D-37 3D.7.6 Qualification by Experience . .. ... .... ... .......... 3D-37 3D.7.7 Qualification Program Conclusions . ..... .. ..... . . . . . 3D-37 3D.7.8 Combined License Information . . . . . . . . . . . . . . .. .. . . . 3D-38 3D.8 References . ............. .... .. ........... . . . . . . . . 3D-3 8 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package ........ . 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program . . . ..... . .. .... . . . . 3D-87 B.1 Introduction . ........... . .. . ... . .. .. ...... . 3D-87 l 1
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| B.2 Objectives . . . . . ... ... ... .... .. .. . . .. .. . . . . . . 3D-87 B.3 Basic Approach . . . . . . . . . . . . . . . . . . . . . ..... . .. .. .. . . . 3D-87 B.4 Subprogram A . . .. .................... ....... ... ... 3D-88
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| (~N. B.4.1 Scope .. . . ......... ............ ....... . . . . . 3D-88 !
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| !. ) B.4.2 Aging Mechanisms . . . . . . . . .. . ... ..... . . . . . . . 3D-88 B.4.3 Time ........... .. .... ............. . . . . . . . . 3D-88 B.4.4 Operational Stresses ... ............ . . . . . . . . . . . 3 D-89 B.4.5 External Stresses ................. ... . . . . . . . . . . . . . . 3 D- 8 9 B.4.6 Synergism . . . . . ....... . ........ ... . . . . . . . . . . . 3D-91 B.4.7 Design Basis Event Testing . . . . ...... .. . . . . . . . . . 3D-91 B.4.8 Aging Sequence . . . . . . . . .. ...... .. .. .... ... . 3D-91 B.4.9 Performance Criterion . . ... ... .. ...... . . . . . . . . 3D-91 B.4.10 Failure Treatment . . . . . . . . . . . . . ... ....... . . 3D-91 B.5 Subprogram B . .. ....... .... ......... ......... ...... 3D-92 B.5.1 Scope . .. .... . ..... . . .. . 3D-93 B.5.2 Performance Criteria . . .... . .. . ... .. 3D-93 B.S.3 Failure Treatment . . . .. . . ... . . . .. . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials . . . .. . . 3D-96 C.1 Introduction .... . .... .. ... .. . .. 3D-96 C.2 Scope. . . . . . ... . .. . .... .. .. . . . 3D-97 C.3 Discussion . .. .. .. . . . .... .. . . 3D-97 C.4 Conclusions ... ...... . ... ... . ... .. . 3D-98 l C.5 References . . . ... ... . .. .. ... . 3D-98 I
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| Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . ... ....... . 3D-103 {
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| D.1 Introduction . . ........ .... .. ..... . ... 3D-103
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| ! D.2 Arrhenius Model . . ...... . . . . . ..... . . 3D-103 D.3 Activation Energy . . ....... ... ... . .. . . 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) .. . . 3D-106 i D.4.1 Normal Operation Temperature . .... ... . . 3D-106 D.4.2 Accelerated Aging Temperature . .. . . . . .. . 3D-107 D.4.3 Examples of Arrhenius Calculations . . ... .. . 3D-107 !
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| D.5 Post-Accident Thermal Aging ....... . . . ..... . .. 3D-108 D.5.1 Post-Accident Operating Temperatures . . ... . . . . . . . . . 3D-106 D.5.2 Accelerated Thermal Aging Parameters for Post-Accident l Conditions ...... ... . ... ... . 3D-109 l D.6 References .. . ..... .. . .. . . 3D-109
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| Appendix 3D-Attachment E - Seismic Qualification Techniques . .... .. .. .. 3D-115 i E.1 Purpose . . . . .... ..... .... .. ... ......... ... 3D-Il5 E.2 Definitions . . . . . . . . . . . . . ..... ...... . . ... . . . . . 3D-115 E.2.1 1/2 Safe Shutdown Eanhquake . . . . . . ... . . . 3D-115 1 E.2.2 Seismic Category I Equipment . . . . . . . .... .. . 3D-115 l
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| E.2.3 Active Equipment . . .. ..... . .. . .... .. . 3D-115 E.2.4 Passive Equipment ....... . . . . .... . . 3D-115 E.3 Qualification Methods . . . . .... ... . 3D-116
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| E.3.1 Use of Qualification by Testing . . . . . . ..... ... 3D-116 E.3.2 Use of Qualification by Analysis . 3D-116 E.4 Requirements . . . . .
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| . ....... . .. .. . . . ... . 3D-Il7 E.4.1 Damping . . .. .. .. . .. . . . ..... . 3D-Il7 l E.4.2 Interface Requirements . . ... . .. . 3D-117 E.4.3 Mounting Simulation . . . . . . . .. . . . .... . 3D-118 E.4.4 1/2 Safe Shutdown Earthquake . . . . . 3D-ll8 E.4.5 Safe Shutdown Eanhquake . . .... .. . ... 3D-Il8 E.4.6 Other Dynamic Loads . . ... . . . . ... . 3D-118 E.5 Qualification by Test . . . ...... . . . . 3D-118 E.5.1 Qualification of Hard-Mounted Equipment . ... .. . 3D-119 E.5.2 Qualification of Line-Mounted Equipment . . . 3D-120 E.5.3 Operational Conditions . .... . . . ..... . . 3D-122 E.5.4 Resonant Search Testing . . .. . .. . .. 3D-123 E.6 Qualification by Analysis . . . . . . . . . 3D-123 E.6.1 Modeling .. . . ..... . . . .. .... . . 3D-124 E.6.2 Qualification by Static Analysis .. . .. . 3D-124 E.6.3 Qualification by Dynamic Analysis . . . . . . 3D-124 O
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| Revision: 10 December 20,1996 x 3 Westinghouse
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| l E.7 Performance Criteria ............. .. . ........ .... . ... 3D-126 E.7.1 Equipment Qualification by Test ... ... . . ....... . 3D-126 E.7.2 Equipment Qualification by Analysis ....... ...... . 3D-126 APPENDIX 3E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND . . . .. .. ... 3E-1 APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS . . . . . .. ..... 3F-1 1 3F.1 Codes and Standards ...... .... . ....... .. . . . 3F-1 3F.2 Loads and Load Combinations . . . . . . . . ........... .. ... .. . 3F-1 3F.2.1 Loads . ...... .. .. .. ....... .. . 3F-1 3F.2.2 Load Combinations . . . . . .. ..... . ... . . . . . 3F-2 3F.3 Analysis and Design . ........ . .. . .... . ...... . 3F-2 3F.3.1 Damping . ........ . ... .. . .. ... . . 3F-2 l 3F.3.2 Seismic Analysis .... .. . . ..... . . .. . . 3F-3 3F.3.3 Allowable Stresses . . . . . . . . . . .. . .... . ... .. . . 3F-3 3F.3.4 Connections . . . . . . ... .. .. .. .... . 3F-3 i
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| CHAPTER 4 REACTOR.. ... .... .. ...... . . .. . ..... .. 4.1-1 f') 4.1 Summary Description ...... . ... . ...... . .. . 4.1-1 t/ 4.1.1 Combined License Information . .. . .. ... ...... . 4.1-4 4.1.2 References . ............. .. ... . ... ...... .. 4.1-4 4.2 Fuel System Design . . ............... . ..... . ..... . .. 4.2-1 4.2.1 Design Basis . . . . . . . . . . . . . . . .. . ..... ... . 4.2 2 4.2.2 Description and Design Drawings . .. . .... ....... . .. 4.2-9 4.2.3 Design Evaluation . . . . . . . . . . ... ...... ... . . 4.2-20 4.2.4 Testing and Inspection Plan . . .. .. . ... .... .. 4.2-32 4.2.5 Combined License Information . ...... . .. .. . . 4.2-37 4.2.6 References . ..... . .... .. ... .. . .... . . 4.2-37 4.3 Nuclear Design . . . ..... ........ . ........ ... . 4.3-1 4.3.2 Description . . . . . . . .. . .. . . 4.3-7 4.3.3 Analytical Methods . . . . . . .. .. 4.3-39 4.3.4 Combined License Information . .. . . . . 4.3-42 4.3.5 References . ... . . . . .. .. 4.3-42 4.4 Thermal and Hydraulic Design .. . . .. . 4.4-1 4.4.1 Design Basis . . . . . . . ... .. . ... . 4.4-1 4.4.2 Description of Thermal and Hydraulic Design of the Reactor Core . . 4.4-4 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System . . . . . . .. . .. . 4.4-201 4.4.4 Evaluation . ...... . . . . . .. . . 4.4-21 4.4.5 Testing and Verification . ... . .. .. . . 4.4-30 4.4.6 Instrumentation Requirements .. . . . 4.4-31
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| -m 4.4.7 Combined License Information .. . .. . . 4.4-35
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| Section Title Page 4.4.8 References . . .. ..... .. ........ . 4.4-35 4.5 Reactor Materials ...
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| . . .... . . . .. .. .. 4.5-1 4.5.1 Control Rod and Drive System Structural Materials . ... ... 4.5-1 !
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| 4.5.2 Reactor Internal and Core Support Materials .... . . . . 4.5-3 4.5.3 Combined License Information .. ... .. .... . . 4.5-4 4.5.4 References . . . .. ..... .. .... . . ..... . . 4.5-4 :
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| 4.6 Functional Design of Reactivity Control Systems . .. . ... . . 4.6-1 4.6.1 Information for Control Rod Drive System .. ... .. .... 4.6-1 4.6.2 Evaluations of the Control Rod Drive System . .. . ... . 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System 4.6-2 l
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| 4.6.4 Information for Combined Performance of Reactivity Systems . . . 4.6-2 l 4.6.5 Evaluation of Combined Performance . . .. ...... . . 4.6-3 4.6.6 Combined License Information . . . . . . .. ....... .. . 4.6-4 l
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| Volume 4 i CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS . . . 5.1-1 l 5.1 Summary Description ......... ..... .. ........ . 5.1-1 l
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| 5.1.1 Design Bases . . . . .. . .......... . 5.1-1 l
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| 5.1.2 Design Description . . . ... ... . .... ... .. ... . 5.1 ' i 5.1.3 System Components . .... ...... . .. . . . .. . 5.1-4 5.1.4 System Performance Characteristics . . . . . . . . .. ... . . . 5.1-7 5.1.5 Combined License Information . . . . . . .... ..... . 5.1-9 !
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| 5.2 Integrity of Reactor Coolant Pressure Boundary .. . . ... . . .. . 5.2-1 5.2.1 Compliance with Codes and Code Cases . . . . .. ... .. . 5.2-1 5.2.2 Overpressure Protection . ... . .... . .. . .. . .. 5.2-2 5.2.3 Reactor Coolant Pressure Boundary Materials .... .... .. . 5.2-7 12.4 Insenice Inspection and Testing of Class 1 Components . . . . . . . 5.2-17 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary . 5.2-20 5.2.6 Combined License Information Items . . . . . 5.2-29 5.2.7 References . .. . . .. . . . . .. . .. 5.2-29 5.3 Reactor Vessel . .. .. . . . .. .. . . . ..... . 5.3-1 5.3.1 Reactor Vessel Design . . .. . ..... . . 5.3-1 5.3.2 Reactor Vessel Materials . . . . . . . . 5.3-4 5.3.3 Pressure-Temperature Limits . . . . . . 5.3-13 5.3.4 Reactor Vessel Integrity ... . . .. . . 5.3-14 5.3.5 Combined License Information . . .. . ... . 5.3-19 5.3.6 References . . . . . ... .. . . ... . . . 5.3-20 5.4 Component and Subsystem Design . . . . .. . 5.4-1 5.4.1 Reactor Coolant Pump Assembly . .. .. . 5.4-1 O
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| Resision: 10 December 20,1996 xii Westingh0USB
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| :--i Master Table of Contents O MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_aage 5.4.2 Steam Generators . . . . ... . . ........ . . . 5.4-10 5.4.3 Reactor Coolant System Piping .. .. .... . .... . . . . 5.4-23 5.4.4 Main Steam Line Flow Restriction . . . . ........ ....... . 5.4-28 5.4.5 Pressurizer . . . . . . . .... . .. .. .. .. .. .. . 5.4-29 5.4.6 Automatic Depressurization System Valves ..... ..... . . 5.4-36 5.4.7 Normal Residual Heat Removal System . ....... .... . 5.4-38 5.4.8 Valves .. ....... ... .. . . ..... . . ..... . 5.4-51 5.4.9 Reactor Coolant System Pressure Relief Devices .. . ....... 5.4-57 5.4.10 Component Supports . . . . . .... . . ... .. 5.4-60 5.4.11 Pressurizer Relief Discharge . .. ... .. .. .. ... . . 5.4-63 5.4.12 Reactor Coolant System High Point Vents . ... .. . 5.4-65 5.4.13 Core Makeup Tank . . . . . . . . . . .. .. ... ... . 5.4-68 5.4.14 Passive Residual Heat Removal Heat Exchanger . . 5.4-71 5.4.15 Combined License Information . . .. ... ... .... . . 5.4-74 5.4.16 References ............. .. . . . ......... . . . . . 5.4-74 CHAPTER 6 ENGINEERED SAFETY FEATURES . ..... .. ...... ......... 6.0-1 6.1 Engineered Safety Features Materials . .. . . . .... . .... . . . 6.1-1 A 6.1.1 Metallic Materials ..... ..... . ..... .... . .. 6.1-1 (j 6.1.2 Organic Materials . .... .. . .. ..... . . . .... 6.1-5 6.1.3 Combined License Information Items ......... . . . . . 6.1-11 6.1.4 References . ............... .... ....... .. . . . 6.1-12 6.2 Containment Systems . . . ........... . ...... .. ..... 6.2-1 6.2.1 Containment Functional Design . . .. . ... ........ ... 6.2-1 1 6.2.2 Passive Containment Cooling System .. ...... . . 6.2-20 i 6.2.3 Containment Isolation System ....... ..... ... .... . . 6.2-28 6.2.4 Containment Hydrogen Control System ........ .... . . . 6.2-378 6.2.5 Containment Leak Rate Test System . .. ... .. . . . 6.2-48 6.2.6 References . . . . . . . .... .. . .... .... . . 6.2-55 6.3 Passive Core Cooling System . . .. .. .. . . . 6.3-1 6.3.1 Design Basis . . . . . . . . . . .. . 6.3-2 6.3.2 System Design . ... .. ... . . 6.3-6 6.3.3 Performance Evaluation . 6.3-28 6.3.4 Post-72 Hour Actions . . .. . . 6.3-41 6.3.5 Limits on System Parameters . . ... . . . 6.3-41 6.3.6 Inspection and Testing Requirements . . . . .. 6.3-42 6.3.7 Instrumentation Requirements . .. . .. .. . 6.3-43 6.3.8 Combined License Information , . .. .. 6.3-48 6.3.9 References . . . . .. .. . 6.3-48 6.4 Habitability Systems . . ... . . . . 6.4-1 6.4.1 Safety Design Basis . . ... . . .. . . . 6.4-1 6.4.2 System Description . .... . . . .. . 6.4-2
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| , 6.4.3 System Operation . . . ... .. .. . . . . . 6.4-6 c :
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| l 6.4.4 System Safety Evaluation ... .... .... ... , . ,. . . . . 6.4-8 I 6.4.5 Inservice Inspection / Inservice Testing ...... . ... .... 6.4-10 I 6.4.6 Instrumentation Requirements .. .. . . . . . . . 6.4-10 6.4.7 Combined License Information . . .. . . .. . . . . . . . . . 6.4- 1 1 6.4.8 References . . . . . . . . .. ... . ... .. .... . ... . 6.4-11 6.5 Fission Product Removal and Control Systems . ..... . . . .. 6.5-1 l 6.5.1 Engineered Safety Feature (ESP) Filter Systems .. . . . . . . . . 6.5- 1 ;
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| 6.5.2 Containment Spray System . . ..... ... . . ... . 6.5-1 6.5.3 Fission Product Control Systems ........ . . .... 6.5-1 l 6.5.4 Combined License Information . . . . . . . . . 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components . . ........ .. ... 6.6-1 6.6.1 Components Subject to " amination . . .. . .. . .. 6.6-1 6.6.2 Accessibility ... .. .. . . . ........ . ... . 6.6-1 6.6.3 Examination Techniques and Procedures . . . . . .. ... . 6.6-2 6.6.4 Inspection Intervals ......... .... .... .. . .. . .. ... 6.6-3 6.6.5 Examination Categories and Requirements . . . . ... ........ 6.6-3 6.6.6 Evaluation of Examination Results . . . . . . . . . ... ... .... . 6.6-3 6.6.7 System Pressure Tests . . . . . . ....... .. ... . .... . 6.6-3 6.6.8 Augmented Inservice Inspection to Protect against Postulated Piping Failures . . ..... . ..... .. .... .... . . 6.6-3 6.6.9 Combined License Information Items . . . . . . .. .. . 6.6-4 j i
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| CHAPTER 7 INSTRUMENTATION AND CONTROLS ..... .... .... . . . . . . .. 7.1 1 l 1
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| 7.1 Introduction ......... ......... ... ..... .... .. . . .. 7.1-1 i 1
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| 7.1.1 The AP600 Instrumentation and Control Architecture . . .... . . . .. 7.1-2 1 1
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| 7.1.2 General Protection Subsystem Configuration . . . . .. . .... . 7.1-6 7.1.3 Plant Control System . . .. .... . ... ..... . . . . . 7.1 -27 l 7.1.4 Identification of Safety Criteria . . .. 7.1 32 l I
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| . 7.1.5 AP600 Protective Functions . . . . . . .... . .. .. 7.1-48 7.1.6 Combined License Information ... . .. . . . . 7.1-48 7.1.7 References . . . .. ... . .... . . . .. 7.1-49 7.2 Reactor Trip . . . ... . . . . . ... 7.2-1 l
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| 7.2.1 Description ... . .. . . . .... . . .. 7.2-14 l 7.2.2 Analyses . . . . . . . . .. . .. . 7.2-14 l 7.2.3 Combined License Information . .. .. . . . 7.2-17 7.2.4 References ..... . . . . 7.2-17 7.3 Engineered Safety Features . . . . ... . .. . .. . .... . 7.3-1 7.3.1 Description .. .. .. . ... . . . . ... 7.3-1 7.3.2 Analysis for Engineered Safety Features Actuation . . . . . . . 7.'2 -19 7.3.3 Combined License Information . . ... .. . . . 7.3-22 7.4 Systems Required for Safe Shutdown . . . . . . . . ... 7.4-1 Revision: 10 December 20,1996 xiv [ WeSilligh00SB
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| Section Title Page 7.4.1 Safe Shutdown . . . . . . . . . . . . . . .. ..... ..... ..... .. 7.4-3 7.4.2 Safe Shutdown Systems . . . . . . ...... ... . .. .. . . . . . . 7.4-10 7.4.3 Safe Shutdown from Outside the Main Control Room . . . . . . . . . 7.4-11 7.4.4 Combined License Information . .. . .... ........ 7.4-14 7.4.5 References . . . . ....... ... . ... .. .... ... . . . . . . 7.4-14 7.5 Safety-Related Display Information .. .. ..... .... . .. . 7.5-1 7.5.1 Introduction ..... . ........... .. .. . . ... . . 7.5-1 7.5.2 Variable Classifications and Requirements . ... . . ..... .... 7.5-1 7.5.3 Description of Variables . .. ... . . .. . . ..... .. . 7.5-9 i 7.5.4 Processing and Display Equipment . .. .. .... ..... .. . 7.5-11 ;
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| 7.5.5 Combined License Information .. ... . .... . . . . . . . . 7.5- 13 7.6 Interlock Systems Imponant to Safety . . . . . . . .... .... .......... 7.6-1 7.6.1 Prevention of Overpressurization of Low-Pressure Systems . . . . . 7.6-1 7.6.2 Availability of Engineered Safety Features . . . .... . . .. 7.6-2 7.6.3 Combined License Information . . . . . . .. .... 7.6-5 7.7 Control and Instrumentation Systems . . . . . . ... .. .. ..... . 7.7-1 7.7.1 Description .. . .... .. . ... . .. .... .. ... . . 7.7-2 7.7.2 Analysis . ........ .... . . . . . ........... . 7.7-20 77 7.7.3 l
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| Combined License Information . . . .. . . ..... . . 7.7-21 (v)
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| Volume 5 !
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| CHAITER 8 ELECTRIC POWER l
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| ... . ..... . ... ...... ... . 8.1-1 -
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| 8.1 Introduction ............. ......... . . ............ . 8.1-1 l 8.1.1 Utility Grid Description .... . .......... .. . 8.1-1 l 8.1.2 Onsite Power System Description . ... ...... ..... 8.1-1 8.1.3 Safety-Related Loads . ..... . .. ....... 8.1-2 l 8.1.4 Design Basis . . . . ... . . . . .. ... 8.1-2 8.1.5 Combined License Information ... .. . .. ...... . 8.1-5 8.2 Offsite Power System ...... . .. . ... . .... . 8.2-1 8.2.1 System Description . ....... .. . . . . 8.2-1 8.2.2 Conformance to Criteria ..... . .... . . .... . .. 8.2-2 8.2.3 Standards and Guides . . .. . . . .... .... . 8.2-2 8.2.4 Combined License Information for Offsite Electrical Power . .. . 8.2-2 8.2.5 References ..... . ... . . . .. . 8.2-2 8.3 Onsite Power Systems . . . .. . . .... . .. . .. 8.3-1 8.3.1 AC Power Systems .... . . .. . . 8.3-11 8.3.2 DC Power Systems . ..... . .. .. . . ... . . 8.3-13 8.3.3 Combined License Information for Onsite Electrical Power . . 8.3-21 8.3.4 References . . . ... .. .. . 8.3-22 O
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page CHAPTER 9 AUXILIARY SYSTEM 5 . . . . . . . . . . . . .. ..... . . . . . 9.1-1 9.1 Fuel Storage and Handling . . . . . . . ..... .. . ... . ... . 9.1-1 9.1.1 New Fuel Storage . . . . . . . . ..... ..... ..... 9.1-1 9.1.2 Spent Fuel Storage . . . . . .. . ... . .. . 9.1-5 9.1.3 Spent Fuel Pool Cooling System . . .. ... . .. 9.1 10 9.1.4 Light Load Handling System (Related to Refueling) ... ... 9.1-21 9.1.5 Overhead Heavy Load Handling Systems . . . . . . ... . 9.1-34 9.1.6 Combined License Information for Fuel Storage Handling . .. 9.1-40 9.1.7 References . ....... ... . . . . .. . . 9.1-40 9.2 Water Systems . . . . . . . . . . . . . . .. . . .. . . . . . . . 9.2-1 9.2.1 Service Water System . . . . .. . . ... .. ... ..... 9.2-1 9.2.2 Component Cooling Water System . . ... ... . .. ... . 9.2-7 9.2.3 Demineralized Water Treatment System . ... .. . . . . 9.2 16 9.2.4 Demineralized Water Transfer and Storage System . . . ... 9.2 20 9.2.5 Potable Water System . .. .. . .... ....... . .. 9.2-25 9.2.6 Sanitar/ Drainage System . .. . .. .. . 9.2-28 9.2.7 Central Chilled Water System .. . . ..... . . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . . . . . . . . 9.2 36 9.2.9 Waste Water System . . . . ......... . .. . 9.2-40 9.2.10 Hot Water Heating System . .. . . ... . .. . . 9.2-44 9.2.11 Combined License Information . . . . . . ... . . . . 9.2-47 9.2.12 References .. ...... .... . . . ...... . . 9.2-48 9.3 Process Auxiliaries . . ...... . ... .. ..... .. . . . 9.3-1 9.3.1 Compressed and Instrument Air System . ..... . . . . . 9.3-1 9.3.2 Plant Gas System . . . . . ... . . . .. 9.3-7 9.3.3 Primary Sampling System . . .... ... ....... . . . 9.3-10 ,
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| 9.3.4 Secondary Sampling System . .... . .. . 9.3-15 !
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| 9.3.5 Equipment and Floor Drainage Systems .. . . . . . 9.3-17 I 9.3.6 Chemical and Volume Control System . . . . 9.3-22 I 9.3.7 Combined License Information . 9.3-43 l
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| 9.3.8 References . .. .. . ... . . 9.3-43 l l
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| Volume 6 9.4 Air-Conditioning. Heating, Cooling, and Ventilation System .. . . 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System .. . . 9.4-1 l 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System 9.4-15 9.4.3 l
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| Radiologically Controlled Area Ventilation System . . . 9.4-26 9.4.4 Balance-of-Plant Interface . .. . . . . 9.4-36 9.4.5 Engineered Safety Features Ventilation System . . 9.4-36 O
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| ,a l b MASTER TABLE OF CONTENTS (Cont.) I Section Title Page l 9.4.6 Containment Recirculation Cooling System . . . . . . .... ... . 9.4-36 9.4.7 Containment Air Filtration System . . ....... ... . . . . . . . . 9.4-41 9.4.8 Radwaste Building HVAC System .. ............ . . . . . . 9.4-49 9.4.9 Turbine Building Ventilation System .. ..... .. .. .. . . 9.4-54 9.4.10 Diesel Generator Building Heating and Ventilation System .. .. . 9.4-59 9.4.11 Health Physics and Hot Machine Shop HVAC System .... . . 9.4-65 9.4.12 Combined License Information . . . . . ..... . .. . 9.4-70 9.4.13 References . . . .. . . . . ... .. . . . . . . . 9.4-70 9.5 Other Auxiliary Systems . ... ..... .. ............ ... . . 9.5-1 9.5.1 Fire Protection System .. . 9.5-1 l
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| 9.5.2 Communication System ... .... .. ... .. .. . . . . . 9.5-14 '
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| 9.5.3 Plant Lighting System . . ...... ........ .. . . . 9.5-18 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System .... . . 9.5-21 9.5.5 References . . .... ...... . .......... ... . . 9.5-27 l APPENDIX 9A FIRE PROECTION ANALYSIS .. . ... . . . . . . . 9A-1 l i
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| 9A.1 Introduction . . . . .... .... . . . . . .. . ... . . 9A-1 l 9A.2 Fire Protection Analysis Methodology . . . . .. . . .... . . 9A-1 !
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| p 9A.2.1 Fire Area Description . . . . . ..... .. .. ... .. . . . . 9 A- 1
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| () 9A.2.2 Combustible Material Survey .. . ... ... .. .. ..... . 9A-2 9A.2.3 Fire Severity Categorization . . . .. ... ............ . . . . . . 9 A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations ...... .. ..... .. . .......... .. . 9A-2 !
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| 9A.2.5 Fire Protection Adequacy . . . . . ... ....... .. .. . . 9A-3 )
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| 9A.2.6 Fire Protection System Integrity . . . . . . ... . ..... . . 9A-4 9A.2.7 Safe Shutdown Evaluation . .. . . .... .. . ...... . . . 9A-4 9A.3 Fire Protection Analysis Results ... . . . ... ...... . .. 9A-8 9A.3.1 Nuclear Island . . . . ... ..... ... .... . .. 9A-9 9A.3.2 Turbine Building .... . ... . ... ... . . 9A-61 9A.3.3 Yard Area And Outlying Buildings . . . . . . . 9A-72 9A.3.4 Annex I and II Buildings . . . . .. . .... . . . 9A-72 9A.3.5 Radwaste Building . . . . . . . . 9A-88 9A.3.6 Diesel Generator Building . . . .. ... . .... . . . 9A-90 9A.3.7 Special Topics . . ... ... .. ... . 9A-94 9A.4 References . . .. . . .. . . 9A-97 Volume 7 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM ..... . . . 10.1-1 10.1 Summary Description ... . ... .. .. . ... .. ... 10.1-1 10.1.1 General Descriptionn . . ... . . . . ... .... . 10.1-1 10.1.2 Protective Features .. .. .. .. . . . .. .. 10.1-2 Revision: 10 3 WB5ti!)gt10llSe xvii December 20,1996
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| 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . 10.1-4 l 10.2 Turbine-Generator . . ... . . .. .. ...... ... . 10.2-1 l 10.2.1 Design Basis . ..... . . . .. .. .... 10.2-1 ]
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| 10.2.2 System Description . .. . .. .. ... . 10.2-1 l 10.2.3 Turbine Rotor Integrity ... .. . . . .... . . 10.2-11 10.2.4 Evaluation . . . . .... ... . .. . . . . 10.2-17 10.2.5 Instrumentation Applications . .. . . . . . .. 10.2-17 10.2.6 Combined License Information on Turbine Maintenance I l and Inspection . . . ... .. . . . ... ..... 10.2-19 10.2.7 References . .... . . . ...... . .... ... . 10.2 19 10.3 Main Steam Supply System . ...... .. . . . ... . . 10.3-1 1 10.3.1 Design Basis . . .... . . . 10.3-1 l 10.3.2 System Description .. . . . . . . . .. 10.3-4 l 10.3.3 Safety Evaluation . . . . . . . ... . 10.3-10 10.3.4 Inspection and Testing Requirements .. ... . . 10.3-12 10.3.5 Water Chemistry . ...... ..... . ... . .. . 10.3-12 1 10.3.6 Steam and Feedwater System Materials . . . . ....... 10.3-16 !
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| 10.3.7 Combined License Information . .. . . .. .. . .. 10.3-17 ;
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| 10.3.8 References . . ...
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| . . .... . . . . . . ... . .... . . 10.3-17 10.4 Other Features of Steam and Power Conversion System ... . .. .. 10.4-1 10.4.1 Main Condensers . . . ... ... . . . .. . . . . 10.4-1 10.4.2 Main Condenser Evacuation System . ... ... . . 10.4-4 10.4.3 Gland Seal System . . .. . . . .. ... .. 10.4-6 10.4.4 Turbine Bypass System . . ... .. .... . .... . .. . 10.4-8 10.4.5 Circulating Water System . .. ... ...... .. 10.4-12 10.4.6 Condensate Polishing System . . . .. .. .. . . 10.4-17 10.4.7 Condensate and Feedwater Systems . ... . . . . 10.4-20 i
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| 10.4.8 Steam Generator Blowdown System . . . ....... .. 10.4-35 l
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| 10.4.9 Startup Feedwater System . .. . . . . .. . . 10.4-44 l 10.4.10 Auxiliary Steam System .... . . . ... ... 10.4-53 10.4.11 Turbine Island Chemical Feed . . . . . . 10.4-56 10.4.12 Combined License Infonnation . .. ... . . 10.4-59 10.4.13 References . . ... . . . . . . .. 10.4-59 CHAPTER I1 RADIOACTIVE WASTE MANAGEMENT . .. .. I1.1-1 11.1 Source Terms . . . ....... .. . ... . . 11.1-1 11.1.1 Design Basis Reactor Coolant Activity . . . . . .... I1.1-1 l 11.1.2 Design Basis Secondary Coolant Activity . . .. . . I1.1-3 l 11.1.3 Realistic Reactor Coolant and Secondary Coolant Activity . . . I1.1-4
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| , 11.1.4 Core Source Term .. . .. . . . .. . . .. . . 11.1-4 O
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| Section Title Page 11.1.5 Process Leakage Sources . . . .... . .. . I1.1-4 11.1.6 Combined License Information ... .. ..... .. ... . I1.1-4 11.1.7 References ... ....... . .... . ... ... . .. I1.15 11.2 Liquid Waste Management Systems . ..... . .. ... ... . I1.2-1 11.2.1 Design Basis . . .. .... .. .... . . . . . . I1.2-1 11.2.2 System Description . . . .. . .. . .......... .... . I1.2-6 11.2.3 Radioactive Releases . . . . . . . . . . . . . ..... ... I1.2-18 11.2.4 Combined License Information . ... ... .. . ...... . I 1.2-2J 11.2.5 References . .. . ... . .... ....... .... . ... 11 2-20 11.3 Gaseous Wn Management System . . . . .. . . ... I1.3-1 11.3.1 Degn Basis . . . .... . .. . .. .... .. . . . . . . 11.3-1 11.3.2 System Description . . .. ... . .. ... ... . . . 11.3-4 l 1
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| 11.3.3 Radioactive Releases . .... .. . . . . ..... I1.3-9 '
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| 11.3.4 - Combined License Information ... .. . .. I1.3-11 11.3.5 References . ...... . . . ... . .. .. . I1.3 11 !
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| 11.4 Solid Waste Management . ... . ... .... ... ... . .. I1.4-1 j 1 L4.1 Design Basis . . . .. .. .. . .... . .... .. 11.4-1 11.4.2 System Description . . .. . . . . ........ . .... . I1.4-3 l p 11.4.3 System Safety Evaluation ... .. .... ........ . . . . . . . . I 1.4- 13 l U/ 11.4.4 Tests and Inspections . .... . .. . . .... . . . ... I1.4-13 11.4.5 Quality Assurance . . . . . . . . . . . . . . . ............. ... I1.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program . . . . . .. . . .. .. I1.4-13 11.4.7 References . ... . .... .. . .. ... . 11.4-14 11.5 Radiation Monitoring ... . .. . .. .... .... ...... . 11.5-1 11.5.1 Design Basis . . . .. . .. .. . .... ... . .. . 11.5-1 11.5.2 System Description . .......... . .. .. . . .. .. 11.5-2 11.5.3 Effluent Monitoring and Sampling . . . .... ... .. . I1.5-13 11.5.4 Process and Airborne Monitoring and Sampling . . . . .. . I1.5-13 11.5.5 Post-Accident Radiation Monitoring . . . . ....... . . I1.5-14 11.5.6 Area Radiation Monitors . . . ...... . I1.5-14 11.5.7 Combined License Information . . . . . .. . . I1.5-17 CHAI7TER 12 RADIATION PROTECTION . . . . .. .. . . . . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As-Low-As-Reasonably Achievable (ALARA) . . . .. .. 12.1-1 12.1.1 Policy Considerations . . . . 12.1-1 12.1.2 Design Considerations . . . .. 12.1-2 12.1.3 Combined Liceuse Information . . . . . . 12.1-6 12.2 Radiation Sources ... . . . . . . 12.2-1 12.2.1 Contained Sources .... .... . .. . .. . 12.2-1 g 12.2.2 Airborne Radioactive Material Sources ... ... 12.2-6 ,
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| 2 Section Title j' age 12.2.3 Combined License Information . . .. ..... ........... . . 12.2-8 12.2.4 References . . . . . . . .. . .... ... ....... . .. . . . . 12.2-8 12.3 Radiation Protection Design Features . . . . . . . .. .... .. ... . . 12.3-1 i 12.3.1 Facility Design Features . .. . .. ..... .... .. . 12.3-1 12.3.2 Shielding . . . . . ... ... . . ... .. .... ..... .... 12.3-9 l 12.3.3 Ventilation . . . . . . . . . .... ... ..... . . . . . . 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instmmentation . .. . .. .... . ... . . . . 12.3 19 12.3.5 Combined License Information . . ... . . . . . 12.3-19 12.3.5 References .. .. . . . . .. . ... . .. 12.3-19 12.4 Dose Assessment ........ .. ... . .. . . ... . .. ... 12.4-1 12.4.1 Occupational Radiation Exposure . ... .. . . . . . . . . 12.4- 1 12.4.2 Radiation Exposure at the Site Boundary . . .. . .. . 12.4-4 l 12.4.3 Combined License Information . . . ... .... ... . . . . . 12.4-4 12.5 Health Physics Facilities Design . . .. . .... .. .. . .. . . . . 12.5-1 12.5.1 Objectives . . . . . .... ..... ... ...... . . . . 12.5-1 I 12.5.2 Equipment, Instrumentation, and Facilities . . . . . . . .. .. ..... 12.5-1 l 12.5.3 Other Design Features ..... .... .. . .... . . . . . . 12.5-3 i 12.5.4 Controlling Access and Stay Time .... .. .... . ... . 12.5-4 12.5.5 Combined License Information . . . . . . ......... .. . 12.5-5 :
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| Volume 8 CHAPTER 13 CONDUCT OF OPERATION .. .. ... .. . ....... 13-1 I 13.1 Organizational Structure of Applicant .. ... ....... .. .. ... 13-1 13.1.1 Combined License Information item . ,.... ....... . ... 13-1 13.2 Training .. . .... . .. .. . . ... . ...... ...... . . 13-1 13.2.1 Combined License Information item . . . . . . . . . . . .. . ... 13-1 13.3 Emergency Planning .. . . . . .. .. .. . 13-1 13.3.1 Combined License Information item . . ... . ... .... 13-2 13.4 Operational Review . .. .. . . ... .. 13-2 13.4.1 Combined License Information Item . . . . 13-2 13.5 Plant Procedures . .. ... .. .. . . 13-2 13.5.1 Administrative Procedures . .. ... 13-2 13.6 Industrial Security .... .. . ... . . .. . . . 13-3 13.6.1 Preliminary Planning . . . . ... . . . . . . 13-3 13.6.2 Security Plan . . ... . .. . . . . 13-3 13.6.3 Plant Protection System . . . . .. ... 13-3 13.6.4 Physical Security Organization . . ... . . . 13-5 13.6.5 Physical Barriers ..... . . . . . .... 13-5 O
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| 13.6.6 Access Requirements . ..... ....... . ....... . . 13-6 13.6.7 Detection Aids . . . .... . . . ............ ... 13-7 13.6.8 Security Lighting . . .. .... .. ... ...... ...... . . 13-7 13.6.9 Security Power Supply System . . . . ... ......... ...... 13-7 13.6.10 Communications ... ... . ... ... .... .. . 13-7 l 13.6.11 Testing and Maintenance . .. . . ..... ..... . . 13-8 l 13.6.12 Response Requirements . . . .. .. . . ........ . .. I3-8 13.6.13 Combined License Information Item . .. . . ...... .. .... 13-8 13.7 References . ............ .. ......... . ... ......... . 13-8 CHAPTER 14 INITIAL TEST PROGRAM ... ...... . . ............. .. 14.1-1 14.1 Specific Information to be Included in Prelimine.ry/ Final Safety Analysis Reports . . . ... .. . ... .. ...... .... ..... .. . . 14.1-1 1 14.2 Specific Information to be Included in Standard Safety Analysis Reports . . 14.2-1 l 14.2.1 Summary of Test Program and Objectives . . . ..... .. . 14.2-1 14.2.2 Organization, Staffing, and Responsibilities . . ........ . . 14.2-4 14.2.3 Test Specifications and Test Procedures ... .......... . 14.2-4 14.2.4 Compliance of Test Program with Regulatory Guides . . . . . . . 14.2-6 i
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| V 14.2.5 Utilization of Reactor Operating and Testing Experience in the Development of Test Program . .. ... ........... .. . 14.2-6 14.2.6 Use of Plant Operating and Emergency Procedures . . . . . . . . . . . . 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality . ... .......... . 14.2-7 14.2.8 Test Program Schedule . . . . . . . .. .. . .......... . . . 14.2 14.2.9 Preoperational Test Descriptions . . . . . .. ....... . . 14.2-10 14.2.10 Startup Test Procedures . . . .... .. . .... ...... . 14.2-80 14.3 Certified Design Material . . . . . . . . . .... . ....... . . . . . . 14.3- 1 14.3.1 CDM Section 1.0, Introduction . . . ........... .... . . 14.3-2 14.3.2 CDM Section 2.0, System Based Design Descriptions and ITAAC . ... .... . ..... . . ..... . 14.3-3 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC . . . . . . . .. . .... . .. .. 14.3-9 14.3.4 Cenified Design Material Section. 4.0 Interface Requirements 14.3-10 14.3.5 CDM Section 5.0, Site Parameters . . .. . ......... . 14.3-10 14.3.6 Initial Test Program .. . . . ........... . 14.3-10 14.3.7 Summary .... . .. . .. . ........ . 14.3-11 14.3.8 References . . ... .. . ... . . ... . . .. 14.3-11 14.4 Combined License Applicant Responsibilities . . . . . . . . 14.4-1 14.4.1 Organization and Staffing . . . . . . . 14.4-1 14.4.2 Test Specifications and Procedures . . . . . .. 14.4-1 14.4.3 Conduct of Test Program . . .... . . . .. . 14.4-1 14.4.4 Review and Evaluation of Test Results . . . ...... . . 14.4-1 A
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| Section Title h CHAPTER 15 ACCIDENT ANALYSES . .... ..... ........ .. . . . . . 15.0-1 15.0.1 Classification of Plant Conditions ...... ....... .. ... . . . 15.0-1 15.0.2 Optimization of Coisml Systems . . . . ... ... . . ....... . . . 15.0-5 15.0.3 Plant Characteristics ar d Initial Conditions Assumed in the Accident Analyses . . . . . . . ..... ...... ..... . . . . . 15.0-5 15.0A Reactivity Coefficien s Assumed in the Accident Analysis . . .. . . 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics . . . . . . .. . . . . 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses . . . 15.0-8 15.0.7 Instrumentation Drift and Calorimetric Errors. Power Range Neutron Flux . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . . ... . . .. ....... . . . . . 15.0-10 15.0.10 Residual Decay Heat .......... .... . .... ... . . ... 15.0-10 15.0.11 Computer Codes Utilized . . . ... . ..... .... ..... . .. . 15.0-11 15.0.12 Component Failures . . . ......... .... . . ... . ....... 15.0-13 15.0.13 Operator Actions . . . . . ...... .... . . . .. .. .. . . . 15.0-14 15.0.14 Combined License Information . . . ..... ....... . .. . . 15.0-14 15.0.15 References . . . . . . ........ .... . . ....... ... . .... 15.0-14 15.1 Increase in Heat Removal from the Primary System . . ................ 15.1-1 15.1.1 Feedwater System Malfunctions that Result in a Decrease in Feedwater Temperature . ..... .. ..... . . .... . . 15.1-1 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow . . . .. ........ . . .. . ...... ... . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow . . . ... . . . . . . . . 15.1 -5 15.1.4 Inadvertent Opening of a Steam Generator Relief or Safety Valve . . . 15.1-8 15.1.5 Steam System Piping Failure . . . ....... . .. . . .. . 15.1-11 15.1.6 Inadvertent Operation of the Passive Residual Heat Removal Heat Exchanger . . . . . . . .... ... ... .. ... 15.1-20 15.1.7 Combined License Information . . . . . . .. . ... .. 15.1-24 15.1.8 References . ..... . .. . .. .. . . ... .. . 15.1-24 15.2 Decrease in Heat Removal by the Secondary System . . . ... .. 15.2-1 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . . .. .. . . . 15.2-1 15.2.2 Loss of External Electrical Load . . .. . . 15.2-1 15.2.3 Turbine Trip ..... . .. . . . . 15.2-3 15.2.4 Inadvenent Closure of Main Steam Isolation Valves . 15.2-7 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries . . .... . . 15.2-8 15.2.7 Loss of Normal Feedwater Flow . . . . . .... . . . 15.2-12 15.2.8 Feedwater System Pipe Break . .. . 15.2-16 15.2.9 Combined License Information .... . .. .. . 15.2-21 Oll Revision: 10 l December 20,1996 xxii 3 Westingh00Se l 1
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| 15.2.10 References . . . . . .... . .. .. .. .. ..... .. 15.2-21 I 15.3 Decrease in Reactor Coolant System Flow Rate . .... .... ... . 15.3-1 !
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| 15.3.1 Partial Loss of Forced Reactor Coolant Flow . . .. .. ... . . 15.3-1 I 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . . . . . . .. . . . 15.3-3 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . . . . . . .... 15.3-5 '
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| 15.3.4 Reactor Coolant Pump Shaft Break . . ... . .. ......... 15.3-10 15.3.5 Combined License Information . . . . . . . . ..... ..... .. 15.3-10 15.3.6 References . . . . . . . . . . . . . . .. . .... . . . 15.3-11 15.4 Reactivity and Power Distribution Anomalies . . . . .. .. . .. 15.4 !
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| 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical or Low-Power Startup Condition . ...... ... . 15.4-1 !
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| 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal I at Power . . . . . . . . . . . .. ........ .. .......... . . . 15.4-5 l 15.4.3 Rod Cluster Control Assembly Misalignment (System i Malfunction or Operator Error) . ........ ........ . 15.4-11 15.4.4 Startup of an Inactive Reactor Coolant Pump at an Incorrect Temperature . . . . . . ....... .. . .. .. .. ..... .... 15.4-17 15.4.5 A Malfunction er Failure of the Flow Controller in a Boiling ra Water Reactor Loop that Results in an Increased Reactor bl Coolant Flow Rate . . . . ... ..... . .... ... . . 15.4-19 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant ...... . .. . . ........... . . 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position . . ........ . .. .. ........... 15.4-25 15.4.8 Spectrum of Rod Cluster Control Assembly Ejection Accidents . . 15.4-28 15.4.9 Combined License Information .............. ........ .. 15.4-39 15.4.10 References . . . . . ....... .... ...... . . . 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory . . . .. . . 15.5-1 15.5.1 Inadvenent Opera. ion of the Core Makeup Tanks (CMT) During Power Operation . . . . .. . .. .. ... . ... . 15.5-1 15.5.2 Chemical and Volume Contre! System Malfunction That Increases Reactor Coolant Inventory . . ... .. .. . 15.5-4 15.5.3 Boiling Water Reactor Transients . . . .. .. .. 15.5-8 15.5.4 Combined License Information . . .. . . ... . 15.5-8 15.5.5 References . . . . . . ... .. . .. .. . .. 15.5-8 15.6 Decrease in Reactor Coolant Inventory . . . . . .. . 15.6-1 15.6.1 Inadvertent Opening of a Pressurizer Safety Valve or Inadvertent Operation of the ADS . .... . 15.6-1
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| Section Title h 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . . . .. .. .... ............ ... .. . . 15.6-4 15.6.3 Steam Generator Tube Rupture . ... . .... . .... . 15.6-5 15.6.4 Spectmm of BWR Steam System Piping Failures Outside of Containment . . . . . .. .. 15.6-15 ;
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| 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . . . . . ..... ... . . 15.6-15 15.6.6 References . . . . ..... .. . . .. ...... ... . 15.6-64 15.7 Radioactive Release From a Subsystem or Component . ..... ... 15.7-1 15.7.1 Gas Waste Management System Leak or Failure .... ..... 15.7-1 l 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ....... . . . ...... ... .. 15.7-1 l 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure ... . .... . .. .. . . .... . 15.7-1 l 15.7.4 Fuel Handling Accident . . ... ..... . ... . . . . . . . 15.7-1 l 15.7.5 Spent Fuel Cask Drop Accident .... .. ..... . . . . 15.7-6 l
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| 15.7.6 Combined License Information . .. . .... .. .. . . 15.7-6 '
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| 15.7.7 References . . ...... .. ........ . . .. . ... . 15.7-7 15.8 Anticipated Transients without Scram . . .. . ... .. . . 15.8-1 15.8.1 General Background . ... ...... . . . . ... ..... 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . ... .. . 15.8-1 15.8.3 Conclusion . . . . ...... . .. . ... .. .. . . . 15.8-1 15.8.4 Combined License Information . . . . . . ......... ..... .. 15.8-1 15.8.5 References . .. ...... ....... ......... . . . 15.8-1 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS .... .. 15A-1 15A.) Offsite Dose Calculation Models . .. .. . . . 15A-1 15 A.l .1 Immersion Dose Models . . . . . . . . 15A-1 15A.I .2 Inhalation Dose (Committed Effective Dose Equivalent) ... . 15A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) . . 15A-2 15A.2 Main Control Room Dose Models . . . .. .. ..... . .. 15A-2 15A.2.1 Immersion Dose Models . . . . . . . 15A-2 15A.2.2 Inhalation Dose . .. . . .. . . . . . . . 15 A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) . ... . . 15A-4 15A.3 General Analysis Parameters . . . . . . .. . . . .. 15A-4 15A.3.1 Source Terms . . . . . ..... .. . ... . 15A-4 15A.3.2 Nuclide Parameters . . . . . . . . . . ... 15A-6 15 A.3.3 Atmospheric Dispersion Factors . . .. . 15A-6 15A.4 References . .. ... .. 15A-6 1
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| I 9
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| Revision: 10 December 20,1996 xxiv T Westinghouse
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| Master Tcble of Contents -
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| ,7 U MASTER TABLE OF CONTENTS (Cont.) l Section Title Pajte I Volume 10 CHAITER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS . ............. ............ 16.1-1 l 16.1.1 Introduction to Technical Specifications . ......... ...... 16.1-1 i 1.0 Use and Application .. . ... ..... ..... . .. .. . 1.1-1 1.1 Definitions . . . . . ...... .. ..... ........ . 1.1 -1 1.2 Logical Connectors . ... ...... ... ..... 1.2-1 1.3 Completion Times . . . .. . ... . . ..... . 1.3-1 !
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| 1.4 Frequency . . . . ........ .. ... .. ... . . . . 1.4-1 2.0 Safety Limits (SLs) . . ..... ...... ........ ...... . 2.0-1 l 2.1 SLs . . . . . . . . . ..... .... . ........... 2.0-1 2.2 SL Violations . . . .. ..... ............... 2.0-1 l 3.0 Limiting Conditions for Operation (LCO) Applicability . . ... . 3.0-1 j 3.0 Surveillance Requirement (SR) Applicabi!ity .. ... ... .... 3.0-4 3.1 Reactivity Control Systems . . . . . . . . ....... ... . . . .. 3.1-1 3.1.1 Shutdown Margin (SDM) . . . . . . .... ... . . . .. . 3.1-1 3.1.2 Core Reactivity . . . . .... ... ..... ...... . 3.1-2 i fq 3.1.3 Moderator Temperature Coefficient (MIC) .. . . . . . . . 3.1-4 j C/ 3.1.4 Rod Group Alignment Limits . . . . . .... .. .. . . 3.1-6 j 3.1.5 Shutdown Bank Insertion Limits . . . . . . ... . . . . . . 3.1-11 3.1.6 Control Bank Insertion Limits .... .. ......... 3.1-13 3.1.7 Rod Position Indication . . . . . . . . . . . . . . . . ....... 3.1 16 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . , . . . . . . . . . . 3.1-18 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves ..... . . 3.1-20 3.2 Power Distribution Limits . . . . . . . . .... .... .. ... .. 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fo (Z)) j (FqMethodology) . . . ........ . .. . . 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) . ...... ...... .. . .. ... 3.2-5 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial i
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| Offset Control (RAOC) Methodology) . .... . . . 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QITR) .... . .. . . . 3.2-10 3.2.5 OPDMS-Monitored Power Distribution l Parameters . . . . . ... . . ... . .. . 3.2-14 3.3 Instmmentation . . . . . . . . . .... . .... . .. . . . ... 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation . . . .. .. . 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation . . . .... .. .. 3.3-17 3.3.3 Post Accident Monitoring (PAM) Instrumentation . . 3.3-45 3.3.4 Remote Shutdown Workstation . . . . . ..... . . . . . . 3.3-4 8
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| :A i Revision: 10
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| [ Westingh0US8 xxy December 20,19% l
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| 1 Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title ,P, age 3.4 Reactor Coolant System (RCS) . . .. ......... . 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . . . . . 3.4- 1 3.4.2 RCS Minimum Temperature for Criticality . . .. .... . 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits . . .. . 3.4-4 3.4.4 RCS Loops - Modes 1 and 2 . . . . . ... . 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . ..... . . . 3.4-7 3.4.6 Pressurizer . . . . .. . . ... . .... . .. 3.4-9 3.4.7 Pressurizer Safety Valves . .. ... ....... . 3.4-10 3.4.8 RCS Operational Leakage . .. .... . . 3.4-12 3.4.9 Minimum RCS Flow . .. . .. . .... ... . . 3.4-14 3.4.10 RCS Leakage Detection Instrumentation . . . ...... . 3.4-15 3.4.11 RCS Specific Activity . . . .. ... ... ...... . 3.4-18 3.4.12 Automatic Depressurization System (ADS) - Operating . 3.4-20 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Intact ... .. . . ... ... ......... . 3.4-22 3.4.14 Automatic Depressurization System (ADS) - Shutdown, RCS Open . .. .... . ..... .... .......... 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . . . ..... . . . . . . . . . . . . . . . 3.4-2 6 3.5 Passive Core Cooling System (PXS) . . . ... . . . . . . 3.5- 1 3.5.1 Accumulators . . . . ... . .... ....... . . 3.5-1 3.5.2 Core Makeup Tanks (CMT)- Operating ....... . ... 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . . 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . . . ... ..... ... .. . 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . . . .. . . . . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST)-
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| Operating . . . . . .. . . . . .. . ...... . . 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST)-
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| Shutdown, RCS Inventory High . . . . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low . ... .. . 3.5-18 3.6 Containment Systems . . . . .. . ... . . .. . 3.6-1 3.6.1 Containment . . . . . . . .. . . . . .. . 3.6-1 3.6.2 Containment Air Locks ... .... .. . . .... . 3.6-3 3.6.3 Containment Isolation Valves . ... ..... 3.6-7 3.6.4 Containment Pressure . . . ... .. . 3.6-12 3.6.5 Containment Air Temperature . .... . . 3.6-13 9
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| Revision: 10 December 20,1996 xxvi [ Westinghouse
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| v -
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| Master Table of Contents i
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| .*2_ _
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| f d MASTER TABLE OF CONTENTS (Cont.) i Section Title Page r 3.6.6 Passive Containment Cooling System (PCS) - Operation . 3.6-14 !
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| 3.6.7 Passive Containment Cooling System (PCS)- Shutdown . 3.6-17 l 3.6.8 Containment Penetrations . . . . . . . . . . . . . . . . . . . . . . . 3.6-19 >
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| 3.6.9 pH Adjustment . . ............... ...... . . . . 3.6-22 3.7 Plant Systems . . . . . . . . . . ................ .... . .. . 3.7-1 4
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| 3.7.1 Main Steam Safety Valves (MSSVs) ...... ... . . .. 3.7-1 3 3 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . ... .. . . 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves .
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| (MFIV and MFCV) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7-7 I 3.7.4 Secondary Specific Activity . . . . . . . . . . . . . . . . . . . . . 3.7-9 3.7.5 Spent Fuel Pool Water Level . . . . . . . . . . . . . . . . . . . . 3.7-10 3.7.6 Main Control Room Habitability System (VES) . . . . . .. . 3.7-11
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| ; 3.7.7 Stanup Feedwater Isolation and Control Valves . . . . . . 3.7-15
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| ; 3.8 Electrical Power Systems ..... . ............ .. . .. 3.8-1 3.8.1 DC Sources - Operating . ................... . . . 3.8-1
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| , 3.8.2 DC Sources - Shutdown . . . . . . . . . . . ....... ... . . 3.8-5 i 3.8.3 Inverters - Operating . . . . . . . . . . . . ............ . . 3.8-7 3.8.4 Inverters - Shutdown . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.8-9 G 3.8.5 Distribution Systems - Operating . . . . . . . . . . . . . . . . . 3.8- 1 1
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| . (d 3.8.6 Distribution Systems - Shutdown . . . . . . . . . . . . . . . . . 3.8- 13 3.8.7 Battery Cell Parameters . . . . . . . . . . . . . . . . . . . . . . . 3.8- 15 i 3.9 Refueling Operations . . . . . . . . . . . . . . . . . . . ........ . . . 3.9-1 l 3.9.1 Boron Concentration . . . . . . . . . . . . . . . . . ..... . . . . 3.9-1 1 3.9.2 Unborated Water Source Flow Paths . . . . . . . . . . . . . . . . 3.9-2 ;
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| 3.9.3 Nuclear Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . 3.9-4 l 3.9.4 Refueling Cavity Water Level . . . . . ............. .. 3.9-6 4.0 Design Features . . . . . . . . . . ........., ........... .. 4.0-1 4.1 Site ...... .. . ..................... .. .. 4.0-1 4.1.1 Site and Exclusion Boundaries . . . . . . . . . . . . . . 4.0-1 4.1.2 Low Population Zone (LPZ) . . ........ ... . . 4.0-1
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| : 4.2 Reactor Core ....... .... ......... ..... .. 4.0-1 4.2.1 Fuel Assemblies . . .. .. .... . .. .... .. 4.0-1 4.2.2 Control Rod and Gray Rod Assemblies . . . . .. 4.0-1 l 4.3 Fuel Storage . ..... .... ..... ............. . 4.0-2 4.3.1 Criticality . . . . . . . . . ..... ....... .... .. 4.0-2
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| ; 4.3.2 Drainage . .. .............. . ... . . 4.0-2 4.3.3 Capacity . . . . . . . . . . ... . .. .. . . . 4.0-2 4.4 Hydrogen Control . ..... .. ........ . ... .. . 4.0-3 4.4.1 Passive Autocatalytic Recombiners (PARS) ...... 4.0-3 5.0 Administrative Controls . . . . ... .... ..... ..... . 5.0-1 5.1 Responsibility . . . . . . . . . . . ... .. ............ 5.0-1 5.2 Organization . . . . . . . . 5.0-2 S ............. .. ......
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| J Revision: 10 T Westinghouse xxvii December 20,1996
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| s- s f Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title fage 5.3 Unit Staff Qualifications .. .. ... ...... . . 5.0-5 5.4 Procedures . . . . ... ................ . 5.0-6 5.5 Programs and Manuals . . . . ...... .. ........ 5.0-7 5.6 Reporting Requirements . . . .. .. 5.0-15 B 2.0 Safety Limits (SLs) . . ........ ... . . .. ... B 2.0-1 B 2.1.1 Reactor Core Safety Limits (SLs) ... . . . . B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pres. cure SL . . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability .... . . B 3.0-1 B 3.0 Surveillance Requirement (SR) Applicability . . .. . B 3.0-12 B 3.1 Reactivity Control Systems ......... ... . . . . B 3.1 - 1 B 3.1.1 Shutdown Margin (SDM) . . .......... B 3.1-1 B 3.1.2 Core Reactivity . . . . . ..... .. . B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . ....... B 3.1-19 B 3.1.5 Shutdown Bank Insenion Limits .... . . B 3.1-7./
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| B 3.1.6 Control Bank Insertion Limits . . . . . . . . B 3. 8 -34 B 3.1.7 Rod Position Indication . . .. ... . . . B ',.1-40 B 3.1.8 Physics Tests Exceptions - Mode 2 . . . .... B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves . . . . . . B 3.1-53 B 3.2 Power Distribution Limits . . . . ... ........ . B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (Fn (Z))
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| (FoMethodology) . ............. B 3.2-1 i B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) .... . ... .... ... . .... B 3.2-10 I B 3.2.3 Axial Flux Difference (AFD)(Relaxed Axial Offset Control (RAOC) Methodology) . . . B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . . . . . B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters . . ..... .... . .. B 3.2-28 B 3.3 Instrumentation ... . . .. ... .. ... B 3.3-1 j B 3.3.1 Reactor Trip System (RTS) Instrumentation . B 3.3-1 '
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| B 3.3.2 Engineered Safety Feature Actuation System i (ESFAS) Instrumentation . . . . . . . ... B 3.3-53 1 B 3.3.3 Post Accident Monitoring (PAM) l Instrumentation .. ..... . . . B 3.3-115 B 3.3.4 Remote Shutdown Workstation . . . B 3.3-125 B 3.4 Reactor Coolant System (RCS) .... .. . . .. B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Depanure from Nucleate Boiling (DNB) Limits . . .. . B 3.4-1 Ol Revision: 10 December 20,1996 xxviii 3 W85tirighottse
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| :6 Master Table or contents in i 't U
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| MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page B 3.4.2 RCS Minimum Temperature for Criticality . . . B 3.4-6 B 3.4.3 RCS Pressure and Temperature (P/I) Limits . B 3.4-9 B 3.4.4 RCS Loops - Modes 1 and 2 . . . . . . . . . . . . B 3.4-17 B 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . . . . . . . B 3.4-21 B 3.4.6 Pressurizer . . . . ........... .. .. . B 34-25 B 3.4.7 Pressurizer Safety Valves . . ..... ... B 3.4-28 B 3.4.8 RCS Operational Leakage .... . .... . B 3.4-32 B 3.4.9 Minimum RCS Flow ....... ... B 3.4-38 B 3.4.10 RCS Leakage Detection Instrumentation . . . . B 3.4-41 B 3.4.11 RCS Specific Activity . . . . . . . . .... . . . B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)-
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| Operating . . . ........ ... . . . . . . . B 3.4-50 B 3.4.13 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Intact . . . . . ..... ... . B 3.4-54 b 3.4.14 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Open . . . . . . . . . . . . . . B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . . . . . . . . . . . ... . . . B 3.4-60 r B 3.5 Passive Core Cooling System (PXS) . . . . . . . . . . . B 3.5-1 i ])
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| B 3.5.1 Accumulators ..... ........... . . . B 3.5-1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . . B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . . . . . . . . . ........... . B 3.5-15 B 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating .. . . B 3.5 B 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . . . . . B 3.5-24 B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating .. .......... B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST)- Shutdown, RCS Inventory High . B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low .. ..... .. .. ........ . . B 3.5-38 B 3.6 Containment Systems . .. . .. ... ... .. . . B 3.6-1 B 3.6.1 Containment . ... . ... .. .. . B 3.6-1 B 3.6.2 Containment Air Locks .. .. . . . . B 3.6-6 B 3.6.3 Containment Isolation Valves . . . . . B 3.6-13 B 3.6.4 Containment Pressure ... . .. .. B 3.6-23 B 3.6.5 Containment Air Temperature . . . . . . . B 3.6-26 B 3.6.6 Passive Containment Cooling System (PCS) - Operating . . . .. .. . . B 3.6-30 V
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| Revision: 10
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| [ Westirigt10LISO xxix December 20,1996 i
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| ! .b .
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . . . . . . . . . . .... ... B 3.6-37 B 3.6.8 Containment Penetrations . . . . . . . . . . . . . . . B 3.6-40 B 3.6.9 pH Adjustment .. . ..... . . . . . . . B 3.6-47 B 3.7 Plant Systems . . . . . . . . .... ..... .... . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . B 3.7- 1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . ... . B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) . .. . . . . . . . . . . . B 3.7- 13 B 3.7.4 Secondary Specific Activity . .. . . . . . B 3.7- 18 B 3.7.5 Spent Fuel Pool Water Level . . ... . B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability System . . . . . . . .. . . .. . ..... . B 3.7-24 B 3.7.7 Stanup Feedwater Isolation and Control Valves B 3.7-30 B 3.8 Electrical Power Systems . . . ...... ...... B 3.8-1 B 3.8.1 DC Sources - Operating . .... ....... B 3.8-1 B 3.8.2 DC Sources - Shutdown . . . . ..... ... B 3.8-11 B 3.8.3 Inverters - Operating . . . . ...... B 3.8-15 B 3.8.4 Inveners - Shutdown . . . . .. .. B 3.8-20 B 3.8.5 Distribution Systems - Operating .... . . B 3.8-24 B 3.8.6 Distribution Systems - Shutdown . . . . . . . . . . B 3.8.33 B 3.8.7 Battery Cell Parameters . .......... . . B 3.8-37 B 3.9 Refueling Operations . ... .. . .. . ..... B 3.9-1 ,
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| B 3.9.1 Boron Concentration ... .. ..... . . . . B 3.9-1 B 3.9.2 Unborated Water Source Flow Paths . . . . . . B 3.9-5 B 3.9.3 Nuclear Instrumentation . . . . . . ......... B 3.9-8 B 3.9.4 Refueling Cavity Water Level . ..... . . . B 3.9-11 Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM . .. . .. . 16.2-1 16.2.1 Introduction . . . . . . . . . . .. ... .... .. . 16.2-1 16.2.2 Scope ... ... . . .. . .. . . . . 16.2-1 16.2.3 Design Considerations . ..... . .. . .. .... . . 16.2-1 16.2.4 Relationship to Other Administrative Programs ... . . . 16.2-2 16.2.5 The AP600 Design Organization . . . . .... . . . 16.2-2 16.2.6 Objective . . . . . . . . .. ..... . . ... .. . . 16.2-3 16.2.7 D-RAP, Phase I .. .. ... ... . . . . . 16.2-4 16.2.8 Combined License Activities RAP .. .. .. 16.2-9 ,
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| 16.2.9 Glossary of Terms . . . . .... . . . ... . ... . . . . . 16.2 10 0
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| V MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Eage 1
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| 16.2.10 References . . . . . . . . ...... .. . .......... .. . 16.2-11 CHAPTER 17 QUALITY ASSURANCE . . . . ......... .. .......... ... 17.1-1 17.1 Quality Assurance During the Design and Constmetion Phases . . .... . . 17.1-1 17.2 Quality Assurance During the Operations Phase . ...... .... . .. .. 17.1-1 !
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| 17.3 Quality Assurance During Design, Procurement, Fabrication, Inspection and/or Testing of Nuclear Power Plant Items and Services . . ..... . . . . . 17.1 - 1 17.4 Combined License Information Items .. ...... .. . . . . . . 17.1-2 ;
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| 17.5 References . . . . ......... ...... .. .. ... .... . . . . . . . . 17.1 -2 I CHAPTER 18 HUMAN FACTORS ENGINEERING . . . . . . . . . . . . . ... ..... . . . 18.1-1 l 18.1 Overview . . . .. . . .... ..... ... ... .. .. ... 18.1 - 1 18.1.1 References . . .... ........... ... .. . . . . . 18.1 -4 18.2 Human Factors Engineering Program Management .... .... . . . 18.2-1 18.2.1 Human Factors Engineering Program Goals, Scope, Assumptions, and Constraints . . . . . . . . . .......... . .... 18.2-1 l 18.2.2 Human System Interfaces Design Team and Organization ..... . 18.2-4 18.2.3 Human Factors Engineering Processes and Procedures . . . . . . . . . . I8.2-11 l 18.2.4 Human Factors Engineering Issues Tracking . . . . . . . . . . 18.2-17
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| y 18.2.5 Human Factors Engineering Technical Programs and j
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| Milestones . .... ...... ... ... . . . ...... 18.2.18 l 18.2.6 Combined License Information . . ...... .... ... . . . 18.2-19 ,
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| 18.2.7 References . . . ...... ..... ... ..... ........... 18.2-19 l 18.3 Operating Experience Review . ..... . .. ..... ... .. .. . I 8.3- 1 18.3.1 Combined License Information . . . . . .. . .. ...... ... . 18.3-1 ;
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| 18.3.2 References . . . .. ........... .. . . ............ 18.3-1 18.4 Functional Requirements Analysis and Allocation ... .. . . . 18.4-1 18.4.1 Combined License Infomiation . . . . . .. ... . .. . . 18.4-2 18.4.2 References .. . . ..... .... . ..... .... . . 18.4-2 18.5 AP600 Task Analysis Implementation Plan .. .... .. ... . . .... 18.5-1 18.5.1 Task Analysis Scope . ....... . . . . .... . . . . 18.5-1 18.5.2 Task Analysis Implementation Plan .... .. .... . 18.5-2 18.5.3 Job Design Factors .. . ... . . ... .. 18.5-5 18.5.4 Combined License Information Item . . . 18.5-5 18.5.5 References . .. . .. . .. . . 18.5-5 18.6 Staffing . .. . ... . . . .. 18.6-1 18.6.1 Combined License Information Item . .. . .. . 18.6-1 18.6.2 References . . .. . ... . ... .... .. 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering 18.7-1 18.7.1 Combined License Information . . . .. . .. ..... . I 8.7-1 18.7.2 References . .... ...... .. .. . . . 18.7-1 18.8 Human System Interface Design .... . . . . .. . . I8.8-1 i o)
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| _ I jj Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_aage 18.8.1 Implementation Plan for the Human System Interface Design ...... 18.8-3 l 18.8.2 Safety Parameter Display System (SPDS) ....... ... ..... I8.8-11 18.8.3 Operation and Control Centers . . . . . ....... .. ....... 18.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Ponion of the Plant . . .... ... .... .. .... . ..... 18.8-20 ,
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| 18.8.5 Combined License Information . . . . ... .. .. . 18.8-23 l 18.8.6 References . ... . ... .. ....... . . .. .. ... 18.8-23 18.9 Procedure Development . ....... .. . . ........ . . . ... I8.9-1 18.9.1 Combined License Information . ...... .. ...... ... 18.9-1 18.9.2 References . ...... .. .. . . . . .. .... I8.9-1 18.10 Training Program Development .. . .... . . ... . .... . I8.10-1 18.10.1 Combined License Information . . . ... . ..... 18.10-1 18.10.2 References ..... ....... . .. .. . . ... I8.10-1 18.1i Human System Interface Design Test Program .. ... .. .. . 18.11-1 18.11.1 Combined License Information . .. ... .. . ... 18.11-2 18.11.2 References . . . . . . . . . . .. . . .. .. .. . ....... 18.11-2 18.12 Displays, Alarms, and Controls . . ..... . . ... .. .. . ...... 18.12-1 18.12.1 Inventory of Displays, Alarms, and Controls . . . ... ..... 18.12-1 18.12.2 Minimura Inventory of Main Control Room Fixed Displays, Alarms, and Controls . . . . .. . ... .... . ... .. 18.12-1 18.12.3 Remote Shutdown Workstation Displays, Alarms, and Controls . . . 18.12-7 18.12.4 Combined License Information . . .. . . ... . . .... I8.12-7 18.12.5 References . . . . . . . . .. .. ....... . . .. . ..... 18.12-8 9
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| Revision: 10 December 20,1996 xxxii Westingh0USB
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| l g- l Master Table of Contents y
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| kJ l MASTER TABLE OF CONTENTS Section Title Page 1
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| Volume 1 '
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| CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT . . . . . ... 1.1-1 l 1.1 Introduction . . ........ ... . . . . .. . ........ . . 1.1 -1 l 1.1.1 Plant Location . . .... ..... ... ... .... .. .... .. . 1.1-1 4
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| 1.1.2 Containment Type . ........ . . .. ........ . . . 1.1-1 l 1.1.3 Reactor Type . . . .. . ... .. ..... . .. . ..... . 1.1-1 1.1.4 Power Output . . . . . . . . ...... ... ... .... ..... ... 1.1-1 l.1.5 Schedule . . . ... . .... . ........ . ... ........ 1.1-1 1.1.6 Format and Content . ...... ... ..... . ............. 1.1-2 1.1.7 Combined License Information . . .. . . .. . . . .. . . 1.1-3 1.2 General Plant Description . . . . . . . . . . . ... .... ......... ... . 1.2-1 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 1.2.2 Site Description . . . .... ....... .. .. .............. 1.2-15 1.2.3 Plant Arrangement Description . . . .. .... . . . . . . . . . 1.2-16 1.2.4 Nuclear Island . . . . ..... .. .. . ....... ... 1.2-17 1.2.5 Annex Building . . . . . . ... .. . . ..... ........ 1.2-24 1.2.6 Diesel Generator Building . .... . ....... .... . . . . . . . . 1.2 25 i i 1.2.7 Radwaste Building . . ...... .......... ..... .. 1.2-26 V 1.2.8 Turbine Building ........... . .. ........ ........
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| . 1.2-26 1.2.9 Combined License Information . . .............. .......... 1.2-27 1.3 Comparisons with Similar Facility Designs ... .. .......... . .... 1.3-1 1.4 Identification of Agents and Contractors . . .... ....... ..... ... 1.4-1 1.4.1 Applicant - Program Manager . .. .... ..... .. . .. 1.4-1 1.4.2 Other Contractors and Participants . . .... .... . . . . . . . 1.4- 1 1.4.3 Combined License Information ... . . . ... .. .. . 1.4-3 1.5 Requirements for Further Technical Information . .. ......,.. . . . 1.5-1 1.5.1 AP600 Safety-Related Tests . . . . . .. . ..... ... . . 1.5-1 1.5.2 AP600 Component Design Tests . . .. . ..... ....... 1.5-7 1.5.3 Combined License Infcrmatior . .. .. . . .. . . 1.5-8 1.5.4 References ....... . .. .. . . . ..... ... . 1.5-8 1.6 Material Referenced . ..... . . .. . .. ... . .. .. .. . 1.6-1 1.7 Drawings and Other Detailed Information .. . . .. . . . . . .. . 1.7-1 1.7.1 Electrical and Instrumentation and Control Drawings . . . .. . 1.7 '.
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| 1.7.2 Piping and Instrumentation Diagrams . . . . 1.7-1 1.7.3 Combined License Information . . . .. .. . ... . . 1.7-1 1.8 Interfaces for Standard Design . . ... . . ... . ... .. . 1.8-1 1.9 Compliance with Regulatory Criteria . . . . ... . . . . 1.9-1 1.9.1 Regulatory Guides . . ........ . . .. ... . .. . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) . . . 1.9-3 1.9.3 Three Mile Island Issues . . . . . . . . . . ....... ... 1.9-3
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| v Revision: 10 W W85tillgt100S6 amme I December 20,1996
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| l Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h 1.9.4 Unresolved Safety Issues and Generic Safety Issues . ...... 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues ........ . 1.9-74 1.9.6 Combined License Information . . . .... .. . . ..... 1.9-107 1.9.7 References . . ...... . .... . . . . . 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES . . . .. ... . . . 1 A-1 1 A.1 References . . . . . . .. ... . .... ... . . ... ...... l A-79 APPENDIX 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES ..... 1B-1 IB.1 Introduction .... .. . ... .. .. . . . . . . ... . 1B-1 IB.2 Summary . . . . . . .. . . .. ... ... .... . . . . IB-1 IB.3 Selection of SAMDAS . .. . ... . .. . ..... . .. IB-2 IB.4 Methodology . ... ... . .. ..... .. .. .. IB-2 1 B.4.1 Risk Reduction . .. . . ..... .. . ... .. IB-2 1 B.4.2 Capital Cost Estimates .... ...... .. . . . .. . . 1 B-3 1B.4.3 Cost Benefit Analysis . . . ... . ....... 1B-3 1B.5 PRA Release Categories . . . . ...... .. . . . ... . ... . 1B-3 IB.5.1 Release Category OK . . . .. ... ..... . .. ..... 1B-4 IB.5.2 Release Category OKP . . . ....... .. . ..... .. .. 1B-4 IB.5.3 Release Category CC . . ...... ... . ..... .... IB-5 IB.5.4 Release Category CI . .. .. ..... .... . .. .. . . . 18-5 IB.6 Total Population Dose . . . . ..... .. .. . .... . 1 B-5 1B.7 SAMDA Description and Benefit . . . . .... . .. . .. ... . 1B-6 I B.7.1 Upgrade the CVCS for Small LOCAs .. . .. . . . IB-6 IB.7.2 Filtered Vent . . . . . ...... ........ .. . ...... IB-6 IB.7.3 Locate Normal RHR Inside Containment .. . .. . .. . 1B-7 1 B.7.4 Self-Actuating Containment Isolation Valves . .. . . .. 1B-7 1 B.7.5 Passive Containment Sprays .. . .. . . .... IB-7 IB.7.6 Active High Pressure Safety Injection System . .. . 1B-7 IB.7.7 Steam Generator Shell-Side Heat Removal System . . .. . 1B-8 1B.7.8 Direct Steam Generator Relief Flow to the IRWST . .. . IB-8 I B.7.9 Increased Steam Generator Pressure Capability . . . IB-8 1B.7.10 Secondary Containment Filtered Ventilation . . 1B-8 1 B.7.11 Diversify the IRWST Discharge Valves . ... . 1B-9 1 B.7.12 Ex-Vessel Core Catcher . . . .. . . . . I B-9 1 B.7.13 High Pressure Containment Design . 1B-9 1B.7.14 Increase Reliability of Diverse Actuation System . . .. . 1B-9 IB.8 Results ... .... .. ... . .. .. .. .. 1B-9 IB.9 References . . . . . . ... . . . . .. . . 1B-11 O
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| Revision: 10 December 20,19% ii W65tiligh0USS
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| Section Title Pagte i
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| CHAPTER 2 SITE CHARACTERISTICS . . ..... . . . . . .. .. . 2-1 2.1 Geography and Demography . . . . . . . . . .. ... .. ..... ... . 2-1 2.1.1 Combined License Information for Geography and Demography . . 2-1 l 2.2 Nearby Industrial, Transportation, and Military Facilities . .. .. . 2-1 l 2.2.1 Combined License Information for Identification of Site-specific l Potential Hazards . ........ . . . .. . 2-2 1 2.3 Meteorology . ...... .. ... ... . . .. . ... 2-2 l 2.3.1 Regional Climatology . . . ... . . . . . . 2-3 l
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| . 2.3.2 Local Meteorology . . . . .. . .... ...... .. .. . 2-3 ;
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| 2.3.3 Onsite Meteorological Measurement Programs . ... . .. ... 2-3 l 2.3.4 Short-Term Diffusion Estimates . .. . . . . . ... 2-3 ;
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| 2.3.5 Long-Term Diffusion Estimates . .. . .. . ..... 2-4 2.3.6 Combined Licensed Information ... . . .. . . 2-4 2.4 Hydrologic Engineering . . . . ....... .. . ...... . .. 2-5 2.4.1 Combined License Information . .. . . . . . . ..25 2.5 Geology, Seismology, and Geotechnical Engineering .... .. ..... ... 2-6 2.5.1 Basic Geological and Seismic Combined License Information .... 2-6 2.5/ Vibratory Ground Motion . . . . . .. . . .. .. .... . 2-7
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| (] 2.5.3 Surface Faulting Combined License Information ............. 2-7
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| () 2.5.4 Stability of Subsurface Materials and Foundations . ... . . 2-8 2.5.5 Combined License Information for Stability of Slopes . . . . . . . 2-12 2.5.6 Combined License Information for Embankments and Dams . .. 2-13 1 2.5.7 References . ... ...... ..... ,.. .... 2-13 APPENDIX 2A DESIGN SOIL PROFILES . . ........ . .. ... .. . . .. 2A-1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. .. 2A-1 2A.2 Generic Soil Profiles . . ... .. . . .. ... . . .... .. 2A 2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . . 2A-4 2A.4 Free-Field Site Response Analysis . . .. . . .. . 2A-5 2A.5 2D Soil-Structure Interaction Analysis .. . . .... . 2A-7 2A.6 AP600 Design Soil Profiles . . .. . . .. . . 2A-12 2A.7 R.cferences .... . . . .. .... . . . . 2A-14 APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL PROFILES . .. .. .. ... . ... .. . 2B-1 2B.1 2D SSI Analysis Parameters and Procedures .. . .. .. ... . 2B-2 2B.l .1 Stmetural Models . . .. .. . .. . . 2B-2 2B.I.2 SASSI Foundation Models .. .. .. .. . .. . 2B-2 2B.1.3 Soil Properties for SSI Analysis . . . . .... 2B-2 2B.I .4 Input Motion . . . ... . . .. 2B-3 2B.1.5 Two-Dimensional Enveloped SSI Results . .. . 2B-3 2B.2 Design Soil Profiles . ... .... .. . . 2B-3 kJ Revision: 10 Westif@0llSe ii December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . .. . 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) .... .. ... . . . . . 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . . . 2B-5 2B.2.4 Variation of Soil Properties and 60 Percent Requirement of Free-Field Spectra at Foundation Level .. .. .... . . . 2B-5 2B.2.5 AP600 Design Soil Profiles . . . . ... . .. .. 2B-6 2B.3 Soil Profile Parametric Studies: ... . .. . ... .. .. . .. . 2B-6 2B.3.1 Depth-to-Base Rock . . . . . . . . .. .. ... .. . . 2B-7 2B.3.2 Soil Curves for Clay Material .... . . ... ...... 2B-7 2B.3.3 Poisson's Ratio for Soil above Water Table . . . ..... .... 2B-8 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site . . . . . 2B-8 2B.3.5 Idriss 1990 Soil Curves . .. . .. . . . . . . 2B-9 2B.3.5 Soil Densitys . . ....... . . . .. . . . 2B-9 2B.4 References .. ..... .. . .. . ..... .. ... .. .. 2B-9A Volume 2 APPENDIX 2C SEISMIC LATEPAL EARTH PRESSURES . .. .... .... . . . . . . 2C- 1 2C.1 2D SASSI Analysis for Seismic Lateral Eanh Pressure . . . . . .. . . . 2C-1 2C.1.1 Analysis Method . .. .. . .. ... .. . .... 2C-1 2C.I .2 Structural Models . . . . ... . . .... ... . .. . . 2C-1 2C.I .3 SASSI Foundation Models ....... . . . . 2C-1 2C.1.4 Representation of Adjacent Structures ..... .. .. . . 2C-2 2C.1.5 Input Motion . . . . .. .. . ..... . ... . . .. 2C-2 2C. I .6 Soil Properties . . . . . . . . .. . ... .. . . . . . . . . 2C-2 2C. I .7 2D SASSI Analyses Results . ..... .. ....... .. .. 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island . . . .... . ... . 2C-2 2C.3 Local Distribution of Lateral Eanh Pressure . ... .. . . . . . . . 2C-3 2C.4 References . . . . . ........ .. . . .. . . .. . 2C-4 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS . .. ...... . .. . .. . . . 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria 3.1-1 3.1.1 Overall Requirements . . .. .. .. .... . . 3.1-1 3.1.2 Protection by Multiple Fission Product Barriers . 3.1-4 3.1.3 Protection and Reactivity Control Systems .. . . . 3.1-12 3.1.4 Fluid Systems ... . . . ..... .. . . . 3.1-18 3.1.5 Reactor Containment . .. . . 3.1-30 3.1.6 Fuel and Reactivity Control . . . ... .. .. . 3.1-34 3.1.7 Combined License Information .... . . . . 3.1-37 3.1.8 References . . .. ... . . . ... ... .. 3.1-37 Revision: 10 December 20,1996 iv [ W85tingh00Se
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| Master Table of Contents v MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.2 Classification of Structures, Components, and Systems . . . .... .. .. 3.2-1 3.2.1 Seismic Classification . . . . . . . ..... ........... . . 3.2-1 3.2.2 AP600 Classification System . . . . .. . .. ........ 3.2-3 3.2.3 Inspection Requirements . ... . . .. ... .. 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System ........ .. .. . .. . ... 3.2-13 3.2.5 Combined License Information ... . .... . 3.2-16 3.2.6 References . . . . . . ... . . . ...... ..... . . 3.2-17 3.3 Wind and Tornado Loadings . . . .. . ... . ...... . 3.3-1 3.3.1 Wind Loadings . ..... ....... . ... . . . .. .. 3.3-1 3.3.2 Tornado Loadings . . . . . . . .... ...... . . ... . 3.3-2 3.3.3 Combined License Information ............ .. .... . 3.3-4 3.3.4 References . . ...... . ...... .. . . . . 3.3-4 3.4 Water Level (Flood) Design .. ... .. .. . .. . .. . ... 3.4-1 3.4.1 Flood Protection ................ .... . .. .. ... 3.4-1 3.4.2 Analytical and Test Procedures .... .. . .. 3.4-24 3.4.3 Combined License Information ... .. .. . .. . 3.4-24 3.4.4 References . ....... ..... ... . . . . .... . . 3.4-24 3.5 Missile Protection . . . . .. . . .. .. .. . . .. . . 3.5-1
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| ;d 3.5.1 3.5.2 Missile Selection and Description . . ....
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| Protection from Externally Generated Missiles . .
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| 3.5-4
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| . 3.5-13 3.5.3 Banier Design Procedures . . ... .... ....... 3.5-13 3.5.4 Combined License Information .... . .. .. .. .... 3.5-16 3.5.5 References . . . . ...... . .... .... .. . 3.5-16 ;
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| 36 Protection Against the Dynamic Effects Associated with the 1 Postulated Rupture of Piping . . . . ........ . .. . . . . . . 3.6-1 l 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment ....... .. ... .... . .. . . . 3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects ,
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| Associated with the Postulated Rupture of Piping . . .. ... . 3.6 12 l 3.6.3 Leak-before-Break Evaluation Procedures . . . . . . 3.6-31 3.6.4 Combined License Information . . . . .. . . . ... 3.6-38 3.6.5 References . . ... ....... . . . .. . . 3.6-38 l 3.7 Seismic Design . ... ... .... .... . . .. . . 3.7-1 l 3.7.1 Seismic Input .... . ..... ... .. .. . . . 3.7-1 1 3.7.2 Seismic System Analysis . . . . . . .. . 3.7-6 !
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| 3.7.3 Seismic Subsystem Analysis ..... . . 3.7-20 l 3.7.4 Seismic Instrumentation . ... . . .. 3.7-46 l 3.7.5 Combined License Information . . . .. . . 3.7-48 l 3.7.6 References . ... . . ... . .. . .. . .. 3.7-49 3.8 Design of Category I Structures . .. . .. . . . .. . . 3.8-1 3.8.1 Concrete Containment . . . . . . . . . . .. . .. . . 3.8-1 3.8.2 Steel Containment . .. . . . 3.8-1
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| [ W85tingh0USS y December 20,1996
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| Section l Title Page 1 l
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| 3.8.3 Concrete and Steel Internal Structures of Steel Containment . 3.8-16 I 3.8.4 Other Category I Structures .. .. . . .. . .. . 3.8-39 3.8.5 Foundations . . .. . . ... . . . 3.8-53 3.8.6 Combined License Information . ... .. .. 3.8-60 3.8.7 References . . . . . .. .. ... ....... . . . 3.8-60 i
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| Volume 3 3.9 Mechanical Systems and Components ... ..... . . .... .. 3.9-1 3.9.1 Special Topics for Mechanical Components . . . . . . . . ... . . 3.9-1 l 3.9.2 Dynamic Testing and Analysis . . . . ......... . . . . 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Components, Component !
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| Suppons, and Core Support Structures . ..... . ...... 3.9-45 3.9.4 Control Rod Drive System (CRDS) . . .. . .. . . 3.9-71 3.9.5 Reactor Pressure Vessel Internals . . .. . 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . . . . 3.9-89 3.9.7 Integrated Head Package . . . .. . .... . 3.9-97 3.9.8 Combined License Information . .. . ... 3.9-102 3.9.9 References ............ .. . .... . .. .. . 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment . . . . .... .. . . .. ..... . . 3.10-1 3.10.1 Seismic and Dynamic Qualification Criteria . ...... . 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Instmmentation, and Mechanical Components . . ... .. 3.10-3 ,
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| 3.10.3 Method and Procedures for Qualifying Suppons of Electrical i Equipment, Instrumentation, and Mechanical Components . ... 3.10-7 l 3.10.4 Documentation . . . . ...... .... .. . 3.10-7 3.10.5 Standard Review Plan Evaluation . . .. . . ... 3.10-7 3.10.6 Combined License Information Item on Experienced-Based Qualification . .... . ... .. . ... 3.10-8 l 3.10.7 References . . . . . .. . .. . . . 3.10-8
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| 3.11 Environmental Qualification of Mechanical and Electrical Equipment 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . 3.11-1 3.11.2 Qualification Tests and Analysis . . . .. . . . 3.11-3 i 3.11.3 Loss of Ventilation . 3.11-4 3.11.4
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| Estimated Radiation and Chemical Environment . . . . . 3.11-5 '
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| 3.11.5 Combined License Information Item for Equipment Qualification File ... .... . .. . . . . . . 3.11-5 3.11.6 References . . . . . . . . . ... . . . . 3.11-6 O
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| l l Section Title P_a_ge l APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS ... ... ... ... . . 3A-1 i 3A.1 Codes and Standards . . . . . . ... .. ... . ........ ,... . ... 3A-1 3A.2 Loads and Load Combinations . ... ... . . .. .... .. .... 3A-1 3 A.2.1 Loads ... ..... . ........ . ..... ... . . . . . . 3 A-1 3A.2.2 Load Combinations . . . .. . .... . ..... .. . 3A-3 3A.3 Analysis and Design . ............ . .. . . .. .. . ... . 3A-3 3A.3.1 Response Due to Seismic Loads . ...... .. . . ... . . 3A-3
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| ! 3 A.3.2 Deflection Criteria . . . . . . . .. . . .. .. .. .... 3A-3 l 3A.3.3 Relative Movement . . . . ......... .. . . . ... . 3A-3 l 3 A.3.4 Allowable Stresses . . .. ... . ... . . . . . .. . . . 3 A-4 3A.3.5 Connections . ......... .. . .. .. ..... . . . . . . 3 A-4 APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . . . . . . 3B-1 3B.1 Leak-Before-Break Criteria for AP600 Piping . . . . . .. . . ...... . . 3B-2 l 3B.2 Potential Failure Mechanisms for AP600 Piping . . .... ... ..... .. . 3B-2 l 3B.2.1 Erosion-Corrosion Induced Wall Thinning . . .. . . . . . . . 3B-2 l 3B.2.2 Stress Corrosion Cracking .. ... ... . .. ...... . . 3B-3 3B.2.3 Water Hammer ...... . . ... .. . . .. . .... 3B-5
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| , ,, 3B.2.4 Fatigue . ........ . .. ... . .. ... . .. . 3B-9 3B.2.5 Thermal Aging
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| ' ld) 3B.2.6 Thermal Stratification 3B-9 3B-10 3B.2.7 Other Mechanisms .. . .. ...... . . .. 3B-13 3B.3 Leak Before-Break Bounding Analysis . .... . .... . 3B-13 l 3B.3.1 Procedure for Stainless Steel Piping . . . . . .. ... .. . . . 3B-13 l 3B.3.2 Procedure for Non-Stainless Steel Piping . . . . .. . .. 3B-16 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . . 3B-17 3B.3.4 Bounding Analysis Results .. . . . .. .. .. . ... . . 3B-21 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe ... .... .... .. ... . .. 3B-21 l 3B.5 Differences in Inspection Criteria for Class 1,2, and 3 Systems . . .... 3B-21 l 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping ...... ... . .. ... ... . . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Lines . . . 3B 21 A 3B.8 Augmented In-Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators . . . . . . . .... ...... ... . 3B-21 A 3B.9 References .. ............. .. . . . . . . 3B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS . . . . . 3C-1 3C.1 Reactor Coolant Loop Model Description . . . . ... .... .... .. .. 3C-1 3C.1.1 Steam Generator Model . . . . . . . .. .. . . . 3C-1 3C. I .2 Reactor Coolant Pump Model . ... . . . . . . 3C-2 3C. I .3 Reactor Pressure Vessel Model .. . ... .... 3C-2 m
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| Section Title Pm 3C.1.4 Containment Interior Building Structure Model . ...... .. 3C-3 3C.I.5 Reactor Coolant Loop Piping Model . . . . . .. ...... ..... 3C-3 3C.2 Design Requirements . .... . .. .. ... . ...... . . 3C-3 3C.3 Static Analyses . .. . ... . .. .. . ... ... . 3C-4 3C.3.1 Deadweight Analysis . . . .. . . . . . ...... .. . 3C-4 3C.3.2 Internal Pressure Analysis . ... . . ...... . . 3C-4 3C.3.3 Thermal Expansion Analysis . . .. . . . . .. 3C-4 3C.4 Seismic Analyses .......... .... .. . . . . 3C-4 3C.5 Reactor Coolant Loop Piping Stresses . . . . ... . . . .. . 3C-5 3C.6 Description of Computer Programs ... ... . .... .. . 3C-5 APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT .... ... . 3D-1 3D.] Purpose . .. ...... ... ... . .. . ....... . .. . 3D-2 3D.2 Scope.... .. . .. .. .. . .... . .... . 3D-2 3D.3 Introduction .... ... . . .... ... . . . . 3D-3 3D.4 Qualification Criteria .. . .. .... . .. 3D-3 3D.4.1 Qualification Guides . .. . . . .. ... . 3D-3 3D.4.2 Definitions . . .. ......... . . .. .. . . . 3D-7 3D.4.3 Mild versus Harsh Environments ... .. . . .. . 3D-7 3D.4.4 Test Sequence .... ... . . .. .. . 3D-8 3D.4.5 Aging . .. .... . ...... .. . .... . 3D.9 3D.4.6 Operability Time . . . .... . . . . .. . 3D-12 3D.4.7 Performance Criterion . . .... . .. .. 3D-12 3D.4.8 Margin .. ..... ... .. . .... . 3D-12 3D.4.9 Treatment of Failures . . . . . . ... . 3D-15 3D.4.10 Traceability . . . ... . ... . .. .. . 3D-16 3D.5 Design Specifications . . .. . .... . . . .. 3D-17 3D.5.1 Normal Operating Conditions . . . . ... . 3D-18 3D.5.2 Abnormal Operating Conditions . . . .. .. .. . . 3D-19 3D.5.3 Seismic Events . . . .. . .. . .. ... . 3D-20 3 D.5.4 Containment Test Environment . . . . . . 3D-20 3D.5.5 Design Basis Event Conditions . . .. . . . 3D-20 3D.6 Qualification Methods ... .. . . . . 3D-24 3D.6.1 Type Test . . .. . ..... ... ... . . .. . 3D-25 3D.6.2 Analysis . ..... . .... . . . .... . 3D-25 3D.6.3 Operating Experience .. . . . . . 3D-30 3D.6.4 On-Going Qualification ... .. . . . 3D-30 3D.6.5 Combinations of Methods .. . . . 3D-30 0
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| i Section Title Page 1
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| 3D.7 Documentation . .. ... ...... ... . .. .. .. . . . 3D-31 !
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| 3D.7.1 Equipment Qualification Data Package ..... . . 3D-32 !
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| 3D.7.2 Specifications . . ...... ... . . .. .. . . 3D-32 3D.7.3 Qualification Program . . . . ..... ..... . . . . 3D-34 3D.7.4 Qualification by Test . . . . .. ... . . 3D-34 l 3D.7.5 Qualification by Analysis .. . .. ... ...... . . . 3D-37 !
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| 3D.7.6 Qualification by Experience . . . . . . ... . . . .. . 3D-37 3D.7.7 Qualification Program Conclusions . . ..... .. ..... . . 3D-37 3D.7.8 Combined License Information . .... .... . .. . . 3D-38 3D.8 References . . . . . . ......... . . .. . ... . ... .... . 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package . .... . . 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program . . . . . . . 3D-87 B.1 Introduction . . . . . ... . ... . . . . . . . 3D-87 B.2 Objectives ..... . . ... . . . . . . 3D-87 l B.3 Basic Approach . . . . . .. . .. . .. ...... 3D-87 B.4 Subprogram A , .. . . . .. . .. . 3D-88 p B.4.1 Scope . . . .. .. . .... ....... 3D-88 h B.4.2 B.4.3 Aging Mechanisms . .
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| Time . .... ...... .
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| . 3D-88 3D-88 B.4.4 Operational Stresses . . . . .. .. .. ... .... . . 3D-89 B.4.5 External Stresses . ... . . . .. . . .. . . . . 3D-89 B.4.6 Synergism . . . .. . .. ...... .... . . 3D-91 B.4.7 Design Basis Event Testing . . ..... . . . 3D-91 B.4.8 Aging Sequence . . . . . . ... . . . ... 3D-91 B.4.9 Performance Criterion . ... .. . 3D-91 B.4.10 Failure Treatment ... .. ... . . .. .. . . 3D-91 B.5 Subprogram B ... . ...... .. . . . . . 3D-92 B.5.1 Scope . . . ... ..... . .. . . 3D-93 B.5.2 Performance Criteria . . ... . . . 3D-93 B.5.3 Failure Treatment . . ... . .. . . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials . . . 3D-96 C.1 Introduction . . .. . . . ... . . 3D-96 C.2 Scope... . . . . .. . . . .. .. . 3D-97 C.3 Discussion .. . . . ... . 3D-97 C.4 Conclusions . . .... . . . . 3D-98 C.5 References .. . . . .. . . . 3D-98 g
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| Section Title Page Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . . ..... . . . . . 3D-103 D.1 Introduction .. . . . . . ... .. .. .. . . ..... 3D-103 ,
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| D.2 Arrhenius Model . ... . . ...... .. ... . . 3D-103 i D.3 Activation Energy . .. . . . . . . . . ....... . 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) . . .. 3D-106 ;
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| D.4.1 Normal Operation Temperature .... . . . 3D-106 D.4.2
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| Accelerated Aging Temperature . .. .. ... . . . . . 3D-107 D.4.3 Examples of Arrhenius Calculations .. ... . ... . 3D-107 D.5 Post-Accident Thermal Aging .... . .... .. . ... ... 3D-108 D.5.1 Post-Accident Operating Temperatures . .... . . . 3D-108 D.5.2 Accelerated Thermal Aging Parameters for Post-Accident Conditioris . ..... ..... . .. ... ......... . . 3D-109 ,
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| D.6 References . . ..... ..... .. . .... .. . . . . 3D-109 j l
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| Appendix 3D-Attachment E - Seismic Qualification Techniques E.1 Purpose
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| .. . . . . . 3D-115 )
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| . .... . . . ... . . . . . . 3D-Il5 i E.2 Definitions . ... .. ....... .. . . . .. .. . . 3D-115 l E.2.1 1/2 Safe Shutdown Earthquake . . . . ... . .. . 3D-115 l E.2.2 Seismic Category I Equipment . . ... .... . 3D-115 !
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| E.2.3 Active Equipment . . . . ... ... . . . ... . . . 3D-115 E.2.4 Passive Equipment . . . . . . . ...... 3D-115 E.3 Qualification Methods ... . . . .. ... . . ... . . 3D-116 E.3.1 Use of Qualification by Testing . . . . . ...... . 3D-116 E.3.2 Use of Qualification by Analysis . . . .. ..... . . 3D-116 E.4 Requirements . .. .. . .. .... .. . . . . .. . 3D-117 E.4.1 Damping . . . . . .. . . . .. ... . 3D-117 E.4.2 Interface Requirements . . . . .. . . . 3D-117 E.4.3 Mounting Simulation . . .. .......... . 3D-118 E.4.4 1/2 Safe Shutdown Earthquake . . . . .. . . 3D-Il8 E.4.5 Safe Shutdown Earthquake . ... . .. .. . .. . 3D-Il8 E.4.6 Other Dynamic Loads . .. . . .... . . 3D-Il8 E.5 Qualification by Test . ... . .... .... .. .. . . . 3D-118 E.5.1 Qualification of Hard-Mounted Equipment . ... . . ... . 3D-119 E.5.2 Qualification of Line. Mounted Equipment .... ... . 3D.120 E.5.3 Operational Conditions ... .. .. .. . .. . 3D-122 E.5.4 Resonant Search Testing . . . . . . ... .. .. ... . . 3D-123 E.6 Qualification by Analysis . . .... .. . ....... 3D-123 E.6.1 Modeling . .... .. .. . .. . . . 3D-124 E.6.2 Qualification by Static Analysis . ... 3D-124 E.6.3 Niification by Dynamic Analysis . .. .. . . . 3D-124 O
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| E.7 Performance Criteria . .. ....... . ....... ...... ... 3D-126 E.7.1 Equipment Qualification by Test ... . . ........... .. . 3D-126 E.7.2 Equipment Qualification by Analysis .... .. ... .. . . 3D-126 APPENDIX 3E HIGH. ENERGY PIPING IN THE NUCLEAR ISLAND . . .... .. .. 3E-1 l APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS . . . . . . . ... . .. . 3F-1 3F.1 Codes and Standards . . . . ... . . . ... .. .. 3F-1 3F.2 Loads and Load Combinations . . . . . . . . . ..... . .... .. . . 3F-1 3F.2.1 Loads ... .. .... ... .. . . .. ..... . 3F-1 ,
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| 3F.2.2 Load Combinations ....... . . ... . .... .. .. 3F-2 l i
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| 3F.3 Analysis and Design . .. .. ... .. .. . ....... . .... . 3F-2 i 3F.3.1 Damping ... ... . .. .. .. ..... . ....... . 3F-2 3F.3.2 Seismic Analysis . . . . . .. . ... .. ...... . 3F-3 3F.3.3 A!!owable Stresses . . . . . . . . . ........... .. 3F-3 3F.3.4 Connections . . . .. . .. . .. . . .. . . .. 3F-3 CHAPTER 4 REACTOR. . . ..... .. . . .. .. . . 4.1-1 4.1 Summary Description .. .. ... . . . . .... .... . 4.1-1 C(3 4.1.1 Combined License Information . ... . . . ..... . 4.1-4 !
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| 4.1.2 References . ... . ..... . . ... . . 4.1-4 4.2 Fuel System Design . .. . ... ... ...... .. .. . 4.2-1 4.2.1 Design Basis . .. . . .... ... .. . .. 4.2-2 4.2.2 Description and Design Drawings .. ... ......... . . 4.2-9 4.2.3 Design Evaluation . . . . .. . . . . ..... .... 4.2-20 4.2.4 Testing and Inspection Plan . .. ..... . . . 4.2-32 4.2.5 Combined License Information . . . . ........ . 4.2-37 4.2.6 References .. ..... . . . . . .. .. 4.2-37 4.3 Nuclear Design ... . . . . ..... . ... .. 4.3-1 4.3.2 Description . .. . . . .. . . 4.3-7 4.3.3 Analytical Methods . ... . . . . .. 4.3-39 4.3.4 Combined License Information . . .. . . .. . 4.3-42 4.3.5 References . . . .. ...... . .. . . . 4.3-42 4.4 Thermal and Hydraulic Design . .. . .. .. ........ . . 4.4-1 4.4.1 Design Basis . . . ... . . . . ..... . . 4.4-1 4.4.2 Description of Thermal and Hydraulic Design of the Reactor Core 4.4-4 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System . . . .... ... ....... ... . . 4.4-201 4.4.4 Evaluation .. . . . . . .. . .. .. . 4.4-21 4.4.5 Testing and Verification .. . . . .. . . 4.4-30 4.4.6 Insuumentation Requirements . . . . 4.4-31 g3 4.4.7 Combined License Information . . . . . .. . 4.4-35
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| 4.4.8 References . . . .. ..... . . .. .. .. .. . . 4.4-35 4.5 Reactor Materials ....... ...... ... . . . .. ..... . 4.5-1 l 4.5.1 Control Rod and Drive System Structural Materials . .. .... 4.5-1 4.5.2 Reactor Internal and Core Support Materials . ... . .... 4.5-3 4.5.3 Combined License Information . ... . . .. 4.5-4 4.5.4 References . . . . . ... . .... . . ...... .. . . . 4.5-4 4.6 Functional Design of Reactivity Control Systems . .. ..... .. ...... 4.6-1 4.6.1 Information for Control Rod Ddve System . . ..... .. . . 4.6-1 4.6.2 Evaluations of the Control Rod Drive System ........ .. . . . . 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System ... . .. 4.6-2 4.6.4 Informauon for Combined Performance of Reactivity Systems . . . . . 4.6-2 4.6.5 Evaluation of Combined Performance ... . . . .. . .. 4.6-3 4.6.6 Combined License Information . . . .. . . . . 4.6-4 i Volume 4 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS . . .... 5.1-1 5.1 Summary Description ... . . . . . ....... . 5.1-1 5.1.1 Design Bases . . .. ..... . ... ...... 5.1-1 5.1.2 Design Descriptior . .. . . . .. . ...... 5.1-2 5.1.3 System Components . .. . . .. . . . . . 5.1-4 5.1.4 System Performance Characteristics . . .. . ..... 5.1-7 5.1.5 Combined License Information . .. .. . . . .. 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary . . . . . . .. .. . . . 5.2-1 5.2.1 Compliance with Codes and Code Cases . . .. . .. 5.2-1 5.2.2 Overpressure Protection . . . . . .. . .. . . 5.2-2 5.2.3 Reactor Coolant Pressure Bounoary Materials ... 5.2-7 5.2.4 Inservice Inspection and Testing of Class 1 Components ... . 5.2-17 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary 5.2-20 5.2.6 Combined License Information Items . ... . . . . . 5.2-29 5.2.7 References ..... .. . . . . . . 5.2-29 5.3 Reactor Vessel . . . .. .. .. . . . .. .. . 5 3-1 5.3.1 Reactor Vessel Design .. ... . . .. . . . . . 5.3-1 5.32 Reactor Vessel Materials . . . . . .. . 5.3-4 5.3.3 Pressure-Temperature Limits ... . . . . 5.3-13 5 3.4 Reactor Vessel Integrity . . .. .... . .. 5.3-14 5.3.5 Combined License Information . . ..... . . 5.3-19 5.3.6 References . ... ..... . . . . . .. . . 5.3-20 5.4 Component and Subsystem Design . . . .. 5.4-1 5.4.1 Reactor Coolant Pump Assembly . . . . . . .. 5.4-1 0
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| Section Title P_ age 5/.2 Steam Generators . ........ . . .. .. . . 5.4-10 l 54.3 Reactor Coolant System Piping . . .... . . . . . . . 5.4-23 !
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| 5.4.4 Main Steam Line Flow Restriction .. .... . . . . 5.4-28 5.4.5 Pressurizer . .... . .... .... . .. . 5.4-29 5.4.6 Automatic Depressurization System Valves . ... ... .. . . 5.4-36 5.4.7 Normal Residual Heat Removal Sys'em .. .. ........ . . . 5.4-38 5.4.8 Valves . .. ....... . .... .. .... ..... . 5.4-51 5.4.9 Reactor Coolant System Pressure Relief Devices . ... .... . 5.4-57 5.4.10 Component Supports . . ... . .. . . . . . . 5.4-60 5.4.11 Pressurizer Relief Discharge .. .. . . .. . ...... . 5.4-63 1 5.4.12 Reactor Coolant System High Point Vents . .. 5.4-65 ;
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| 5.4.13 Core Makeup Tank . . ... . .. . .. ... . ... .. .. . 5.4-68 l 5.4.14 Passive Residual Heat Removal Heat Exchanger .. .... . .. 5.4-71 5.4.15 Combined License Information . . . . . . 5.4-74 5.4.16 References . ... .. ....... ... .. .. . .. 5.4-74 CHAPTER 6 ENGINEERED SAFETY FEATURES . . .. .. . . ... ... . . 6.0-1 6.1 Engineered Safety Features Materials .. . .. .. .. .. . .. . 6.1-1 (3 6.1.1 Metallic Materials . . . . . . . . . . . . . ... .. .. 6.1-1
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| () 6.1.2 6.1.3 Organic Materials . . .
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| Combined License Information Items
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| . . . . . .. ..... . . 6.1-5
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| .. . .. . ........ 6.1-11 6.1.4 References .... ... . ..... . .. . . .. .. 6.1-12 6.2 Containment Systems .. ..... . . . . . .. . 6.2-1 6.2.1 Containment Functional Design . . . ... . . ... . . . 6.2-1 6.2.2 Passive Containment Cooling System . .... . . .. . .. 6.2-20 6.2.3 Containment Isolation System . ... ... .... . . 6.2-28 6.2.4 Containment Hydrogen Control System . . .. . .... .. . 6.2-378 6.2.5 Containment Leak Rate Test System .. .. .. .. . 6.2-48 6.2.6 References .... .. ..... .... .... . .. ... . 6.2-55 6.3 Passive Core Cooling System . . .. . . .... .. 6.3-1 I 6.3.1 Design Basis . . . . .. . . .. . 6.3-2 j 6.3.2 System Design . . . . .. . 6.3-6 l 6.3.3 Performance Evaluation . .. .... ... . 6.3-28 1 6.3.4 Post-72 Hour Actions . . . .. .. .. ... . . 6.3-41 6.3.5 Limits on System Parameters . . . ... . . 6.3-41 6.3.6 Inspection and Testing Requirements . . . 6.3-42 6.3.7 Instrumentation Requirements . . . . ... .. . 6.3-43 6.3.8 Combined License Information . . . .. .. . ... . 6.3-48 i 6.3.9 References . . . . .. ... . 6.3-48 i 6.4 Habitability Systems . . .. .. . . .. . . 6.4-1 '
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| 6.4.1 Safety Design Basis . .. .... . . . . 6.4-1 6.4.2 System Description . . . . . .. .. . 6.4-2 6.4.3 System Operation . . . 6.4-6 L..)
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| G, Section Title hge 6.4.4 System Safety Evaluation .... . . ... .... .... . . 6.4-8 6.4.5 Inservice Inspection / Inservice Testing . . . . . .. . . ..... 6.4-10 6.4.6 Instrumentation Requirements . . . ... .... . . ... . . 6.4-10 6.4.7 Combined License Information . .. ... . . .. . 6.4-11 6.4.8 References . . . . . . . . . . . . ... .... . . . . . . 6.4-11 6.5 Fission Product Removal and Control Systems . . .... .. .. . . . 6.5-1 l 6.5.1 Engineered Safety Feature (ESP) Filte.r Systems ... . .. . 6.5-1 6.5.2 Containment Spray System . .. .. ... . . .. . . . . 6.5-1 :
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| 6.5.3 Fission Product Control Systems . ... . .. . ... . . . 6.5-1 I 6.5.4 Combined License Information .... . . ... . . . . . 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components . ...... .. . . 6.6-1 j 6.6.1 Components Subject to Examination . . . ..... .. . . 6.6-1 !
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| 6.6.2 Accessibility .. .... ... .. . ..... . .. ..... . .. 6.6-1 !
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| 6.6.3 Examination Techniques and Procedures ... ......... ... . 6.6-2 j 6.6.4 Inspection Intervals . . . . ... . . . . .. . . 6.6-3 ;
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| 6.6.5 Examination Categories and Requirements . . . . ........ . . . 6.6-3 6.6.6 Evaluation of Examination Results . ... .. ... .... .. . 6.6-3 6.6.7 System Pressure Tests . . . . .. ...... ...... .. 6.6-3 1 6.6.8 Augmented Inservice Inspection to Protect against Postulated l Piping Failures . . ... .. .. . 6.6-3
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| 6.6.9 Combined License Information Items . . . . . . 6.6-4 l l
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| CHAPTER 7 INSTRUMENTATION AND CONTROLS . . . .. 7.1-1 l 7.1 Introduction . . ...... .. . .. ... ...... ... ... 7.1-1 !
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| 7.1.1 The AP600 Instrumentation and Control Architecture . . . . . . 7.1-2 l 7.1.2 General Protection Subsystem Configuration . . .... .. ... . 7.1-6 7.1.3 Plant Control System . . . .. .. .. . . . .. . 7.1-27 7.1.4 Identification of Safety Criteria . . . . . . . . .. . .. 7.1 32 7.1.5 AP600 Protective Functions . . . . .. . 7.1-48 7.1.6 Combined License Information . ... . . 7.1-48 7.1.7 References .... .. . . . . ..... . . 7.1-49 7.2 Reactor Trip . . .. ........ . . ... .... . . .. 7.2-1 7.2.1 Description . . .. . . . .. . 7.2-14 7.2.2 Analyses . .......... . . . . . . 7.2-14 7.2.3 Combined License Information . . . . 7.2-17 1 7.2.4 References ... . ..... . . .. . 7.2-17 7.3 Engineered Safety Features . . . . . . . .. ... 7.3-1 7.3.1 Description . ... .... . . . . . . . 7.3-1 7.3.2 Analysis for Engineered Safety Features Actuation . . . . 7.3-19 7.3.3 Combined License Information .. ... . 7.3-22 7.4 Systems Required for Safe Shutdown . . . . . . 7.4-1 O
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| Secti1n Title Page 7.4.1 Safe Shutdown . . . . . . ...... .. ... ...... ..... . 7.4-3 7.4.2 Safe Shutdown Systems . . .. ... .. . .......... . 7.4 10 7.4.3 Safe Shutdown from Outside the Main Control Room . .. . . 7.4-11 7.4.4 Combined License Information . . . . ... . . 7.4-14 7.4.5 References . . . . ... . .. ...... . .. .... . . . 7.4-14 7.5 Safety-Related Display Information ... . . .. . .... 7.5-1 7.5.1 Introduction . . . . . . . . . . . . . . ..... . . . 7.5-1 7.5.2 Variable Classifications and Requirements ....... ..... .. 7.5-1 7.5.3 Description of Variables . . . .. .. .. .. ...... ..... . .. 7.5-9 7.5.4 Processing and Display Equipment . . . .. . ... . 7.5-11 7.5.5 Combined License Information . . ....... .. . . .. ... 7.5-13 7.6 Interlock Systems Important to Safety . . . . . . . ..... ....... ..... . 7.6-1 7.6.1 Prevention of Overpressurization of Low-Pressure Systems .. .. 7.6-1 7.6.2 Availability of Engineered Safety Features . ... . .... 7.6-2 7.6.3 Combined License Information . . ... .. .. .... . 7.6-5 7.7 Control and Instrumentation Systems . . . ... .... . . .. . 7.7-1 7.7.1 Description ... . . .... .. ... . .. ... . . 7.7-2 7.7.2 Analysis .... ...... . . ..... . .. ... 7.7-20 t' ^ 7.7.3 Combined License Information . . .. .. . .... . . 7.7-21 Volume 5 CHAPTER 8 ELECTRIC POWER . . .... . . . ... .. . . .... . 8.1-1 8.1 Introduction .. ... ...... .. . . . . . .. .. . 8.1-1 8.1.1 Utility Grid Description . . . .... .. . . ..... .. 8.1-1 8.1.2 Onsite Power System Description ... . . ..... . . . . 8.1-1 8.1.3 Safety-Related Loads . . .... .. . .. . .. . . . 8.1-2 8.1.4 Design Basis . ......... . . ... . ... . 8.1-2 8.1.5 Combined License Information . . .. . .... . 8.1-5 8.2 Offsite Power System . ... .. .. . ..... ... 8.2-1 8.2.1 System Description . . . . . . ... ... . .. . 8.2-1 8.2.2 Conformance to Criteria . . . . . . ..... . . 8.2-2 8.2.3 Standards and Guides . . . . .... . ... . ... .. 8.2-2 8.2.4 Combined License Information for Offsite Electrical Power . .. 8.2-2 8.2.5 References . . ... . . . .. . . . 8.2-2 8.3 Onsite Power Systems . . ...... . . . . . . . . 8.3-1 8.3.1 AC Power Systems .. . . . . .. ... . . 8.3-11 8.3.2 DC Power Systems . ... ... . .. . . . . .. 8.3-13 8.3.3 Combined License Information for Onsite Electrical Power . . 8.3-21 8.3.4 References . . .... . . . . 8.3-22
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| Section Title Page CHAPTER 9 AUXILIARY SYSTEMS . ........... ... . ....... . . . 9.1-1 9.1 Fuel Storage and Handling . . . . . . . . . . . .. . . . ...... .. 9.1-1 9.1.1 New Fuel Storage . . . . . .... . .......... . 9.1-1 9.1.2 Spent Fuel Storage . . . . . . . . . . . . . .. . 9.1-5 9.1.3 Spent Fuel Pool Cooling System . . . . . . . . . . ... ... . 9.1-10 9.1.4 Light Load Handling System (Related to Refueling) . .... . . . 9.1-21 9.1.5 Overhead Heavy Load Handling Systems . .... .... . 9.1-34 9.1.6 Combined License Information for Fuel Storage Handling . .. . 9.1-40 9.1.7 References . . . . . . ........... . . ..... ........ . 9.1-40 9.2 Water Systems ....... . .. . ....... ... ...... ... 9.2-1 9.2.1 Service Water System . . . . . . . ....... .. . ...... 9.2-1 9.2.2 Component Cooling Water System . . ... ... .. ... 9.2-7 9.2.3 Demineralized Water Treatment System . . .. ... ........ 9.2-16 i 9.2.4 Demineralized Water Transfer and Storage System . . . . . 9.2-20 9.2.5 Potable Water System . . . ... ... . ..... . 9.2-25 9.2.6 Sanitary Drainage System . . . . .. . .. ..... . 9.2-28 9.2.7 Central Chilled Water System . . .... . . . .. .. . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . . . .. . 9.2-36 ;
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| 9.2.9 Waste Water System . . . . . . . . . .. .. .. . . . 9.2-40 9.2.10 Hot Water Heating System ....... . . . . .. .... 9.2-44 ;
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| 9.2.11 Combined License Information . . .. .... .. . ... . 9.2-47 l 9.2.12 References .... ....... . . .... .. ... ... . 9.2-48 9.3 Process Auxiliaries .. . .... . . . . ..... . .... 9.3-1 9.3.1 Compressed and Instrument Air System .. . . ....... 9.3-1 9.3.2 Plant Gas System ... ... ... ... . .... . . 9.3-7 l 9.3.3 Primary Sampling System . . . . . .... . . . . 9.3-10 9.3.4 Secondary Sampling System . . . . . . ... .. . . 9.3-15 9.3.5 Equipment and Floor Drainage Systems . . .. . . 9.3-17 ;
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| 9.3.6 . . . 9.3-22 Chemical and Volume Control System . . . . ..
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| 9.3.7 Combined License Information . .. . ..... . . 9.3-43 9.3.8 References . . .. .. . .. .. ... 9.3-43 Volume 6 i
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| 9.4 Air-Conditioning. Heating, Cooling, and Ventilation System . .. . 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System . . . . ... . 9.4-1 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System . 9.4-15 9.4.3 Radiologically Controlled Area Ventilation System .. .... . 9.4-26 9.4.4 Balance-of-Plant Interface . . .. .. ... ... . 9.4-36 I 9.4.5 Engineered Safety Features Ventilation System .. . . . 9.4-36 O'
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| Section Title Page 9.4.6 Containment Recirculation Cooling System . . . . . . .. . ... . 9.4-36 9.4.7 Containment Air Filtration System . . . ........ ... 9.4-41 9.4.8 Rat. waste Building HVAC System ...... . .... ... . . 9.4-49 9.4.9 Tuibine Building Ventilation System . ... ... . ... ... 9.4-54 9.4.10 Dust.1 Generator Building Heating and Ventilation System . . . 9.4-59 9.4.11 Health Physics and Hot Machine Shop HVAC System . . . . 9.4-65 9.4.12 Corabined License Information . . . .. .... . . . 9.4-70 9.4.13 References . . . . .... . . .... .... . 9.4-70 9.5 Other Auxiliary Systems ... ... .... .. ... . . 9.5-1 9.5.1 Fire Protection System . . . . . . . . .... ... . . 9.5-1 9.5.2 Communication System ..... ... .. .... . ... . . 9.5-14 9.5.3 Plant Lighting System . . ... .. .. .... .... . . . . 9.5-18 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System . .. ... . 9.5-21 9.5.5 References . . .. .. ... ....... ...... . 9.5-27 APPENDIX 9A FIRE PROTECTION ANALYSIS . .. . . . ...... .... . . 9A-1 9A.1 Introduction ... . . ...... .... . .. . ... . . 9A-1 9A.2 Fire Protection Analysis Methodology .. .. . . . . . 9A-1
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| (] 9A.2.1 Fire Area Description ... .. . .. .... .. . . . 9A-1
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| (/ 9A.2.2 Combustible Material Survey . . . . . .. . .. .. .. . . . 9A-2 9A.2.3 Fire Severity Categorization . . . .. ..... .. .. 9A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations . . .... .. . . .. ... . 9A-2 9A.2.5 Fire Protection Adequacy ... ... . . ..... ... . 9A-3 9A.2.6 Fire Protection System Integrity .. .. . . . . . 9A-4 9A.2.7 Safe Shutdown Evaluation . . . . .. .. .. . .. . 9A-4 9A.3 Fire Protection Analysis Results . . . ...... . . . . . 9A-8 9A.3.1 Nuclear Island . ...... . . .. .. . . 9A-9 9A.3.2 Turbine Building .. . . . .. .... . .. . 9A-61 9A.3.3 Yard Area And Outlying Buildings . . . . . 9A-72 9A.3.4 Annex I and II Buildings . . ... .. . . . . . . 9A-72 9A.3.5 Radwaste Building . . . . . ... . . 9A-88 9A.3.6 Diesel Generator Building . . . . .... . . . 9A-90 9A.3.7 Special Topics . .. . . . ... ... . . .. 9A-94 9A.4 References . . .. . . .. .. .... . 9A-97 Volume 7 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM .. ... .. ... 10.1-1 10.1 Summary Description . . ... . . . .... . 10.1-1 10.1.1 General Descriptionn . .. .. . 10.1-1 10.1.2 Protective Features . .. . . . . . 10.1-2 Revision: 10 W85tingh0USB xvii December 20,1996
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| Section Title Page 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . 10.1-4 10.2 Turbine-Generator ... . ... . . . ... . . . 10.2-1 10.2.1 Design Basis . . ... .. ...... . . 10.2-1 10.2.2 System Description . . . .. . ... . . . .. .. .. 10.2-1 10.2.3 Turbine Rotor Integrity ... . . .. . .. . .. . 10.2-11 10.2.4 Evaluation . . ....... .. .. . . . .. . . . . . 10.2-17 10.2.5 Instrumentation Applications ... . . . .. .. 10.2-17 10.2.6 Combined License Information on Turbine Maintenance i and Inspection . . . . ...... . . ...... . . .. .. 10.2-19 10.2.7 References . . . . ... .. .... . .. .... . ... 10.2-19 10.3 Main Steam Supply System ...... .. . . . . .. . 10.3-1 10.3.1 Design Basis . .. . ... . . . . . .. .. 10.3 1 10.3.2 System Description . . .. . .... . . . ... 10.3-4 10.3.3 Safety Evaluation . . . . .. . ... 10.3-10 10.3.4 Inspection and Testing Requirements .. . .. ...... 10.3-12 10.3.5 Water Chemistry . . ... . . .. ... . ... 10.3-12 10.3.6 Steam and Feedwater System Materials . . . .. . . 10.3-16 10.3.7 Combined License Information . .... . ... . .. . 10.3-17 10.3.8 References . . . . . . .. ..... .. ... .. .. 10.3-17 10.4 Other Features of Steam and Power Conversion System . ... 10.4-1 10.4.1 Main Condensers . ... . ... .. .. . .... . 10.4-1 10.4.2 Main Condenser Evacuation System . .. . ... ...... 10.4-4 10.4.3 Gland Seal System . .... . . . . . .. ... .. 10.4-6 10.4.4 Turbine Bypass System . . . . ... .. . .. ... . 10.4-8 10.4.5 Circulating Water System . . . . . . . . . . 10.4-12 10.4.6 Condensate Polishing System . . . . . .. .. 10.4-17 10.4.7 Condensate and Feedwater Systems . . . . . . . .. . . .. 10.4-20 10.4.8 Steam Generator Blowdown System . . .... ... . 10.4-35 10.4.9 Startup Feedwater System . . . . ... . . 10.4-44 10.4.10 Auxiliary Steam System . ... ... .. . .. .. ... 10.4-53 10.4.11 Turbine Island Chemical Feed . . . . .. 10.4-56 10.4.12 Combined License Information . . .. .. . 10.4-59 l 10.4.13 References . . . . . .. . . ... . .... . 10.4-59 j CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT . . . . . . . ... . I1.1-1 l 11.1 Source Terms ... ... . . . ... . . . . I1.1-1 l 11.1.1 Design Basis Reactor Coolant Activity . . . . .... . I 1.1-1 11.1.2 Design Basis Secondary Coolant Activity .. .. . . 11.1-3 11.1.3 Realistic Reactor Coolant and Secondary Coolant Activity . . 11.1-4 11.1.4 Core Source Term .. .. .. .. . . . . I1.1-4 )
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| i 11.1.5 Process Leakage Sources . .... ... .... . I1.1-4 11.1.6 Combined License Information . . . . .. . ...... . . . 11.1-4 11.1.7 References .... . .. .... . . .. . .. . 11.1-5 11.2 Liquid Waste Management Systems . . .. . ...... . 11.2-1 11.2.1 Design Basis .. ... . ... . . . . .... . . .. I1.2-1 11.2.2 System Description . . . . . . ... .. ... . ..... ... I1.2-6 11.2.3 Rad 6 active Releases . ....... . ... .. .. .. . .. 11.2-18 11.2.4 Combined License Information . . . .. .... .. .. I1.2-20 l 11.2.5 References . ... . . .... . ....... ...... . . I1.2-20 l 11.3 Gaseous Waste Management System . .. . ..... . .. .. I1.3-1 11.3.1 Design Basis . . . . . . . . . . .. . . .. .. ... . .. . .. . 11.3-1 l 11.3.2 System Description . . ......... . . ....... ... 11.3-4 i 11.3.3 Radioactive Releases . . . . .... ..... . ........ I1.3-9 l 11.3.4 Combined License Information . . .. . . . 11.3-11 4 11.3.5 References .. .. .. .... . . . . . .. 11.3-11 I 11.4 Solid Waste Management .. . . . . . . . . .. . . 11.4-1 11.4.1 Design Basis . . . .. . ...... . .. .... ... . 11.4-1 11.4.2 System Description . .. .. .. ..... .... .. ... 11.4-3 f II A.3 System Safety Evaluation ...... .... . .. .. .. .. .. 11.4-13 i C]/ 11.4.4 Tests and Inspections . . . ... ... ... .. . . . . 11.4-13 11.4.5 Quality Assurance . . . . . . . . ... .. ... . 11.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program . . .. . . 11.4-13 11.4.7 References . . . ... . .. . .. . . 11.4-14 11.5 Radiation Monitoring .. .. .. .. .... .... . .. . I1.5-1 11.5.1 Design Basis . . ...... . . .. ... .. . .. . . I1.5-1 11.5.2 System Description . .. . . . .. . ... ... 11.5-2 11.5.3 Effluent Monitoring and Sampling . . . .. ...... I1.5-13 11.5.4 Process and Airborne Monitoring and Sampling . . . . . . . . . I1.5-13 11.5.5 Post-Accident Radiation Monitcring . . .. .. ... 11.5-14 11.5.6 Area Radiation Monitors . . . . . . ......... ... 11.5-14 11.5.7 Combined License Information . . . ... . . I1.5-17 CHAPTER 12 RADIATION PROTECTION . . ... . . . ..... .. 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As-Low-As-Reasonably Achievable (ALARA) ... . .. . . 12.1-1 12.1.1 Policy Considerations ...... .. . . 12.1-1 i 12.1.2 Design Considerations . . .. . .. .. . ... . . 12.1-2 l 12.1.3 Combined License Information . .... . .... .. ... . 12.1-6 12.2 Radiation Sources ... .. . ... . . .. . .. . . 12.2-1 12.2.1 Contained Sources . .. . . . .. 12.2-1
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| ,m 12.2.2 Airbome Radioactive Material Sources .. ... . 12.2-6 i
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| Section Title Page 12.2.3 Combined License Information . . ... ... .. . . . 12.2-8 12.2.4 References . . . . . . ..... ..... ........ ..... . . 12.2-8 12.3 Radiation Protection Design Features . .. .. .. ... . . . . . 12.3-1 12.3.1 Facility Design Features . ... . . ..... ... . .. 12.3-1 12.3.2 Shielding . . . . . . . . . . . . . . ... . .. .. . . . 12.3-9 12.3.3 Ventilation . . . ... .. . . ...... .. . . ... 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation . ..... . . ....... ... .... 12.3-19 12.3.5 Combined License Information . .. . . .. .... .. . 12.3-19 12.3.6 References . . . . . . . . . . . . . . . . . . .. 12.3-19 12.4 Dose Assessment .... ...... .. . . .. . ... . . 12.4-1 12.4.1 Occupational Radiation Exposure .... .. . . .... .. . 12.4-1 12.4.2 Radiation Exposure at the Site Boundary . . .... . . . 12.4-4 12.4.3 Combined License Information . . . . . . . . . . . . . . . . 12.4-4 12.5 Health Physics Facilities Design . ... .. ... . .. . .... 12.5-1 12.5.1 Objectives . . . .... .. . .... ..... . . .. 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities ........ . . . . . 12.5-1 12.5.3 Other Design Features . . . . . .. . . . . . . . 12.5-3 12.5.4 Controlling Access and Stay Time . . . . . .. 12.5-4 12.5.5 Combined License Information . . . ... . . . . . .. . 12.5-5 Volume 8 CHAPTER 13 CONDUCT OF OPERATION . . . .. . ... .. . ... 13-1 13.1 Organizational Structure of Applicant . ... .... . ... . .. 13-1 13.1.1 Combined License Information Item . .... . .. ... 13-1 13.2 Training .. . . .. . .. ... ... . . ... 13-1 13.2.1 Combined License Information Item . .. ..... .. .. 13-1 13.3 Emergency Planning . . . .... .... . . . . .... .... 13-1 13.3.1 Combined License Information Item . . . .. 13-2 13.4 Operational Review . . . . .. . . . . .. 13-2 13.4.1 Combined License Information Item . . . . .. 13-2 13.5 Plant Procedures . ... .. . . . . . . .. . 13-2 -
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| 13.5.1 Administrative Procedures . . . . .. . . 13-2 13.6 Industrial Security .. .. .. . . . . .. .... .. . . . 13-3 13.6.1 Preliminary Planning .... .. . . . . . .. 13-3 13.6.2 Security Plan . .. .. .... ... . . ...... . .. .. 13-3 13.6.3 Plant Protection System . . . . .. . .... 13-3 13.6.4 Physical Security Organization .. . . . .. 13-5 13.6.5 Physical Barriers .... . . . . 13-5 O
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| Section Title Page 13.6.6 Access Requirements . . . . ..... . ..... .... ... 13-6 !
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| 13.6.7 Detection Aids . . . .. . . . . .. . . ... . ..... 13-7 13.6.8 Security Lighting ...... . . .... . .... ...... .. 13-7 13.6.9 Security Power Supply System . . . . .. . .. . . .... 13-7 13.6.10 Communications . ..... . . . . . . ...... 13-7 13.6.11 Testing and Maintenance . . . .... ..... ......... . .. 13-8 l 13.6.12 Response Requirements . . .... . . ... .... ..... 13-8 !
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| 13.6.13 Combined License Information Item . . . ... .. . .. 13-8 j 13.7 References . . . .... .. . ..... . .. .. .. . . . . .. 13-8 '
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| l CHAPTER 14 INITIAL TEST PROGRAM . ... . . . ... . . ....... ... 14.1-1 14.1 Specific Information to be Included in Preliminary / Final Safety I Analysis Reports . . . . . . . .. . .. .. . . . ..... .. 14.1-1 l
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| 14.2 Specific Information to be included in Standard Safety Analysis Repons . . .. 14.2-1 1 14.2.1 Summary of Test Program and Objectives . . ... ... . .. . 14.2-1 14.2.2 Organization, Staffing, and Responsibilities . ..... . 14.2-4 ;
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| 14.2.3 Test Specifications and Test Procedures .. ... . ... .. .. 14.2-4 I i
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| 14.2.4 Compliance of Test Program with Regulatory Guides .. . .. ... 14.2-6 l
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| (] 14 2.5 Utilization of Reactor Operating and Testing Experience in the l V Development of Test Program . .. .. . . ... . . ... 14.2-6 ;
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| ' 4.2.6 Use of Plant Operating and Emergency Procedures .
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| . .... . . 14.2-6 i 14.2.7 Initial Fuel Loading and Initial Criticality ... . ....... . 14.2-7 l 14.2.8 Test Program Schedule .. .... .. . .. .... ... 14.2-10 J4.2.9 Preoperational Test Descriptions . . . ... . ... . . . . . . . 14.2-10 14.2.10 Startup Test Procedures . .. . . . . .. ...... . 14.2-80 14.3 Certified Design Material . . . .. . . . .. ... . . .. 14.3-1 14.1.1 CDM Section 1.0, Introduction . ...... . . .. . .... 14.3-2 14.3 2 CDM Section 2.0, System Based Design Descriptions and ITAAC . . . . ... . ... . . . . . . . . . 14.3-3 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC .. . .. . . ... . .... ... 14.3-9 14.3.4 Cenified Design Material Section, 4.0 Interface Requirement: . . 14.3-10 14.3.5 CDM Section 5.0, Site Parameters . .. . ..... . 14.3-10 14.3.6 Initial Test Program . . . . .... . .... . 14.3-10 14.3.7 Summary .... . . . ... .. ... . . ... . 14.3-11 !
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| 14.3.8 References . . . .... . .. . .. ...... 14.3-11 14.4 Combined License Applicant Responsibilities . ... .. . . .. ... 14.4-1 14.4.1 Organization and Staffing . . . ... .. . . ... .... . 14.4-1 14.4.2 Test Specifications and Procedures . . . . . . .. . . . . 14.4-1 14.4.3 Conduct of Test Program . ... .. . . . . . .. 14.4-1 14.4.4 Review and Evaluation of Test Results . ... . . .. 14.4-1 Q ,-
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| Revision: 10 Westiligt10USS xxi December 20,1996
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| Section Title P.,, age CHAPTER 15 ACCIDENT ANALYSES . .. ... . . . .. ..... .... . 15.0-1 15.0.1 Classification of Plant Conditions . . . .. ...... .. 15.0-1 15.0.2 Optimization of Control Systems . . . .... .. ......... ....... . 15.0-5 15.0.3 Plant Characteristics and Initial Conditions Assumed in the Accident Analyses . ... .... .. .... .. ... . ... . 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysts . . . . . 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics .. . ..... . 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses . 15.0-8 15.0.7 Instrumentation Drift and Calorimetric Errors, Power Range Neutron Flux . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accidant Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . ... ... ...... . .... .. . . 15.0-10 15.0.10 Residual Decay Heat . . . .... .. . .. .. . .. .. . . . 15.0-10 15.0.11 Computer Codes Utilized . . ... .. .. ....... . . . 15.0-11 15.0.11 Component Failures . . . . . ... ... .. .. . .. . .... . 15.0-13 15.0.13 Operator Actions . . ... . ..... ... . .... ... .. . 15.0 14 l ',.0.14 Combined License Information . . . . .. .... .. .. .. 15.0-14 15.0.15 References .. . ...... ... . . . . . .. . .. .. . . . 15.0-14 15.1 Increase in Heat Removal from the Primary System . . . . .... . 15.1-1 15.1.1 Feedwater System Maifunctions that Result in a Decrease in Feedwater Temperature . . . . . .. ....... . 15.1-1 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow ...... .. . . . ............ . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow . . ... . 15.1-5 15.1.4 Inadvenent Opening of a Steam Generator Relief or Safety Valve . . 15.1-8 .
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| 15.1.5 Steam System Piping Failure . . . . .. . ......... 15.1-11 l 15.1.6 Inadvertent Operation of the Passive Residual Heat Removal l Heat Exchanger . . . . . .. . . .. . ... ... . 15.1-20 15.1.7 Combined License Information . . . ..... 15.1-24 15.1.8 References . . .. .. . . . . .. .. . 15.1-24 15.2 Decrease in Heat Removal by the Secondary System . . .. .... 15.2-1 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . . .. ........ . 15.2-1 15.2.2 Loss of External Electrical Load . . .. . . . .. .. . . 15.2-1 15.2.3 Turbine Trip . ... . . . .. . .. . .. ... . . 15.2-3 15.2.4 Inadvertent Closure of Main Steam Isolation Valves . . . . . . . . . 15.2-7 l 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries . . . .... .... . . 15.2-8 15.2.7 Loss of Normal Feedwater Flow . ...... . . .. . 15.2-12 15.2.8 Feedwater System Pipe Break . ... . . . 15.2-16 15.2.9 Combined License Information .... .. . 15.2-21 O
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| Section Igl_e Pm 15.2.10 References . . . . . . . . . .. . . .. . . . . 15.2-21 15.3 Decrease in Reactor Coolant System Flow Rate .... .. . . ... . 15.3-1 15.3.1 Panial Loss of Forced Reactor Coolant Flow . ... .. . . . 15.3-1 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . .. . . . . 15.3-3 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . . .. . . . 15.3-5 15.3.4 Reactor Coolant Pump Shaft Break . ...... .. ... .. . . 15.3-10 15.3.5 Combined License Information . . . . . .. ..... .. . 15.3-10 15.3.6 References . . . ........... . ...... .. . ... 15.3-11 15.4 Reactivity and Power Distribution Anomalies . . ... .. . . . . 15.4-1 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Suberitical or Low-Power Startup Condition . . ... . . . . . . 15.4-1 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power . . . . . . ..... . . . . . . . . . . . 15.4-5 15.4.3 Rod Cluster Control Assembly Misalignment (System Malfunction or Operator Error) . ... .... . . . . ... 15.4-11 15.4.4 Stanup of an Inactive Reactor Coolant Pump at an Incorrect Temperature . . . ..... .. ... .. .. .... . . 15.4-17 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling
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| (~T Water Reactor Loop that Results in an Increased Reactor V Coolant Flow Rate . . ... . .. ...... . .. ..... 15.4-19 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant . ....... . .. .. . . . . 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position . . . .... .... . .. ..... ... . 15.4-25 15.4.8 Spectrum of Rod Cluster Control Assembly Ejection Accidents ... 15.4-28 15.4.9 Combined License Information . ...... .. . 15.4-39 15.4.10 References .... . . .. .. ... . . .. . 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory .. . . . . . 15.5-1 15.5.1 Inadvenent Operation of the Core Makeup Tanks (CMT) During Power Operation . . . . . .. ... .. .. . 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory . . . . . . .. . . . 15.5-4 15.5.3 Boiling Water Reactor Transients . . . 15.5-8 15.5.4 Combined License Information . . . . . .. .. . . 15.5-8 15.5.5 References . . . .. . . . .. . . .. ... 15.5-8 l 15.6 Decrease in Reactor Coolant Inventory . .. ... . . 15.6-1 15.6.1 Inadvenent Opening of a Pressurizer Safety Valve or Inadvenent Operation of the ADS . .. . .. 15.6-1 U
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| [ W85tiligh0USe xxiii December 20,1996
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| l 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . . . .... ............. . ... .. ... ... 15.6-4 15.6.3 Steam Generator Tube Rupture .. . ... .. ... . .. .. . 15.6-5 l 15.6.4 Spectmm of BWR Steam System Piping Failures l Outside of Containment . ..... . . . .. .... . . 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant 1 Pressure Boundary . ..... .. .. .. ... . 15.6-15 1 ,
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| 15.6.6 References . . ............. .. . . ... . . . . . 15.6-64 !
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| 15.7 Radioactive Release From a Subsystem or Component .. ...... . . . 15.7-1 15.7.1 Gas Waste Management System Leak or Failure . . . . . . . . . . . .. 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure j (Atmospheric Release) . ........ .... ... .... . . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure . ..... .. ..... .. ... ... . .. 15.7-1 !
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| 15.7.4 Fuel Handling Accident . . ... . . . ...... .. 15.7-1 15.7.5 Spent Fuel Cask Drop Accident . . . . . . .......... . 15.7-6 15.7.6 Combined License Information . .. . . .. . .... 15.7-6 15.7.7 References . . . . . . .... . . . . . . . . 15.~/-7 15.8 Anticipated Transients without Scram . . .. . .. . I',.8-1 15.8.1 General Background . ..... . ... .... . ..... '45.8-1 15.8.2 Anticipated Transients without Scram in the AP600 ... . .. 15.8-1 15.8.3 Conclusion . . . . ...... . . . ..... . 15.8-1 15.S.4 Combined License Information .. ... . ... ...... 15.8-1 15.8.5 References .... .... ...... . .... ....... . . . 15.8-1 l APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL, CONSEQUENCES OF ACCIDENTS .... . 15A-1 !
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| l 15A.1 Offsite Dose Calculation Models . . . .. . . . . .. . 15A-1 15 A.I.1 Immersion Dose Models . .. . .. .. 15A-1 l 15A.I.2 Inhalation Dose (Committed Effective Dose Equivalent) . . 15A-2 15A.l.3 Total Dose (Total Effective Dose Equivalent) ..... .. . . 15A-2 l 15A.2 Main Control Room Dose Models . . .. . . .. . .. ... . 15A-2 !
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| 15 A.2.1 Immersion Dose Models .. . .. ... . .. ... . . 15A-2 l 15A.2.2 Inhalation Dose . . ....... . .. .... .. . . . . 15A-4 ;
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| 15A.2.3 Total Dose (Total Effective Dose Equivalent) . . .. .. .. 15A-4 l 15A.3 General Analysis Parameters ... . .... ... . .. .. . 15A-4 !
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| 15A.3.1 Source Terms . . . . . .. . ... . . . . . 15A-4 15A.3.2 Nuclide Parameters . . . . . .. . . .. 15A-6 15A.3.3 Atmospheric Dispersion Factors . .. . 15A-6 15A.4 References . .... . . . . . . . 15A-6 Revision: 10 December 20,1996 xxjy [ WBCiflgh0USB l
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| 1--i Master Table of Contents C/ MASTER TABLE OF CONTENTS (Cont.)
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| l Section Title Page Volume 10 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS . ....... ...... .. .. . . . . 16.1-1 16.1.1 Introduction to Technical Specifications . . . . . . . .. . 16.1-1 1.0 Use and Application .... . ...... . ... . . 1.1-1 1.1 Definitions . ...... .. .. ... ... . . . 1.1-1 1.2 Logical Connectors . . . .. ....... ...... 1.2-1 I 1.3 Completion Times . . . .. . .. .. ... . . 1.3-1 ,
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| 1.4 Frequency .... ..... . . ... . .. .. . 1.4-1 i 2.0 Safety Limits (SLs) . .. . .. .............. . .. . 2.0-1 2.1 S Ls . . . . . . . . . .. .. .... .. . ........ .. 2.0-1 2.2 SL Violations ..... ........... .. ... ..... 2.0-1 3.0 Limiting Conditions for Operation (LCO) Applicability . . . . . . . 3.0-1 3.0 Surveillance Requirement (SR) Applicability . . . . ...... . 3.0-4 3.1 Reactivity Control Systems . .. .... .. .. . ... .. 3.1-1 3.1.1 Shutdown Margin (SDM) .. . ... . . . . 3.1-1 3.1.2 Core Reactivity . . .. . . .... .. .. ... . 3.1-2 p 3.1.3 Moderator Temperature Coefficient (MTC) . ...... . 3.1-4
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| ( ) 3.1.4 Rod Group Alignment Limits . . . . . . . . . .. . . 3.1-6 3.1.5 Shutdown Bank Insertion Limits . . . . . . . .. . . 3.1-11 3.1.6 Control Bank Insertion Limits . . .... .... . . . 3.1-13 3.1.7 Rod Position Indication . . . . . . . . .... .. . . . . 3.1 -16 3.1.8 Physics Tests Exceptions - Mode '2 . . . . ... .. . . 3.1-18 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves . . ... 3.1-20 3.2 Power Distribution Limits . . . . . . ... . ..... ..... 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fo (Z))
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| (FqMethodology) .. . . .. . ...... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) .. . .. . . .. ... 3.2-5 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . . 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . . . . . . . . . 3.2- 10 3.2.5 OPDMS-Monitored Power Distribution Parameters . . ..... .. .... . .. .. . . 3.2-14 3.3 Instrumentation ... . . .. . . .. .. ... 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation . . .. 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation . . ... 3.3-17 3.3.3 Post Accident Monitoring (PAM) Instrumentation . 3.3-45 3.3.4 Remote Shutdown Workstation . . . . . . .. 3.3-48
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title M 3.4 Reactor Coolant System (RCS) . , ...... .. 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . . . . . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . . . . . . 3.4-3 3.4.3 RCS Pressure and Temperature (Pfr) Limits . ..... . 3.4-4 3.4.4 RCS Loops - Modes 1 and 2 .......... . .. . 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . ... . ..... . . . 3.4-7 3.4.6 Pressurizer ..... ... . . .. .... . . 3.4-9 3.4.7 Pressurizer Safety Valves . . .. ... .. . . . . . . . 3.4-10 3.4.8 RCS Operational Leakage .. .. .. . .. ... . 3.4-12 3.4.9 Minimum RCS Flow . . .... .. .. . . . . . 3.4-14 3.4.10 RCS Leakage Detection Instrumentation .. .. . . . . 3.4-15 3.4.11 RCS Specific Activity . . .... ....... .. 3.4-18 3.4.12 Automatic Depressurization System (ADS) - Operating . 3.4-20 3.4.13 Automatic Depressurization System (ADS)- Shutdown, RCS Intact . . . . ..... .. ...... . . . 3.4-22 3.4.14 Automatic Depressurization System (ADS) - Shutdown, RCS Open . . . .. . .. .... . ........ . 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . ... .. . ... ....... . 3.4-26 3.5 Passive Core Cooling System (PXS) . .. ..... . . . 3.5-1 3.5.1 Accumulators . . . . . . . ... ... . ....... . . 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating . . .. . . . 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact .. . 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . .......... .. . . 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . . . . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST) -
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| Operating . . . .... .. . .. . . ...... . . 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory High . . . . ..... . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low ..... . .. . . . 3.5-18 3.6 Containment Systems . . . . . .. . .. ..... .... . 3.6-1 3.6.1 Containment . .. .. . ... ....... .... . . 3.6-1 3.6.2 Containment Air Locks . ..... .. . . ... .... .. 3.6-3 ;
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| 3.6.3 Containment Isolation Valves . ...... .. .. . 3.6-7 3.6.4 Containment Pressure . . . . .... .. . 3.6-12 3.6.5 Containment Air Temperature . . .. .. . . . 3.6-13 O
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| Revision: 10 December 20,1996 xxvi Westilighouse
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| l N-) MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age i
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| 1 1
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| 3.6.6 Passive Containment Cooling System (PCS) - Operation . 3.6-14 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . 3.6-17 3.6.8 Containment Penetrations . ........ . .. ... 3.6-19 3.6.9 pH Adjustment . . . . ......... . . ....... 3.6-22 i 3.7 Plant Systems . ........ ... . . . . .. .. .. 3.7 .
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| 3.7.1 Main Steam Safety Valves (MSSVs) . . . . .. .. .. .. 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . .......... 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves (MFIV and MFCV) . . . . . . . ..... . ........ . 3.7-7 3.7.4 Secondary Specific Activity . . . . .. . .. .. .... 3.7-9 j 3.7.5 Spent Fuel Pool Water Level . . . . . .... . ... .. . 3.7-10 3.7.6 Main Control Room Habitability System (VES) . . .. . 3.7-11 !
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| 3.7.7 Startup Feedwater Isolation and Control Valves . . .. . 3.7-15 3.8 Electrical Power Systems . . . . .. . ...... ... . 3.8-1 3.8.1 DC Sources - Operating . ... . . . ...... .. 3.8-1 3.8.2 DC Sources - Shutdown . . .. . ... . 3.8-5 i 3.8.3 Inverters - Operating . . . .. .. . ... .. . 3.8-7 ;
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| 3.8.4 Inverters - Shutdown . . . . . .
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| . ... ...... 3.8-9
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| ~'i 3.8.5 Distribution Systems - Operating . ... .. .. 3.8-11 (C l 3.8.6 Distribution Systems - Shutdown ... .......... . . 3.8-13 l 3.8.7 Battery Cell Parameters . . .... ...... .... 3.8-15 l 3.9 Refueling Operations ........ ... ... . .. .. ..... 3.9-1 .
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| 3.9.1 Boron Concentration . ....... .......... . . 3.9-1 l 3.9.2 Unborated Water Source Flow Paths . . . . ..... .. 3.9-2 )
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| 3.9.3 Nuclear Instrumentation .... . . .. ... .. . . 3.9-4 !
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| 3.9.4 Refueling Cavity Water Level . . . . . .. . . ..... 3.9-6 l 4.0 Design Features .... .. .. .. . . . . . .. .. 4.0-1 4.1 Site . . . . . . ..... . . .. ... . . .. ... .. 4.0-1 4.1.1 Site and Exclusion Boundaries .... . . . . 4.0-1 4.1.2 Low Population Zone (LPZ) . . . ... .. .. 4.0-1 j 4.2 Reactor Core ...... .. ..... . . .. .. 4.0-1 i 1
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| 4.2.1 Fuel Assemblies . . . . . . . . .. .... 4.0-1 1 4.2.2 Control Rod and Gray Rod Assemblies . 4.0-1 1 4.3 Fuel Storage . . . . . . .. . ... . .. . 4.0-2 4.3.1 Criticality . . . .. ... . .. . ... . 4.0-2 4.3.2 Drainage ... ..... .. . . . . 4.0-2 4.3.3 Capacity .. .. .. .. .... .. . 4.0-2 4.4 Hydrogen Control . . . .. . .. ... . .. 4.0-3 4.4.1 Passive Autocatalytic Recombiners (PARS) . .. . 4.0-3 5.0 Administrative Controls . ... . . . . 5.0-1 5.1 Responsibility . . . ... ...... .. . . .. . 5/kl n 5.2 Organization . ... .. ... .. . . .. . ... . 5.0-2 i \
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| G Revision: 10 3 Westingh00S8 xxvii December 20,1996
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| Master Table of Contents m-MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 5.3 Unit Staff Qualifications ...... . ...... . . . . 5.0-5 5.4 Procedures . . . . . ......... .. .. .... ... 5.0-6 5.5 Programs and Manuals . . . .. ... . . . ... . . 5.0-7 5.6 Reponing Requirements . .. . . .. . . . 5.0-15 B 2.0 Safety Limits (SLs) . . . . .... . . ..... .... . B 2.0-1 B 2.1.1 Reactor Core Safety Limits (SLs) . .... . . B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability . ... . . B 3.0-1 B 3.0 Surveillance Requirement (SR) Applicability ............ . B 3.0-12 B 3.1 Reactivity Control Systems . . .. . ..... . . . B 3.1-1 B 3.1.1 Shutdown Margin (SDM) . .. .. ... . . B 3.1-1 B 3.1.2 Core Reactivity . . . ...... . ... B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . .... . .. B 3.1-19 B 3.1.5 Shutdown Bank Insenion Limits . . . .... B 3.1-29 B 3.1.6 Control Bank Insenion Limits . .. .... B 3.1-34 B 3.1.7 Rod Position Indication . . ... . .... .. B 3.1-40 B 3.1.8 Physics Tests Exceptions - Mode 2 . . . . B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves . ... B 3.1-53 B 3.2 Power Distribution Limits . . . .... .. . . . . . . B 3.2- 1 B 3.2.1 Heat Flux Hot Channel Factor (Fq(Z))
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| (FoMethodology) ...... . ........ B 3.2-1 ,
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| B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor !
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| (F%) .. ... . .. . .. .. ... . .. B 3.2-10 I B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) .. .. B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . . ... B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters . .... . .. . . . B 3.2-28 B 3.3 Instrumentation .. . .. . . . . .. . . . . . B 3.3-1 j B 3.3.1 Reactor Trip System (RTS) Instrumentation . . . B 3.3-1
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| B 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instmmentation .. . .. .. B 3.3-53 B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation . . . . . ... . . . . . . B 3.3-115 B 3.3.4 Remote Shutdown Workstation . ... . . B 3.3-125 ;
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| B 3.4 Reactor Coolant System (RCS) . . .... . B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure l from Nucleate Boiling (DNB) Limits . . . B 3.4-1 01 Resision: 10 December 20,1996 xxviii W85tingh0USS
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| Section Title Page B 3.4.2 RCS Minimum Temperature for Criticality . . B 3.4-6 B 3.4.3 RCS Pressure and Temperature (P/T) Limits B 3.4-9 B 3.4.4 RCS Loops - Modes 1 and 2 . . . . . . . . . . B 3.4-17 B 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . ... B 3.4-21 B 3.4.6 Pressurizer . . . . . . .. . . .... . . . . B 3.4-25 B 3.4.7 Pressurizer Safety Valves . . ..... .. . B 3.4-28 B 3.4.8 RCS Operational Leakage .. .... . . B 3.4-32 B 3.4.9 Minimum RCS Flow . . .......... . B 3.4-38 B 3.4.10 RCS Leakage Detection Instrumentation . .. B 3.4-41 B 3.4.11 RCS Specific Activity. ... ... .... . B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)-
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| Operating . . . . . ....... ..... .... B 3.4-50 B 3.4.13 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Intact . .. .... . .. B 3.4-54 B 3.4.14 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Open . . . ........ B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . . . . ... .. . . . B 3.4-60 (3
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| (,)
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| B 3.5 Passive Core Cooling System (PXS) ...
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| B 3.5.1 Accumulators .. . . . ..... . .
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| . . . . B 3.5-1
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| . . B 3.5-1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . . B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact ... .. . .. ... .. .. B 3.5-15 l B 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . .. B 3.5-18 B 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . B 3.5-24 ,
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| l B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating ... .. .. B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory High . . B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low ... . . .. . . . B 3.5-38 B 3.6 Containment Systems . .. . ... .... . .. . . . B 3.6-1 B 3.6.1 Containment . . . ..... . . . B 3.6-1 B 3.6.2 Containment Air Loc'cs . . .. ... B 3.6-6 B 3.6.3 Containment Isolation Valves . . .... B 3.6-13 B 3.6.4 Containment Pressure ... .... ... B 3.6-23 B 3.6.5 Containment Air Temperature . . ... B 3.6-26 B 3.6.6 Passive Containment Cooling System 7- (PCS) - Operating . . .... .. B 3.6-30 i
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . . . . . . .. ..... . B 3.6-37 B 3.6.8 Containment Penetrations . .. . . . . . . . B 3.6-40 B 3.6.9 pH Adjustment . . . . . . . . ... . . B 3.6-47 B 3.7 Plant Systems . . . . .. . . .. ... B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) .. ............ B 3.7-13 B 3.7.4 Secondary Specific Activity . ... . . . B 3.7-18 B 3.7.5 Spent Fuel Pool Water Level . . . . . . . . . . B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability System . . . . . ...... .. .. .. . B 3.7-24 B 3.7.7 Startup Feedwater Isolation and Control Valves B 3.7-30 B 3.8 Electrical Power Systems .... .. . . .. . . . . B 3.8- 1 B 3.8.1 DC Sources - Operating . . .. .. ... . B 3.8-1 B 3.8.2 DC Sources - Shutdown . . .. . B 3.8-11 B 3.8.3 Inveners - Operating . .. . ... . . . B 3.8-15 B 3.8.4 Inverters - Shutdown . . . ..... .. . B 3.8-20 B 3.8.5 Distribution Systems - Operating . .. ... B 3.8-24 B 3.8.6 Distribution Systems - Shutdown . ... . . B 3.8.33 B 3.8.7 Battery Cell Parameters . . .. . B 3.8-37 B 3.9 Refueling Operations . ... . . .. ... .. . B 3.9-1 B 3.9.1 Boron Concentration . . . . . .. .. . . . . B 3.9-1 B 3.9.2 Unborated Water Source Flow Paths . . . . . B 3.9-5 B 3.9.3 Nuclear Instrumentation . .. .. . . . B 3.9-8 B 3.9.4 Refueling Cavity Water Level ... B 3.9-11 Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM . . .. . .. 16.2-1 16.2.1 Introduction . ... . . .. . . . ... . . . 16.2-1 16.2.2 Scope . . .. . . . .. .. . . . 16.2-1 16.2.3 Design Considerations . . ... . . .. . . 16.2-1 16.2.4 Relationship to Other Administrative Programs . .. . . . . 16.2-2 16.2.5 The AP600 Design Organization ... . ... . . . 16.2-2 16.2.6 Objective . ...... ... . . .... . .. .. .... 16.2-3 16.2.7 D-RAP, Phase I . . ... . . . ... . . . . 16.2-4 16.2.8 Combined License Activities - O-RAP ... .. . . 16.2-9 16.2.9 Glossary of Terms ..... .. . .. .. ... 16.2-10 0
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| Section Title Pm .:
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| 16.2.10 References . . ..... ...... ... . .. . . 16.2-11 CHAPTER 17 QUALITY ASSURANCE . . . . . ....... ...... .. . .. . . 17.1-1 j 17.1 Quality Assurance During the Design and Construction Phases . . . . . . 17.1-1 '
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| 17.2 Quality Assurance During the Operations Phase . . . .. ... . . . 17.1-1 17.3 Quality Assurance During Design, Procurement, Fabrication, Inspection ;
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| and/or Testing of Nuclear Power Plant Items and Services . . . .. .. 17.1-1 17.4 Combined License Information Items ..... .. . . ... .. . 17.1-2 17.5 References ...... .. . ... ... ........ . . . . . . . . . . . . 17.1 -2 i
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| CHAPTER 18 HUMAN FACTORS ENGINEERING . .. . .. . ....... 18.1-1 18.1 Overview . . .... .. ..... ... . . ... ...... . . 18.1-1 18.1.1 References . ............. . .. .... .. . . . 18.1-4 18.2 Human Factors Engineering Program Management ... .. . .. . . 18.2-1
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| ;8.2.1 Human Factors Engineerie.g Program Goals, Scope, Assumptions, and Constraints . . . . . . . . . . . .... . I8.2-1 18.2.2 Human System Interfaces Design Team and Organization . . . 18.2-4 18.2.3 Human Factors Engineering Processes and Procedures . . . . .. . 18.2-11 f7 18.2.4 Human Factors Engineering Issues Tracking . . . . . . . . . . . . I 8.2-17 V 18.2.5 Human Factors Engineering Technical Programs and Milestones . . . . . . .. .. . .. . . .. . . ... 18.2.18 18.2.6 Combined License Information .. .. ..... .. .. . . 18.2-19 18.2.7 References . ... .. ....... . . .. .... 18.2-19 18.3 Operating Experience Review ... . . . .. . . .. . . I8.3-1 18.3.1 Combined License Information ... . .. . 18.3-1 18.3.2 References . . .. .. ... . .. . . . . . .. 18.3-1 18.4 Functional Requirements Analysis and Allocation .... . .. .. I8.4-1 18.4.1 Combined License Information . . . . . .... . . 18.4-2 18.4.2 References . .. . . .. .. . . .. . . 18.4-2 18.5 AP600 Task Analysis Implementation Plan . .. . . . . 18.5-1 18.5.1 Task Analysis Scope . .. ... .... . . .. .. . 18.5-1 18.5.2 Task Analysis Implementation Plan .. . . . .. .. . 18.5-2 18.5.3 Job Design Factors . . .... .. .. .. . . . . . 18.5-5 18.5.4 Combined License Information Item . ... . . .. . 18.5-5 18.5.5 References . . . ..... . . .. . .. . 18.5-5 18.6 Staffing . . . .. . . .. . . . .. .. . ... . . 18.6-1 18.6.1 Combined License Information Item . .. .. .. ... .... . 18.6-1 18.6.2 References . . . . . . . . . . ... . .. ..... . . . . . . . 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering . 18.7-1 18.7.1 Combined License Information . ... . . .. . ...... 18.7-1 18.7.2 References . ... . .... ... .. .. . . . . . I8.7-1 18.8 Human System Interface Design . ... . . . . . ... 18.8-1 O*
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pm 18.8.1 Implementation Plan for the Human System Interface Design 18.8-3 18.8.2 Safety Parameter Display System (SPDS) . . . . . . . .. . 18.8-11 18.8.3 Operation and Control Centers . ... ....... . 18.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Portion of the Plant . . . . . . . ..... .. .. 18.8-20 18.8.5 Combined License Information . . . .. . ... 18.8 23 18.8.6 References . . . ... . . ... . ..... .... 18.8-23 18.9 Procedure Development ........ . . . . .. .. .... I8.9-1 18.9.1 Combined License lnformation . . . .... . . . . 18.9-1 18.9.2 References . . . . . . . . . ... .. . .. . . . 18.9-1 18.10 Training Program Development .. ... . . . . ... I8.10-1 18.10.1 Combined License Information . . . . . . 18.10-1 18.10.2 References . . ...... . . .. . . . 18.10-1 18.11 Human System Interface Design Test Program . . . . 18.11-1 18.11.1 Combined License Information . . . ..... . . 18.11-2 18.11.2 References . . . .. .. .. .. . 18.11-2 18.12 Displays, Alarms, and Controls . . . . .. . . . . . . . 18.12-1 18.12.1 Inventory of Displays, Alarms, and Controls . . .. . . . . I 8.12-1 18.12.2 Minimum Inventory of Main Control Room Fixed Displays, Alarms, and Controls . . . . . . ...... . . 18.12-1 18.12.3 Remote Shutdown Workstation Displays, Alarms, and Controls . 18.12-7 18.12.4 Combined License Information . . . . . . . . . 18.12-7 18.12.5 References . .. . ... .. .. . . . ... . 18.12-8 9
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| Revision: 10 December 20,1996 xxxii T Westinghouse
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| MASTER TABLE OF CONTENTS Section Title Page Volume 1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRHrrION OF PLANT .. . .. . 1.1-1 1.1 Introduction . .... ... ... ............ . ..... ... . 1.1-1 1.1.1 Plant Location . . ............ . ... . .. .... . 1.1-1 1.1.2 Containment Type .. ........ .... .... .. . ...... 1.1-1
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| [ 1.1.3 Reactor Type . . . . . ...... .. .. . . .. . . ...... . . . . .. .. . 1.1-1 1.1.4 Power Output . . . . . . . ........ . . .... ...... .. ... 1.1-1 1.1.5 Schedule . . ....... .. .... ... . . ..... .. ... . 1.1-1 1.1.6 Format and Content .. . .... ....... ... . ......... . 1.1 -2 1.1.7 Combined License Information . . .............. ..... 1.1-3 1.2 General Plant Description . . . . . . . . . . . ... . ...... .. . . . . . .. .. . 1.2-1 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 ;
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| 1.2.2 Site Description . . . . . . . . . . . . . ..... . . .... . 1.2-15 l 1.2.3 Plant Arrangement Description . . ...... . . ... . . . . . . 1.2-16 l 1.2.4 Nuclear Island . . . . . . . . . . . . . . . . . . .......... . . . . . . . 1.2-17 i 1.2.5 Annex Building . . . . . . . . . . . . . . . .. . . ....... .... 1.2-24 g 1.2.6 Diesel Generator Building . . ......... . ..._....... .. 1.2-25 1.2.7 Radwaste Building . . . . . . . . . 1.2-26 (V) 1.2.8 Turbine Building . . . . . . .
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| ... .... . .... ...... . 1.2-26 i
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| 1.2.9 Combined License Information . . . .. .. .. ............. 1.2-27 ;
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| 1.3 Comparisons with Similar Facility Designs .. ..... ...... ... ..... . 1.3-1 l 1.4 Identification of Agents and Contractors . ....... .... . ... .. . 1.4-1 !
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| 1.4.1 Applicant - Program Manager . . . . . . ....... ..... 1.4-1 1.4.2 Other Contractors and Participants . . . . . ..... . ....... . 1.4-1 1.4.3 Combined License Information . .... . . ..... . . .. .. . 1.4-3 1.5 Requirements for Further Technical Information .. . . .... . . . . . . . 1.5-1 1.5.1 AP600 Safety-Related Tests . .. .... .. .... .... . 1.5-1 1.5.2 AP600 Component Design Tests .. . . . ........ .. . 1.5-7 1.5.3 Combined License Information . ... ... . . . ..... . 1.5-8 1.5.4 References . . . . . . . . . ..... .... . . ...... .. . . 1.5-8 1.6 Material Referenced ... .......... .. . . .... .. . ..... .. 1.6-1 1.7 Drawings and Other Detailed Information ...... . ..... . . . . . 1.7-1 1.7.1 Electrical and Instrumentation and Control Drawings ..... .... . 1.7-1 1.7.2 Piping and Instrumentation Diagrams . . . . . .. ... .... 1.7 1 1.7.3 Combined License Information . . . . . . . . . . . . . . 1.7-1 1.8 Interfaces for Standard Design . . .. ... . .. .... .. . 1.8-1 1.9 Compliance with Regulatory Criteria . . .... .. . . . 1.9-1 1.9.1 Regulatory Guides . . . . .. ..... . . . ... ... . . . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) .... ... . 1.9-3 1.9.3 Three Mile Island Issues . .. .. .. . . .... . 1.9-3
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| Revision: 10 W-W85tiftgt100S8 -
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| December 20,1996
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| ~ mn l Master Tame of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h 1.9.4 Unresolved Safety Issues and Generic Safety Issues . . . .. . . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues . . .. . 1.9-74 l
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| 1.9.6 Combined License Information . . . .. ... .......... . . 1.9-107 1.9.7 References . ..... .. . . .. .. ........... 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES . ...... ..... . 1 A-1 1 A.1 References .............. ....... . .... . .. ... ... l A-79 APPENDIX IB SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES ... .. . IB-1 IB.1 Introduction . . . . . . ... .... . . . . . .... .. . ... IB-1 I B.2 Summary . .... . ... ... ..... .. ........... . . IB-1 I B.3 Selection of SAMDAS . . . . . . .. .. .. . . .. . .... . IB-2 I B.4 Methodology . . . . . ... .... .. .. . .. .... .... IB-2 1B.4.1 Risk Reduction .... . . . .. . ... . .. .. . . IB-2 IB.4.2 Capital Cost Estimates ..... . .. ..... . ...... . . . . . I B-3 IB.4.3 Cost Benefit Analysis . . . .. . .............. ... . IB-3 IB.5 PRA Release Categories . . . . ... . . ...... .............. . IB-3' IB.5.1 Release Category OK . . . . ... ........... . . . 1 B-4 IB.5.2 Release Category OKP .. . . . ...... ..... . . . . . . I B-4 IB.5.3 Release Category CC . . . . . . . . . . . .. ... .. . . . . . . . I B-5 IB.5.4 Release Category CI . . . . .. .. .. ........ .. . ... . IB-5 IB.6 Total Population Dose . . . . . . . . . . . . . . . . . .. ... . ....... . IB-5 I B.7 SAMDA Description and Benefit . . . . . . . ......... ... .. . . 1B-6 1 B.7.1 Upgrade the CVCS for Small LOCAs . . . . . . . . . . ... .. . . . I B-6 IB.7.2 Filtered Vent . . . . . . . . . . . . ..... ... ........ . . I B-6 1B.7.3 Locate Normal RIIR Inside Containment ....... .. . .. .. 1B-7 1B.7.4 Self-Actuating Containment Isolation Valves . ..... ..... .. 1 B-7 IB.7.5 Passive Containment Sprays . . .. ... . .. . ... . . . IB-7 1B.7.6 Active High Pressure Safety Injection System . . . . . . .... . . I B-7 1B.7.7 Steam Generator Shell-Side Heat Removal System . . .. . . . IB-8 IB.7.8 Direct Steam Generator Relief Flow to the IRWST .. . IB-8 IB.7.9 Increased Steam Generator Pressure Capability . ... IB-8 IB.7.10 Secondary Containment Filtered Ventilation .. .. . . . . IB-8 l 1 B.7.11 Diversify the IRWST Discharge Valves ..... .. . . IB-9 1B.7.12 Ex-Vessel Core Catcher . .. .. . ... . . . . 1B-9 1B.7.13 High Pressure Containment Design . ..... ... .... . . . 1 B-9 1B.7.14 Increase Reliability of D..erse Actuation System .. . . . . . . I B-9 1 B.8 Results .. .... .. ... .. ..... . .... .. .. . 1B-9 1B.9 References . ... . . .. . .... . . .. . ....... .. .... IB 11 Revision: 10 l December 20,1996 i [ W85tingh0USS
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| Master Table of Contents 4
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| A (v) MASTER TABLE OF CONTENTS (Cont.) '
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| Section Title Eage CHAPTER 2 SITE CHARACTERISTICS ........ ........... .............. 2-1 2.1 Geography and Demography . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1
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| , 2.1.1 Combined License Information for Geography and Demography . . . 2-1 2.2 Nearby Industrial, Transportation, and Military Facilities ........ ...... 2-1
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| , 2.2.1 Combined License Information for Identification of Site-specific Potential Hazards . . . . . . . . . . . . . ...................... 2-2 2.3 Meteorology .......................................... ... 2-2 2.3.1 Regional Climatology . . . . . . . . . . . . . . . . l
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| , . .............. 2-3 ;
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| . 2.3.2 Local Meteorology . . . ....................... .... .. 2-3 l 2.3.3 Onsite Meteorological Measurement Programs . . . . . . . . . . . . . .. 2-3 2.3.4 Short-Term Diffusion Estimates . . . . . . . ................. 2-3 2.3.5 Long-Term Diffusion Estimates . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 l 2.3.6 Combined Licensed Information . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 4 2.4 Hydrologic Engineering . . . . . . . . . . . . . . . . . . . . ................. 2-5 2.4.1 Combined License Information ................ ......... 2-5 2.5 Geology, Seismology, and Geotechnical Engineering . . . . . . . . . . . . . . . . . . 2-6 2.5.1 Basic Geological and Seismic Combined License Information . . . . . 2-6 1 2.5.2 Vibratory Ground Motion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-7 Q 2.5.3 Surface Faulting Combined License Information . . . . . . . . . . . . . . 2-7 (V 2.5.4 Stability of Subsurface Materials and Foundations .. . . . . . . . . . . . . 2-8 2.5.5 Combined License Information for Stability of Slopes . . . . . . . . . 2-12 2.5.6 Combined License Information for Embankments and Dams . . . . . . 2-13 2.5.7 Re ference s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 13 APPENDIX 2A DESIGN SOIL PROFILES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. . . . . 2A-1 ,
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| 2A.2 Generic Soil Profiles . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-2
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| . 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . . . . . . . . 2A-4 2A.4 Free-Field Site Response Analysis . . . ...................... . 2A-5 2A.5 2D Soil-Structure Interaction Analysis . . . . . . . . . . .. ........ . . . . 2A-7 2A.6 AP600 Design Soil Profiles . . . . . . . . .. .............. . . . . . 2A-12 l 1
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| 2A.7 References . . . . . . . . . . ............... ........... . . . . . . 2A-14 APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL 1
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| PROFILES . . . . . . . . ....... ................... ..... . . 2B-1 2B.1 2D SSI Analysis Parameters and Procedures ........ ... . .... . . 2B-2 2B.l .1 Stmetural Models . . . . . . . ...... .... ..... ... . . . 2B-2 2B.l.2 SASSI Foundation Models ............. ......... . . . 2B-2 l
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| 2B.I.3 Soil Properties for SSI Analysis . . . . . . . ....... . . . . . . . . 2B-2 2B.I .4 In put Motion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2B-3 28.1.5 Two-Dimensional Enveloped SSI Results . . . .... .. . . . . 2B-3 2B.2 Design Soil Profiles . . . . ... ...... . .. ..., .. .. ...... 2B-3 V
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| Revision: 10 T h sdnghouse ii December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page i
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| 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . . . . . 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) . ......... . . . . . 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . . 2B-5 2B.2.4 Variation of Soil Properties and 60 Percent Requirement of Free-Field Spectra at Foundation Level . . . . .. . . . 2B-5 2B.2.5 AP600 Design Soil Profiles .. .. . . .. ... . . . 2B-6 2B.3 Soil Profile Parametric Studies: ..... . .... . .. . ... 2B-6 2B.3.1 Depth-to-Base Rock .. .. . .. .. ... ... . 2B-7 !
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| 2B.3.2 Soil Curves for Clay Material . .. . ...... . . . . . . 2B-7 2B.3.3 Poisson's Ratio for Soil above Water Table . .... .. ... . 2B-8 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site . .. . 2B-8 2B.3.5 Idriss 1990 Soil Curves . .. . . . . . . . . 2B-9 2B.3.5 Soil Densitys . . .. . . .. . . .... 2B-9 2B.4 References . . . . . . .. ...... . . .. .. 2B-9A Volume 2 APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES . . . ..... .... . . 2C-1 2C.1 2D SASSI Analysis for Seismic Lateral Earth Pressure . . . . . . . 2C-1 !
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| 2C.l .1 Analysis Method . .......... 2C-1 l
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| 2C.I .2 Structural Models . . .... .. ... . . .. ... .. . . 2C-1 2C. I .3 SASSI Foundation Models . . ..... . . . . 2C-1 i 2C. I .4 Representation of Adjacent Structures . .. ..... . . 2C-2 j 2C.I .5 Input Motion ......... .. . .. . .. . . . . . . . 2C-2 2C. I .6 Soil Propenies . .... . . . . . . .. . 2C-2 2C. I .7 2D SASSI Analyses Results .... .... . ... . 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island . . . . . . . . . . . 2C-2 2C.3 Local Distribution of Lateral Eanh Pressure . .. . . ... . . 2C-3 2C.4 References . . .. ... .. . .. . . . .. 2C-4 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS .. . . .. .. . . ... .. . . 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria 3.1-1 3.1.1 Overall Requirements . . .. . ... . .. 3.1-1 3.1.2 Protection by Multiple Fission Product Barriers 3.1-4 3.1.3 Protection and Reactivity Control Systems . 3.1-12 3.1.4 Fluid Systems ..... . . . . ... .. . 3.1-18 3.1.5 Reactor Containment . ... . ... . 3.1-30 3.1.6 Fuel and Reactivity Control ... . . . .. . . 3.1-34 3.1.7 Combined License Information . . . . . 3.1-37 3.1.8 References . . . ... ... ... . . . . .. 3.1-37 Revision: 10 December 20,1996 iv 3 Westirighouse
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| r k MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page j
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| l 3.2 Classification of Stmetures, Components, and Systems ......... .. .. . 3.2-1 3.2.1 Seismic Classification . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 3.2-1 3.2.2 AP600 Classification System . . . . . . , . .... ...... .. .. . 3.2-3 3.2.3 Inspection Requirements . . .......... ...... . . . 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System ... . ..... ........... . . . 3.2-13 3.2.5 Combined License Information .. ....... . ............ 3.2-16 3.2.6 References . . . . . . . . . . . . .................. . . 3.2-17 3.3 Wind and Tornado Loadings . . . . . .... . ..................... 3.3-1
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| ! 3.3.1 Wind Loadings . . . . . . . . . . .. ........ ........ .. . . . 3.3-1 3.3.2 Tornado Loadings . . . . . . . . . . . ........ .. ... .. .. . . 3.3-2 3.3.3 Combined License Information . . . ..... ............. 3.3-4 3.3.4 References . . . . . . . . . . . . . . . . . . ..... ... ..... ... . 3.3-4 3.4 Water Level (Flood) Design ............... .. ................ 3.4-1 3.4.1 Flood Protection ..... .. ............. ... .. .. 3.4,1 i 3.4.2 Analytical and Test Procedures . . . . . . . . . . . . ... . . . . . . . 3.4-24 l 3.4.3 Combined License Information ............... . . . . . . . . 3.4-24 :
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| 3.4.4 References . . . . . . . . . . . . . . . ......... ..... . . . . . 3.4-24 3.5 Missile Protection . . . . . . . . . . . . . .................. .. 3.5-1 O 3.5.1 Missile Selection and Description . . . . . ...................
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| 3.5-4 3.5.2 Protection from Externally Generated Missiles . . . . . . . . . . . . . . 3.5-13 3.5.3 Barrier Design Procedures . . . . . ........... ........... 3.5-13 3.5.4 Combined License Information .........,............... 3.5-16 !
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| i 3.5.5 References . . . . . . . . . . . . ........................... 3.5-16 l 3.6 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside l Containment .................... ........ . ... 3.6-2 l 3.6.2 Determination of Break Locations and Dynamic Effects l Associated with the Postulated Rupture of Piping . . . .. . . . . 3.6-12 3.6.3 Leak-before-Break Evaluation Procedures . . . ..... . . 3.6-31 3.6.4 Combined License Information . ........ ... . .. 3.6-38 3.6.5 References . . . . . . . . . . . . . . .. . .... . ... .. . . . . 3.6-38 l 3.7 Seismic Design . ....... ... .............. . . ... 3.7-1 l 3.7.1 Seismic Input . . . . . . . . . . . .. ..... . ... ..... . . . 3.7 1 l 3.7.2 Seismic System Analysis . . . . . , . . . . . . .. ....... . . . 3.7-6 l l 3.7.3 Seismic Subsystem Analysis . . . ....... . ..... . . . . . 3.7 20 3.7.4 Seismic Instrumentation . .. .. . ... ..... ... . . . . 3.7-46 3.7.5 Combined License Information .. .. . . .. . . . 3.7-48 3.7.6 References . . . ... . ..... ... ...... .. . . . 3.7-49 3.8 Design of Category I Structures . . . ..... . ......... .... .. . 3.8-1 3.8.1 Concrete Containment . . . . . . ... . .... ... .. 3.8-1
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| . 3.8.2 Steel Containment .. . . ........ .. . .... .. .. 3.8-1 4
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| Revision: 10 W85tmgh0US8 y December 26,1996
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| [ Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.8.3 Concrete and Steel Intemal Structures of Steel Containment . 3.8-16 3.8.4 Other Category I Structures . . . . . . .... ........ . 3.8-39 3.8.5 Foundations . .. . .. . .. .. . . . . . 3.8-53 3.8.6 Combined License Information ... ... . .. ..... 3.8-60 3.8.7 References . . . . . . ... .. . ..... . ....... . . 3.8-60 Volume 3 3.9 Mechanical Systems and Components ....... . . ........ .. ... 3.9-1 3.9.1 Special Topics for Mechanical Components .... ..... ... . 3.9-1 3.9.2 Dynamic Testing and Analysis . . . . . . ............ . 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Components, Component Supports, and Core Support Structures . . ... . . 3.9-45 3.9.4 Control Rod Drive System (CRDS) . ............. .. . 3.9-71 3.9.5 Reactor Pressure Vessel Internals . . . ... .. .. . 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . .... .. ..... . 3.9-89 3.9.7 Integrated Head Package . . ... . . . .... . . . . . . . . 3.9-97
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| ! 3.9.8 Combined License Information ........... .... ..... 3.9-102 3.9.9 References .. ... ......... .. . ...... .... .. 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and l Electrical Equipment . . . . . . . . ............ ... ......... . 3.10-1 3.10.1 Seismic and Dynamic Qualification Criteria ..... .. ... 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Instrurnntation, and Mechanical Components ......... . . 3.10-3 l 3.10.3 Method and Procedures for Qualifying Supports of Electrical !
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| l Equipment, Instrumentation, and Mechanical Components . . . . . 3.10-7 l 3.10.4 Documentation . ... . ... . . . ... . 3.10-7 3.10.5 Standard Review Plan Evaluation . . ... ..... . 3.10-7 3.10.6 Combined License Information Item on Experienced-Based Qualification . . .... . . . . . . . . 3.10-8 3.10.7 References .. .. .. .... .... . 3.10-8 l 3.11 Environmental Qualification of Mechanical and Electrical Equip' ment . . 3.11-1 i 3.11.1 Equipment Identification and Environmental Conditions . . 3.11-1 j 3.11.2 Qualification Tests and Analysis . .. . .. .. 3.11-3 l 3.11.3 Loss of Ventilation .. . .. . . . . 3.11-4 l 3.11.4 Estimated Radiation and Chemical Environment .. . . . 3.11-5 l 3.11.5 Combined License Information item for Equipment Qualification File ...... ... .. .. .. .. 3.11-5 3.11.6 References . . . ... ... .. 3.11-6 9 :
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| Revision: 10 December 20,1996 vi W Westinghouse
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| l Section Title Para APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS . ... ... . . . . . 3A-1 3A.1 Codes and Standards . .... .. . . . . .. ... ....... . . 3A-1 3A.2 Loads and Load Combinations . ...... .. ...... .. .. . . 3A-1 3 A.2.1 Loads .. ....... .... ... .... ... .. .. . . 3A-1 3A.2.2 Load Combinations .. ...... .... . . 3 A-3 3A Analysis and Design . ...... .. ... .. ... . ... . . 3A-3 l 3 A.3.1 Response Due to Seismic Loads .. . . ... . . . . . . . . 3 A-3 3A.3.2 Deflection Criteria . .. . . .. ....... .. . 3A-3 j 3A.3.3 Relative Movement . . .. . ..... . . . . 3A-3 '
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| 3 A.3.4 Allowable Stresses . .. .. .. . .. .. . .. . 3A-4 3A.3.5 Connections . . . .. . .. .. ... .. ....... . . . 3 A-4 APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . . 3B-1 l 3B.1 Leak-Before-Break Criteria for AP600 Piping . .. . . .. .. . .. 3B-2 3B.2 Potential Failure Mechanisms for AP500 Piping . . ............ . .. . 3B-2 l 3B.2.1 Erosion-Corrosion Induced Wall Thinning . . . .. . . . 3B-2 3B.2.2 Stress Corrosion Cracking .... .. .. . .. . .. .. 3B-3 3B.2.3 Water Hammer .. ..... . . .. . . . . . . . . 3B-5 3B.2.4 Fatigue .. ... ........ .. .... . . .... . 3B-9 V) 3B.2.5 Thermal Aging .. ..
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| 3B.2.6 Thermal Stratification ..... ..
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| . 3B-9 3B-10 3B.2.7 Other Mechanisms .. ..... . . ... . . .. . . 3B-13 3B.3 Leak-Before-Break Bounding Analysis .... ..... .. .. . 3B-13 3B.3.1 Procedure for Stainless Steel Piping . . . . .. . . . . . . 3B-13 1 3 B.3.2 Procedure for Non-Stainless Steel Piping . . .. .. .... . 3B-16 l 3B.3.3 Evaluation of Piping System Usir.g Bounding Analysis Curves . . . 3B-17 l 3B.3.4 Bounding Analysis Results .. . ............ .... . 3B-21 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe .. .. ... . .. ... . ... . 3B-21 3B.5 Differences in Inspection Criteria for Class 1,2, and 3 Systems . ... . . 3B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping ... . . . . .. . . . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Lines .. 3B-21 A 3B.8 Augmented In-Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators . . .. . . . . . 3B-21A 3B.9 References . . . . ... . .. . 3B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS . . .. . . 3C-1 3C.1 Reactor Coolant Loop Model Description . . . . . . . . 3C-1 3C.l .1 Steam Generator Model . ... . . .. . . 3C-1 3C.I.2 Reactor Coolant Pump Model . . .. . .... 3C-2 3C.I .3 Reactor Pressure Vessel Model . . . . . 3C-2 l
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| Revision: 10 3 Westingt!OUSe yi December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title a age,
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| 3C.I .4 Containment Interior Building Structure Model . . ......... . 3C-3 3C.I.5 Reactor Coolant Loop Piping Model . . . .. ........... . 3C-3 3C.2 Design Requirements . .. .. . ......... . ... .. 3C-3 3C.3 Static Analyses . . . . . .. ... ..... . . . ...... ... 3C-4 3C.3.1 Deadweight Analysis . . . .. . ... .. . .. . . 3C-4 3C.3.2 Internal Pressure Analysis . . . ... . . ... . . . 3C-4 3C.3.3 Thermal Expansion Analysis . . .. . .. .. . 3C-4 3C.4 Seismic Analyses .. . .. . . . . .. . .. .. . 3C-4 3C.5 Reactor Coolant Loop Piping Stresses . . . . . .......... . .. 3C-5 3C.6 Description of Computer Programs . . . . . . . . . . .... . 3C-5 APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT . . . ... ... 3D-1 3D.1 Purpose . . ... .... ...... . .. .. . .. .. ... .. 3D-2 3D.2 Scope..... ...... . . ... . . . .. . ... . . 3D-2 3D.3 Introduction . . . . . . ... . ... .... ... . . .. .. . . 3D-3 3D.4 Qualification Criteria . . . . .. . .. . ..... . . . . 3D-3 3D.4.1 Qualification Guides ... . . .. . .. . .. . . 3D-3 3D.4.2 Definitions . . .. ... ... ... ........... .. 3D-7 3D.4.3 Mild versus Harsh Environments . .. .. .. . 3D-7 3D.4.4 Test Sequence . . . .. .... . .. .. . . ...... . 3D-8 ,
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| 3D.4.5 Aging . . . . . . ... . .. . .. . . ... ... .. . . 3D-9 !
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| 3D.4.6 Operability Time . . . . .. . . .. . ... . . 3D-12 3D.4.7 Performance Criterion ... . .. . . . . . 3D-12 3D.4.8 Margin ..... . .. .. . .... ... .... . 3D-12 3D.4.9 Treatment of Failures .. ... ... . . .... . . 3D-15 3D.4.10 Traceability ..... ... .. . . .. . . . ... 3D-16 3D.5 Design Specifications . . . . .. .. . .... . 3D-17 3D.5.1 Normal Operating Conditions . . . . .. . 3D-18 3D.5.2 Abnormal Operating Conditions . . .. .. . 3D-19 1 3D.5.3 Seismic Events . . .. .... . ... . . .... . 3D-20 )
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| 3D.5.4 Containment Test Environment . ... .. . . 3D-20 l 3D.5.5 Design Basis Event Conditions . . . . 3D-20 3D.6 Qualification Methods . . . . .. . .. . . . . 3D-24 3D.6.1 Type Test ........... . ... . . . . . . 3D-25 3D.6.2 Analysis .. . ... . .. . . 3D-25 3D.6.3 Operating Experience . . . . . . 3D-30 l 3D.6.4 On-Going Qualification . . . .. . . . . . 3D-30 l 3D.6.5 Combinations of Methods .. .. . . ..... 3D-30 Ol Revision: 10 December 20,1996 viii 3 W85tingh00S8
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| :--n Master Tcble of Contents i
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| e G) MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Eage a
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| 3D.7 Documentation . . . . . . . . . . . ......... ... ... ...... . 3D-31 3D.7.1 Equ'pment Qualification Data Package .. ....... .. . . . . 3D-32 3D.7.2 Specifications . . . . . . . ....... . . .. . . . . . . . . . . . . . . 3 D-3 2 3D.7.3 Qualification Program . . . . . . .. . .. .... . ... . 3D-34 3D.7.4 Qualification by Test . ...... . . ... . . .. . . . . . . . . 3D-34 3D.7.5 Qualification by Analysis ..... ......... .. ..... 3D-37 3D.7.6 Qualification by Experience . . . . . . . . . . .... .......... 3D-37 3D.7.7 Qualification Program Conclusions . . . . . . ....... .. . . . 3D-37 3D.7.8 Combined License Information . . .. .. .. .. .. . . . . . 3D-38 3D.8 References . . . . .. ............ ......... ...... ... . . 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package . . . .. .. 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program ... . . ......... .. . 3D-87 B.1 Introduction . . .. ......... ... ... . . ... . . . .. . . 3D-87 B.2 Objectives .. ... .... ..... . ..... ............. . . . 3D-87 B.3 Basic Approach . ............... .... .. ...... .. .. . . 3D-87 B.4 Subprogram A ..... . ... ... .... ... . .. . ... . . . 3D-88 (3 B.4.1 Scope ...... . ... ..... .. ..... ..... . .. . 3D-88
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| (,_) B.4.2 Aging Mechanisms . . ...... . . . ..... .. ... . 3D-88 B.4.3 Time ........ . . . ..... .. . ........ . . . . . 3D-88 B.4.4 Operational Stresses . ... .. ......... ...... .. .... 3D-89 B.4.5 External Stresses . ..... .. .. . ........ .... . . . 3D-89 B.4.6 Synergism . . ... . . ........ .. .... ....... . 3D-91 B.4.7 Design Basis Event Testing . . .. .... . .... ........ 3D-91 B.4.8 Aging Sequence . . . .. .... . ..... ....... . . . . . . 3D-91 B.4.9 Performance Criterion . . .. . .. ...... .. ... . . 3D-91 B.4.10 Failure Treatment . .. ........ . ....... ...... . 3D-91 B.5 Subprogram B ... .......... ...... .... . . .. ... . . 3D-92 B.5.1 Scope ... .. . . .... .... .... .. .... ... . 3D-93 B.5.2 Performance Criteria . .... . . . .. .. . . .. . . 3D-93 l B.S.3 Failure Treatment . . . . . ..... ..... . . . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials ....... . . 3D-96 C.1 Introduction . . . .. . .. .. .. ..... . . . .. . 3D-96 C.2 Scope.... .. . . . . . .. . . .. .. 3D-97 C.3 Discussion . . . . . . .. . ..... . . . . ... . 3D-97 C.4 Conclusions .. .. . .. . .. . . .. . . .. . 3D-98 l
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| , C.5 References . . ... .. ... .. . ... .. .. . . 3D-98 ir 's (m )
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| i Revision: 10
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| Section Title Page Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . . . . . . . . .. . 3D-103 D.1 Introduction . . .......... . . . .. .. ............... 3D-103 D.2 Arrhenius Model . .. .. . . . . . . ..... . . 3D-103 D.3 Activation Energy ...... .. .... . ... . .. . 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) . . .... . 3D-106 D.4.1 Normal Operation Temperature .. . .. . 3D-106 D.4.2 Accelerated Aging Temperature . ... . .... . . . . 3D-107 D.4.3 Examples of ArThenius Calculations . . . . . . . . . .. 3D-107 D.5 Post-Accident Thermal Aging . . . .. .. . . . .. ... .... . . 3D-108 D.5.1 Post-Accident Operating Temperatures ...... . . . . . . 3D-108 D.5.2 Accelerated Thermal Aging Parameters for Post-Accident Conditions . . . . . . . . . . . .. . ... . .. . . . 3D-109 D.6 References . . . . . ........... . .... . . . . . 3D-109 Appendix 3D-Attachment E - Seismic Qualification Techniques ... .... .... 3D-115 E.1 Purpose . . . . . . . . . . . . ... ... . .. ... ... . .... . 3D-Il5 E.2 Definitions . .... ..... ...... .. .. . ... . .. .... 3D-Il5 j E.2.1 1/2 Safe Shutdown Earthquake . . . .... ... . . 3D-Il5 i E.2.2 Seismic Category I Equipment . . .. .. .. .... . . . . 3D-115 E.2.3 Active Equipment . . .. . . ..... . ... . . 3D-Il5 E.2.4 Passive Equipment .. . ..... . ..... ... .. .. 3D-ll5 E.3 Qualification Methods . . . . . . . ...... ...... . .. ... . .... 3D-Il6 E.3.1 Use of Qualification by Testing . . .. . . . . . . . . . . 3 D- 1 16 E.3.2 Use of Qualification by Analysis ... . . ... .. . . 3D-116 E.4 Requirements .... .......... ... ..... ... .. . . . . . 3D-I l 7 E.4.1 Damping ....... . .... ... . .. .. . . . . . 3D-Il7 E.4.2 Interface Requirements ... . . . . .. 3D-117 E.4.3 Mounting Simulation . . . . . .. . .. . . .. 3D-118 E.4.4 1/2 Safe Shutdown Earthquake . . . . 3D-118 E.4.5 Safe Shutdown Earthquake . . . ... . ..... 3D-118 E.4.6 Other Dynamic Loads . . . .. . . . 3D-118 E.5 Qualification by Test . . . . . . . . . . . . ... . . . . 3D-118 E.5.1 Qualification of Hard-Mounted Equipment . . . . 3D-Il9 E.5.2 Qualification of Line-Mounted Equipment .. .. . . 3D-120 E.5.3 Operational Conditions . . ... . . . 3D-122 E.5.4 Resonant Search Testing . . . . . . 3D-123 E.6 Qualification by Analysis . . . . .... ... ... . . . . . 3D-123 E.6.1 Modeling . . .... . . . .... . . . ... . 3D-124 E.6.2 Qualification by Static Analysis . . . . . 3D-124 E.6.3 Qualification by Dynamic Analysis . . . . 3D-124 O
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| Revision: 10 December 20,1996 x 3 Westinghouse
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| Master 'Itble of contents
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| (v) MASTER TABLE OF CONTENTS (Cont.)
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| 1 Section Title _P_ age l E.7 Performance Criteria . . . .. ......... .. .... . .. .... . 3D-126 E.7.1 Equipment Qualification by Test . ... .... . . . . . . . . . 3D-126 E.7.2 Equipment Qualification by Analysis .. .. . .... .. . . . . 3D-126 i l
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| APPENDIX 3E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND .. ... . 3E-1 1
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| APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS ..... ... . 3F-1 ;
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| 3F.1 Codes and Standards . .. . . .. ... ... ....... ... . . 3F-1 3F.2 Loads and Load Combinations . . . . . . . ........ . . . 3F-1 3F.2.1 Loads ....... .. ... . .. ... . ....... . . 3F-1 3F.2.2 Load Combinations . . . .. . ... ... . . .... .. . 3F-2 !
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| 3F.3 Analysis and Design . .. . ........ . . . .. . ..... 3F-2 3F.3.1 Damping . . ..... . .... . . ..... ... ..... . 3F-2 3F.3.2 Seismic Analysis ....... . . .. ... . . .... ... . 3F-3 l 3F.3.3 Allowable Stresses . . ..... . . .... . . . . . . 3 F-3 !
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| 3F.3.4 Connections . . . . . . . .. . .. .. .. . . . . . . . . . . 3 F-3 l
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| l CHAPTER 4 REACTOR....... .... ....... . .. .. .... . . 4.1-1 I (3 4.1 Summary Description ........ .. . . . . ........ .. . 4.1-1 !
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| V 4.1.1 Combined License Information . . . ..... ... ........ 4.1-4 4.1.2 References . . . . . . . . . .. . ... . . ......... ...... 4.1-4 4.2 Fuel System Design . . ..... .. .. ......... ....... 4.2-1 4.2.1 Design Basis . . . . . . . . .. .. . .. . . . .. ...... .. 4.2-2 4.2.2 Description and Design Drawings . .. .. . ......... . . 4.2-9 4.2.3 Design Evaluation . . . . . ........ . .. . ........ . 4.2-20 ,
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| 4.2.4 Testing and Inspection Plan . . .. . . . . . .. . . . 4.2-32 l 4.2.5 Combined License Information .. . .. . . . . . . . . . . 4.2-3 7 l 4.2.6 References . . . . . .. .. .... . . . ... . . . . 4.2-37 4.3 Nuclear Design . . . ...... . . . . . ..... .. ... . 4.3-1 4.3.2 Description . .. . ... . . ... . . . 4.3-7 !
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| 4.3.3 Analytical Methods . . .. ....... . 4.3-39 4.3.4 Combined License Information . .. . . .. 4.3 '2 4.3.5 References . ... . .. .. . . .... 4.3-42 4.4 Thermal and Hydraulic Design . . . .. . ........ . . 4.4-1 4.4.1 Design Basis . . ... .. ... . . ....... . 4.4-1 4.4.2 Description of Thermal and Hydraulic Design of the Reactor Core .. 4.4-4 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System . . . ....... . . .... ... 4.4-201 4.4.4 Evaluation . . . ...... . ... . . . . . .. 4.4-21 4.4.5 Testing and Verification . . . . . .. . 4.4-30 4.4.6 Instrumentation Requirements . . . .. . .. 4.4-31 n 4.4.7 Combined License Information .. . . . . . . 4.4-35 V) f Revision: 10
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| [ W85tingh0USB xi December 20,1996
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| 1 rm Master Table cf Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 4.4.8 References . ......... . . ... ... . . . 4.4-35 4.5 Reactor Materials . . . . . .... ... .... ...... .. . . . . 4.5-1 4.5.1 Control Rod and Drive System Stmetural Materials . . . . . 4.5-1 4.5.2 Reactor Internal and Core Support Materials . . . .... .. 4.5-3 4.5.3 Combined License Information . ... ... . . ...... 4.5-4 4.5.4 References . .. ........... .. . .. .. . . 4.5-4 4.6 Functional Design of Reactivity Control Systems ....... ... . .. .. 4.6-1 4.6.1 Information for Control Rod Drive System . . . . . . .. .. . . 4.6-1 4.6.2 Evaluations of the Control Rod Drive System .. .... ...... .. 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System . . . . .. . 4.6-2 4.6.4 Information for Combined Performance of Reactivity Systems ..... 4.6-2 4.6.5 Evaluation of Combined Performance . ... . . .. .. . ... 4.6-3 4.6.6 Combined License Information . . . . . . ... 4.6-4 Volume 4 CHAIYTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS ... . . . 5.1-1 5.1 Summary Description ...... . .. ..... .. .. ... . .. . 5.1-1 5.1.1 Design Bases . . ....... . .. . .. . . .. . ... . . . 5.1-1 5.1.2 Design Description . . . . . . . . . . ... ......... . . . . . . . 5.1 -2 5.1.3 System Components . . ... . . ..... ... . . . . . 5.1-4 5.1.4 System Performance Characteristics . ..... .. . .... . . . . 5.1-7 5.1.5 Combined License Information . . . ...... ... ....... .. . 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary . . . . . . . . ..... ....... 5.2-1 5.2.1 Compliance with Codes and Code Cases . .. .... ... . ... . 5.2-1 5.2.2 Overpressure Protection . . . . ... . ......... .. . . . 5.2-2 5.2.3 Reactor Coolant Pressure Boundary Materials .. ..... ... . 5.2-7 5.2.4 Inservice Inspection and Testing of Class 1 Components .... . 5.2-17 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Bounday . 5.2-20 5.2.6 Combined License Information Items .. . . . . . 5.2-29 5.2.7 References . . . . . . ..... .. . . 5.2-29 5.3 Reactor Vessel . ....... . . . . .. . . .. . . . 5.3-1 5.3.1 Reactor Vessel Design ... ... . .. . . . 5.3-1 5.3.2 Reactor Vessel Materials . . . . .. . . . . 5.3-4 5.3.3 Pressure-Temperature Limits . .. . . . 5.3-13 5.3.4 Reactor Vessel Integrity .. ... . . ... 5.3-14 5.3.5 Combined License Information . .. . . .... 5.3-19 5.3.6 References . .... . . . . . 5.3-20 5.4 Component and Subsystem Design .. . . . . . . 5.4-1 5.4.1 Reactor Coolant Pump Assembly . ... ... . . 5.4-1 0,
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| Revision: 10 December 20,1996 xii 3 W85tingh0USe I
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| Section Title Eage 5.4.2 Steam Generators . . . .... .... . . . ...... 5.4-10 l 5.4.3 Reactor Coolant System Piping ..... ...... .. ...... 5.4-23 5.4.4 Main Steam Line Flow Restriction ...... .... . . ... .. 5.4-28 5.4.5 Pressurizer . . . . . . . . . . . . . .... ...... .. . . . . . . . . 5.4-29 5.4.6 Automatic Depressurization System Valves ... ........... 5.4-36 5.4.7 Normal Residual Heat Removal System .... .... ....... . 5.4-38 5.4.8 Valves . . . . ....... ........... ..... .. .... . 5.4-51 5.4.9 Reactor Coolant System Pressure Relief Devices . . . ....... 5.4-57 5.4.10 Component Supports . . .. . .. .... ... .... . 5.4-60 5.4.11 Pressurizer Relief Discharge .. . .... . .. . ..... . 5.4-63 5.4.12 Reactor Coolant System High Point Vents .... .. .. . . 5.4-65 5.4.13 Core Makeup Tank . . . . . .... .... ..... ......... . 5.4-68 5.4.14 Passive Residual Heat Removal Heat Exchanger ... ........ 5.4-71 5.4.15 Combined License Information . . . ... . ...... .... .. 5.4-74 5.4.16 References ........ .. ....... . . . . . . . . . . . 5.4-74 !
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| CHAPTER 6 ENGINEERED SAFETY FEATURES . ...... . .. . ... . . . ... . 6.0-1 6.1 Engineered Safety Features Materials . ... .... . . .......... 6.1-1
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| ; 77 6.1.1 Metallic Materials . . . .... .. .. .. ....... . . . 6.1 -1 j () 6.1.2 Organic Materials . . ....... . . . ... . .......... 6.1-5 6.1.3 Combined License Information Items . . . . . . . . . . . . . . . . . . . . 6.1 - 1 1 6.1.4 References . . . . . . . . . . . . . . . .. ...... ...... . 6.1-12 6.2 Containment Systems . . . . . . . . . . . . . . .. .. . . . ... ..... 6.2-1 6.2.1 Containment Functional Design . . . ... ........... .. 6.2-1 6.2.2 Passive Containment Cooling System . .. . . ........ . 6.2 20 6.2.3 Containment Isolation System .. .. .. ..... .... ... 6.2-28 6.2.4 Containment Hydrogen Control System . . . . .. ........ .. 6.2-378 6.2.5 Containment Leak Rate Test System . . ... ...... . . . . . . . 6.2-48 6.2.6 References . . . . . . . . . . . .. . . . . .. .... .... . 6.2-55 6.3 Passive Core Cooling System .. . . . . . .......... . 6.3-1 6.3.1 Design Basis . . . . .. . . . . .. . . . 6.3-2 6.3.2 System Design . . . . . . .. ... . . . .. .. . . . 6.3-6 6.3.3 Performance Evaluation . . . . .. . .... . . 6.3-28 6.3.4 Post-72 Hour Actions . .. ... . . . . ..... . . 6.3-41 l 6.3.5 Limits on System Parameters ..... . .. . .. . 6.3-41 ;
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| ! 6.3.6 Inspection and Testing Requirements . . . ... .. . 6.3-42 1 6.3.7 Instrumentation Requirements ... . .. . . 6.3-43 6.3.8 Combined License Information . . . . . . . . . . 6.3-48 6.3.9 References ... .... . . . . . 6.3-48 i Habitability Systems . . . . . . . . .
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| 6.4 . . . . . . . 6.4-1 6.4.1 Safety Design Basis .. . .... . ..... ... .. . 6.4-1 6.4.2 System Description ..... . . . . . ... 6.4-2
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| , 6.4.3 System Operation . . . .. . . .. . 6.4-6 (v)
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| ( Revision: 10
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| Section Title Page 6.4.4 System Safety Evaluation .... . . . . . .... 6.4-8 6.4.5 Inservice Inspection / Inservice Testing . ... .... .. . . . 6.4-10 6.4.6 Instrumentation Requirements . . . .. .... ...... 6.4-10 6.4.7 Combined License Information . . . . .. .. .. . . 6.4-11 6.4.8 References . . . . . . . . . . . . ..... .. ... .. . . 6.4-11 6.5 Fission Product Removal and Control Systems . . . . . . .. .. 6.5-1 6.5.1 Engineered Safety Feature (ESF) Filter Systems . . . . . . 6.5-1 6.5.2 Containment Spray System . .. ... .. . . ...... .. . 6.5-1 6.5.3 Fission Product Control Systems . . . . . . . . 6.5-1 6.5.4 Combined License Information . . . ... .. ... . ....... . 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components .. .............. . 6.6-1 6.6.1 Components Subject to Examination .. . .... . . ... 6.6-1 6.6.2 Accessibility ... . . . ... . . . . . . ... . 6.6-1 6.6.3 Examination Techniques and Procedures . .... . . 6.6-2 6.6.4 Inspection Intervals . ... .,... . .. . ..... ..... 6.6-3 6.6.5 Examination Categories and Requirements . .. . .. ... .. 6.6-3 6.6.6 Evaluation of Examination Results ..... ..... ...... . . 6.6-3 6.6.7 System Pressure Tests . .. ....... . .. ....... ....... . 6.6-3 '
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| 6.6.8 Augmented Inservice Inspection to Protect against Postulated Piping Failures .... ... . . ....... . ...... . 6.6-3 6.6.9 Combined License Information Items . . . ... .... .. . 6.6-4 CHAPTER 7 INSTRUMENTATION AND CONTROLS . . . . . .. ... . . . 7.1-1 7.1 Introduction .. . .... ... ..... .. . .. .. ..... ...... 7.1-1 7.1.1 The AP600 Instmmentation and Control Architecture . . . ... 7.1-2 7.1.2 General Protection Subsystem Configuration . . . . ...... .. .. 7.1-6 7.1.3 Plant Control System . . . . . .. .. .. . . . . . . . 7.1 -27 7.1.4 Identification of Safety Criteria .. .. . .. . 7.1-32 7.1.5 AP600 Protective Functions . . . .. ... 7.1-48 ;
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| 7.1.6 Combined License Information . . . .. .... 7.1-48 1 7.1.7 References . . . . . . ... .. 7.1-49 ;
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| 7.2 Reactor Trip . . . .. ..... .. . . 7.2-1 !
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| 7.2.1 Description . . .. . . .. . . . . 7.2-14 7.2.2 Analyses . . . . ... . . ... .... 7.2-14 7.2.3 Combined License Information . . .. . . . 7.2-17 7.2.4 References . ..... . . . . . . . 7.2-17 7.3 Engineered Safety Features . . . . . . .. . . .. . 7.3-1 7.3.1 Description .... ... .. . . . . . ... . 7.3-1 7.3.2 Analysis for Engineered Sa..ay Features Actuation . 7.3-19 7.3.3 Combined License Information . ... . . .. . 7.3-22 7.4 Systems Required for Safe Shutdown . . . . . .. ... . ... 7.4-1 O
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| Revision: 10 December 20,1996 xiv [ W85tillghouse
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| ; /m i I i i C/ . MASTER TABLE OF CONTENTS (Cont.)
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| ! l Section Title P_aage l
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| l 7.4.1 Safe Shutdown . . . . ..... . ... .. .. ... . . . 7.4-3 7.4.2 Safe Shutdown Systems . ........... .. .. ..... . . . 7.4-10 ;
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| 7.4.3 Safe Shutdown from Outside the Main Control Room . . . . . . . . 7.4- 1 1 7.4.4 Combined License Information . . . . .. . .. . .. . 7.4-14 i
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| 7.4.5 References ............. .. ..... . ... ....... .. 7.4-14 1 7.5 Safety-Related Display Information . . . .. . .. . . .. .. 7.5-1 7.5.1 Introduction . ........... .... . . . . . . . .. ... 7.5-1 7.5.2 Variable Classifications and Requirements . ... .. . .. . . . 7.5-1 ;
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| 7.5.3 Description of Variables . ...... .. . . .... .... . . . 7.5-9 !
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| 7.5.4 Processing and Display Equipment . ... .. . .. .. . . . . . 7.5-11 7.5.5 Combined License Information . . ..... ..... .. . . . 7.5-13 l 7.6 Interlock Systems Important to Safety . . . . . ..... . 7.6-1 7.6.1
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| l Prevention of Overpressurization of Low-Pressure Systems . .. 7.6-1 l 7.6.2 Availability of Engineered Safety Features . .. .. .... . 7.6-2 7.6.3 Combined License Information . . . . .... .... .. . ... . 7.6-5 7.7 Control and Instrumentation Systems . . .... .. . ... .. . 7.7-1 7.7.1 Description . ... .. . . . . .. ..... . . . . 7.7-2 7.7.2 Analysis .... ..... .... . . ... .... ..... . . 7.7-20 4
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| (~'Ni 7.7.3 Combined License Information . . ..... . .. . . . . . . . . 7.7-21 Volume 5 CHAPTER 8 ELECTRIC POWER . . . ... .... ... . .... ....... . . 8.1-1 8.1 Introduction . .. .... . . . . . ... . .............. . 8.1-1 j 8.1.1 Utility Grid Description . . . . . . . .... ... ... . . 8.1-1 8.1.2 Onsite Power System Description . . . . . . .... ... . 8.1-1 8.1.3 Safety-Related Loads . .. , ... .... . . ... . 8.1-2 8.1.4 Design Basis . . . . . . . .... .... ..... . . . . . 8.1-2 8.1.5 Combined License Information . . . .. . . . .. .. . . . 8.1-5 8.2 Offsite Power System . . . .. ... . .. .. . .. . .. . . 8.2-1 8.2.1 System Description . .... . . . . . . .. 8.2-1 8.2.2 Conformance to Criteria . . .... .. . .. . . 8.2-2 1 8.2.3 Standards and Guides . .. . .. .. . .. . 8.2-2 i 8.2.4 Combined License Information for Offsite Electrical Power . .. 8.2-2 8.2.5 References . . . . . . .. . 8.2-2
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| ; 8.3 Onsite Power Systems . . . . . . . .. .. .. . . . . 8.3-1
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| ; 8.3.1 AC Power Systems . . . .. . .. 8.3-11 l
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| 8.3.2 DC Power Systems . . . ... . . . . . . 8.3-13 8.3.3 Combined License Information for Onsite Electrical Power . . 8.3-21 8.3.4 References . . .. .. ... . . . . . . 8.3-22 3 4 m) l Revision: 10 l [ Westingh00S8 xy December 20,1996 I
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| Section Title Page CHAPTER 9 AUXILIARY SYSTEMS . . . . ... .... . ... . ... .. ....... 9.1-1 9.1 Fuel Storage and Handling . . ..... . . .. . . . 9.1 - 1 9.1.1 New Fuel Storage . . .. . . .. ... ... . .. 9.1-1 9.1.2 Spent Fuel Storage ... . . ... . .. .. . . 9.1-5 9.1.3 Spent Fuel Pool Cooling System .... .... .. . .. . . 9.1-10 9.1.4 Light Load Handling System (Related to Refueling) . . . . . . . 9.1-21 9.1.5 Overhead Heavy Load Handling Systems . . . . . . . . . . 9.1 -34 9.1.6 Combined License Information for Fuel Storage Handling . ... 9.1-40 9.1.7 References ..... ............. . . .. . . . . . 9.1-40 9.2 Water Systems . ....... . . ... .... .. . . . .. . 9.2-1 9.2.1 Service Water System .. . .. ... . . 9.2-1 9.2.2 Component Cooling Water System . ... . . . .... .. 9.2-7 9.2.3 Demineralized Water Treatment System . ........... . . . . 9.2-16 9.2.4 Demineralized Water Transfer and Storage System . .. ..... . 9.2-20 9.2.5 Potable Water System . . .... . . ... . . . 9.2-25 9.2.6 Sanitary Drainage System . . . . . . . ... . . ... .. 9.2-28 9.2.7 Central Chilled Water System ... .. . . ... .... . . . . . . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . .. .... . 9.2-36 9.2.9 Waste Water System . . . .. .. ..... .. .. . 9.2-40 9.2.10 Hot Water Heating System .... . .. . ....... 9.2-44 9.2.11 Combined License Information . . . . .. ... . . ... 9.2-47 9.2.12 References . .. . .. . . . .. .. . . .. . 9.2-48 9.3 Process Auxiliaries . . . . . . . . . . . ....... .. . . . . . . . . . 9.3- 1 9.3.1 Compressed and Instrument Air System . ... . ... .... 9.3-1 9.3.2 Plant Gas System . .. ..... . . . .. . . . . 9.3-7 9.3.3 Primary Sampling System . . . . . . . . ... . . .. 9.3-10 9.3.4 Secondary Sampling System ........ . . ... .. .... . 9.3-15 9.3.5 Equipment and Floor Drainage Systems .. . ... . . . 9.3-17 9.3.6 Chemical and Volume Control System . . ... . .. 9.3-22 9.3.7 Combined License Information . . . . . 9.3-43 9.3.8 References .. . ....... . .. . . 9.3-43 Volume 6 9.4 Air-Conditioning Heating, Cooling, and Ventilation System . . . . 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System . . . . 9.4-1 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System . . 9.4-15 9.4.3 Radiologically Controlled Area Ventilation System .. . . . 9.4-26 l 9.4.4 Balance-of-Plant Interface . . . . ... . .. . . 9.4-36 9.4.5 Engineered Safety Features Ventilation System ... .. . . . 9.4-36 O
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| Section Title Pam 9.4.6 Containment Recirculation Cooling System . . . . . . . . . . . . . . . . 9.4-36 9.4.7 Containment Air Filtration System . . . . . . . . . . . . . . . . . . . . . . . . 9.4-41 9.4.8 Radwaste Building HVAC System . . . . . . . . . . . . . . . . . . . . . . . 9.4-4 9 9.4.9 Turbine Building Ventilation System ......... ........ . . 9.4-54 9.4.10 Diesel Generator Building Heating and Ventilation System .... . 9.4-59 9.4.11 Health Physics and Hot Machine Shop HVAC System . . . . . . . . . 9.4-65 9.4.12 Combined License Information . . ... ............. . . . 9.4-70 9.4.13 References . . . . . . ........... .. .. . . . . . . . . . . . . . 9.4-70 9.5 Other Auxiliary Systems . . . . . . . . . . . .. ... ...... ...... . .. . 9.5-1 9.5.1 Fire Protection System . . . . . . . . . . . . . . .. . .... . . . . .. .. . . . 9.5-1 9.5.2 Communication System . . . . . . . . . . ..... ........... . . 9.5-14 9.5.3 Plant Lighting System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.5- 18 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System . . . . . . . . 9.5-21 9.5.5 References . . . . . . . . ....... .. .. ..... .......... . 9.5-27 APPENDIX 9A FIRE PROTECTION ANALYSIS ... ....... ......... . . 9A-1 9A.1 Introduction . . . . . . . ......... .... .. . .. ................9A-1 9A.2 Fire Protection Analysis Methodology . . . . . . . . ....... . . . . . . . . . . 9 A- 1 7
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| 9A.2.1 Fire Area Description . . . . . .... ................. .... 9A-1
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| ( 9A.2.2 Combustible Material Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-2 9A.2.3 Fire Severity Categorization . . . . . . . .................... . 9A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations . . . . . . . . . . . . . . . ... .... . . . . . . . . . . . . . . . . 9 A-2 9A.2.5 Fire Protection Adequacy ........................... . .. 9A-3 9A.2.6 Fire Protection System Integrity . . . . . .... .... .......... . 9A-4 9A.2.7 Safe Shutdown Evaluation . . . . . . . . . . . . . . . . ......... . . . . 9A-4 9A.3 Fire Protection Analysis Results . . . . . . . . . ..... . ............ 9A-8 9A.3.1 Nuclear Island . . . . . . .... .... .. ..................9A-9 9A.3.2 Turbine Building . . . . . ......., ..... . ... ..... . . . 9A-61 9A.3.3 Yard Area And Outlying Buildings . . .............. . . . 9A-72 9A.3.4 Annex I and II Buildings ......... . ............... . 9A-72 9A.3.5 Radwaste Building . . ....... ........ .. .......... 9A-88 ;
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| 9A.3.6 Diesel Generator Building . . . . .. ... . .. ..... . . 9A-90 ;
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| 9A.3.7 Special Topics . . . . . . . ...... . . ......... . . . 9A-94 l 9A.4 References . . . . . . ...... .. .. .. . . .. . ....... .. . . 9A-97 Volume 7 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM . . . . . . . . . . . . . . . . 10.1-1 10.1 Summary Description ....... .......... .. . ......... . . 10.1-1 10.1.1 General Descriptionn . . .. . ... . ........ ... . . 10.1-1 l 10.1.2 Protective Features . . . . . . . . . . . . . . . . . .. . ... . . . . . 10.1-2 {
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| Section Title Page :
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| 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . .. 10.1-4 j 10.2 Turbine-Generator . . ..... . . ... .. . .. .. .. 10.2-1 !
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| 10.2.1 Design Basis ........ .... . .. . ... . . .. 10.2-1 10.2.2 System Description .. .. . . .. . . .. .. . 10.2-1 10.2.3 Turbine Rotor Integrity . . . . . . . . ... . ... 10.2-11 10.2.4 Evaluation ............... .. .. ... ......... . 10.2-17 10.2.5 Instrumentation Applications . . ... . . . . . .... 10.2-17 10.2.6 Combined License Information on Turbine Maintenance and Inspection ... ... . . . ... .... . ... 10.2-19 10.2.7 References ...... ..... . ..... . . .. . . . .. 10.2-19 10.3 Main Steam Supply System . . . ... .. ... . . . 10.3-1 10.3.1 Design Basis . ..... .. . .. . . . . . 10.3-1 10.3.2 System Description .. .. . . . . . . .. 10.3-4 10.3.3 Safety Evaluation . ... .... . .. . .. . 10.3-10 10.3.4 Inspection and Testing Requirements . ... .. . .. . . 10.3-12 10.3.5 Water Chemistry ... ..... ... . ......... .. ... 10.3-12 i 10.3.6 Steam and Feedwater System Materials . . . . . ...... . 10.3-16 10.3.7 Combined License Information . . . . . . .......... ....... 10.3-17 '
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| 10.3.8 References ... .. ...... . . ... . .. ....... 10.3-17 10.4 Other Features of Steam and Power Conversion System .. . ... . . . . 10.4-1 i 10.4.1 Main Condensers ... .... .. . . .. .. . .. . . 10.4-1 i 10.4.2 Main Condenser Evacuation System . . . . . . .... .. . 10.4-4 l 10.4.3 Gland Seal System . .... . 10.4-6 l
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| 10.4.4 Turbine Bypass System .. ... . ..
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| .. .... .. . . .. 10.4-8 10.4.5 Circulating Water System ... ..... .. .. ... ... 10.4-12 10.4.6 Condensate Polishing System . . . . ... . . . .. 10.4-17 10.4.7 Condensate and Feedwater Systems .. .. ... . .. 10.4-20 l 10.4.8 Steam Generator Blowdown System . . . . ..... .. 10.4-35 l 10.4.9 Startup Feedwater System . . ..... . . . 10.4-44 10.4.10 Auxiliary Steam System . . . 10.4-53 10.4.11 Turbine Island Chemical Feed . . .. 10.4-56 10.4.12 Combined License Information . . . .. .. .. .. 10.4-59 10.4.13 References . . ... .. .. . . .. 10.4-59 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT . . .. . ... . . 11.1-1 11.1 Source Terms . . ... . .. . . . . . . . I1.1-1 11.1.1 Design Basis Reactor Coolant Activity ... . . . I1.1-1 11.1.2 Design Basis Secondary Coolant Activity . ... . . . I1.1-3 11.1.3 Realistic Reactor Coolant and Secondary Coolant Activity . . 11.1-4 11.1.4 Core Source Term . . . . . ... . .. .. . 11.1-4 O
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| Section Title Page 11.1.5 Process Leakage Sources . . . . .. . .... . I1.1-4 11.1.6 Combined License Information . . . . . . . ... . ..... . .. 11.1-4 I 11.1.7 References . . . .. . .. . .... . .. ... . . 11.1-5 l
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| 11.2 Liquid Waste Management Systems . . ..... . .. . ..... . 11.2-1 ,
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| 11.2.1 Design Basis ....... .. . . . 11.2-1
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| 11.2.2 System Description . ........ . .. ....... .. . 11.2-6 J 11.2.3 Radioactive Releases . . . . . ... .. .. .... 11.2-18 l 11.2.4 Combined License Information . . ..... . . ..... . I1.2-20 l 11.2.5 References . . . . . . .... .. .. . . . . .. . . . 11.2-20 11.3 Gaseous Waste Management System . ... . ... . . .. . . . I1.3-1 11.3.1 Design Basis ... . .. ...... . . . ...... .. I1.3-1 11.3.2 System Description .. . . . .. .... ..... . . 11.3-4 11.3.3 Radioactive Releases . . .. . .. .... . .. 11.3-9 11.3.4 Combined License Information . . . . . . . ... .. I1.3-11 :
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| 11.3.5 References . . . . . .. .. . . .. .. . . . . 11.3-11 I 11.4 Solid Waste Management .. .. .. . .. . ... ...... I1.4-1 11.4.1 Design Basis . . . ... . .... . . . .. .. . I1.4-1 11.4.2 System Description . ... ...... . .... ..... I1.4-3 (3 11.4.3 System Safety Evaluation . .. .. . ..... .......... . I1.4-13 C) 11.4.4 Tests and Inspections ..... . ... ... ......... 11.4-13 11.4.5 Quality Assurance . . ..... .......... . . .. ... . 11.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program . . . . . . . .. ... .... . .. I1.4-13 11.4.7 References . ... . ... ... ... . .. ... ... 11.4-14 i 11.5 Radiation Monitoring . . . . . .... ......... . . .. . . . . I1.5-1 l 11.5.1 Design Basis . .. ...... . .. . ........ . 11.5-1 !
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| 11.5.2 System Description . . . . ........ . .. ..... 11.5-2 11.5.3 Effluent Monitoring and Sampling . . . ..... . ..... . 11.5-13 11.5.4 Procets and Airbome Monitoring and Sampling . .. . 11.5-13 l 11.5.5 Post Accident Radiation Monitoring . . .. . 11.5-14 11.5.6 Area Radiation Monitors . . . . .... . . .... . 11.5-14 11.5.7 Combined License Information . . . . . . 11.5-17 CHAI'TER 12 RADIATION PROTECTION . . . . . . . . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As. Low-As-Reasonably Achievable (ALARA) . . . . . 12.1-1 12.1.1 Policy Considerations . ... 12.1-1 12.1.2 Design Considerations . . . . . . .. 12.1-2 12.1.3 Combined License Information . ... .. .. . . . .. 12.1-6 12.2 Radiation Sources . . . . . . ... . . . . . 12.2-1 12.2.1 Contained Sources ... . . . . . 12.2-1 12.2.2 Airborne Radioactive Material Sources 12.2-6 (m 8 C/
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| Section Title Page 12.2.3 Combined License Information . . . ... . ... . . 12.2-8 12.2.4 References . . . . . . . ....... . ... . . . ..... . ... . 12.2-8 12.3 Radiation Protection Design Features . . . . . ... . ... ... ... 12.3-1 12.3.1 Facility Design Features ... . . ..... . ..... .. . 12.3-1 12.3.2 Shielding . . . ....... . . ... ... ... .. 12.3-9 12.3.3 Ventilation . . . ........... . . . .. .... .. . 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation . . ...... . . . . . . . 12.3-19 12.3.5 Combined License Information . .. . .. 12.3-19 12.3.6 References . . .. .. ..... ... .. . . 12.3-19 12.4 Dose Assessment ... .. ...... . ... .. . .. .. . 12.4-1 12.4.1 Occupational Radiation Exposure ... ... . . . . . . . 12.4-1 12.4.2 Radiation Exposure at the Site Boundary . . ... .. . 12.4-4 12.4.3 Con'bined License Information . ... . ... . . .... 12.4-4 12.5 Health Physics Facilities Design . . ..... .. . . .... . .. . 12.5-1 12.5.1 Objectives . ......... . ... ... . . .. . . . 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities . . . ... ..... . 12.5-1 12.5.3 Other Design Features . . . . . .... . .... ..... . 12.5-3 12.5.4 Controlling Access and Stay Time . .. ... .. ... 12.5-4 12.5.5 Combined License Information . . . .. .. .. .. . 12.5-5 Volume 8 CHAPTER 13 CONDUCT OF OPERATION . .. .. . .... . . .. ... 13-1 13.1 Organizational Structure of Applicant .... . . . .. .. .... .. 13-1 13.1.1 Combined License Information Item . ....... ...... .. 13-1 !
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| 13.2 Training . . . . ....... . .... . ... .... ..... .. . 13-1 l 13.2.1 Combined License Information Item . .... . ,..... . . 13-1 13.3 Emergency Planning . .. . . ...... . . ... 13-1 13.3.1 Combined License Information Item . . ... .. .. 13-2 13.4 Operational Review . . . . . . ... .. .. . 13-2 13.4.1 Combined License Information Item . . . . .. . . 13-2 13.5 Plant Procedures . . .. . .. . . .. .... .. . .. . 13-2 13.5.1 Administrative Procedures . . . . . . . . .. 13-2 13.6 Industrial Security . .. . .. .. ... . ... . . . 13-3 13.6.1 Preliminary Planning . . . . .... . 13-3 13.6.2 Security Plan .. .. . .... .......... .. . 13-3 13.6.3 Plant Protection System . . . . .. . . . .. . .. 13-3 I 13.6.4 Physical Security Organization .. .. . .. .... 13-5 l 13.6.5 Physical Barriers . . . ... .. . .. 13-5 O.
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| Section Title fage 13.6.6 Access Requirements . ... .. .. . .... . .... . 13-6 13.6.7 Detection Aids . . .... ... ..... . . .... . ... 13-7 13.6.8 Security Lighting . . . . .. . . . .. ... ... . .... 13-7 !
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| 13.6.9 Security Power Supply System . . . .... ... .. ....... 13-7 13.6.10 Communications . . . .
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| .. .. .... . .. .. ... .. ... 13-7 13.6.11 Testing and Maintenance . . ... .. .. . .. . . .. . 13-8 l 13.6.12 Response Requirements .... . 13-8 l
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| 13.6.13 Combined License Information Item . .. .. .. . .. .... 13-8 13.7 References . . ..... . .. ... . ....... .. ... .... 13-8 CHAIYTER 14 INITIAL TEST PROGRAM . ... .. . . . .. .. .... .. .. . . 14.1-1 l 14.1 Specific Information to be Included in Preliminary / Final Safety i Analysis Reports . ....... ... .. ... .... ...... .. . . . . 14.1-1 14.2 Specific Information to be Included in Standard Safety Analysis Reports . . . . 14.2-1 14.2.1 Summary of Test Program and Objectives . . . ... ...... . 14.2-1 14.2.2 Organization, Staffing, and Responsibilities . .... ..... . 14.2-4 l 14.2.3 Test Specifications and Test Procedures .... .... .. . 14.2-4 14.2.4 Compliance of Test Program with Regulatory Guides ... . .. . 14.2-6
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| (~N 14.2.5 Utilization of Reactor Operating and Testing Experience in the
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| () Development of Test Program . . . ..... . ... ........ 14.2-6 14.2.6 Use of Plant Operating and Emergency Procedures . . . . . . . 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality . . . ... .. . . . . . . 14.2-7 14.2.8 Test Program Schedule .. . . ...... ...... ...... 14.2-10 14.2.9 Preoperational Test Descriptions . . . ...... .. ....... . . . 14.2-10 14.2.10 Startup Test Procedures .... ... .... . .......... . .. 14.2-80 14.3 Certified Design Material . . . . . . . . . . . . . . ... .... . . . . . . 14.3-1 14.3.1 CDM Section 1.0, Introductior' ...... ...... ... . . . 14.3-2 14.3.2 CDM Section 2.0, System Based Design Descriptions and ITAAC . . . . . . . . .... ..... . 14.3-3 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC . . . . . . . .. . .... .. . 14.3-9 14.3.4 Certified Design Material Section, 4.0 Interface Requirements 14.3-10 14.3.5 CDM Section 5.0, Site Parameters . .. . ... 14.3-10 14.3.6 Initial Test Program . . . .. .. .... . . 14.3-10 14.3.7 Summary . . . ... . .. ... . . . . 14.3-11 14.3.8 References . .. . . ... . . . .. . .... 14.3-11 14.4 Combined License Applicant Responsibilities . . . .. . .... 14.4-1 14.4.1 Organization and Staffing . . . . . . 14.4 1 14.4.2 Test Specifications and Procedures . . . .. .. .. 14.4-1 14.4.3 Conduct of Test Program . . . . . . .. 14.4-1 14.4.4 Review and Evaluation of Test Results .. . ... . . .. 14.4-1 Revision: 10 3 WB5tingfl00Se xx December 20,1996 l
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| Section Title Page CHAPTER 15 ACCIDENT ANALYSES ... ........ . . ..... ....... . . 15.0-1 15.0.1 Classification of Plant Conditions . . . . . . . . . ..... .. .... . ... . 15.0-1 15.0.2 Optimization of Control Systems . ....... . ... .......... . . . . . 15.0-5 15.0.3 Plant Characteristics and Initial Conditions Assumed in the Accident Analyses . . . . .. .. .... . ......... . . 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysis . . ....... . . . 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics .... . ..... 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses ... . . 15.0-8 15.0.7 Instmmentation Drift and Calorimetric Errors. Power Range Neutron Flux . . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . . . .... . .. ...... . . . . . . . . 15.0-10 15.0.10 Residual Decay Heat . . ...... ......... ............ . 15.0-10 15.0.11 Computer Codes Utilized . ...... .... .. . .... . . . . . . 15.0-11 15.0.12 Component Failures . . . . . . . ......... .. . ...... ..... . 15.0-13 15.0.13 Operator Actions . . . . . . ...... . ... .... .. .... .... ... 15.0-14 15.0.14 Combined License Information . . ......... .. ........ ... 15.0-14 15.0.15 References . . . . . . . .... .. . .............. .. ... . ... 15.0-14 15.1 Increase in Heat Removal from the Primary System . .... ... ..... . 15.1-1 15.1.1 Feedwater System Malfunctions that Result in a Decrease in Feedwater Temperature ...... ... . ............ .. . . 15.1-1 1 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow ... . ........ .. .... ... . .... . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow . .............. 15.1-5 15.1.4 Inadvertent Opening of a Steam Generator Relief or Safety Valve . 15.1-8 i 15.1.5 Steam System Piping Failure ... ........ ............. 15.1-11 15.1.6 Inadvertent Operation of the Passive Residual Heat Removal Heat Exchanger . . ... ....... ....... ... .... . 15.1-20 l 15.1.7 Combined License Information . . . . . .. . ... ... . .. 15.1-24 ;
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| 15.1.8 References . . . . . . .. ... . ...... . . 15.1-24 1 15.2 Decrease in Heat Removal by the Secondary System . . .... .. .. . 15.2-1 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . .. . . ... ..... . . 15.2-1 15.2.2 Loss of Extemal Electrical Load . . ... ... 15.2-1 15.2.3 Turbine Trip . . . . . . ... . .. ... .. . . . 15.2-3 15.2.4 Inadvertent Closure of Main Steam Isolation Valves . . . . . . . . 15.2-7 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries .... ... . .... 15.2-8 l 15.2.7 Loss of Normal Feedwater Flow . . . . .. .. .. ... 15.2-12 15.2.8 Feedwater System Pipe Break . .. .. ..... .. . 15.2-16 15.2.9 Combined License Information . . . .. . 15.2-21 O
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| 15.2.10 References . . . . .. . ... .. . .. . . . .. .. 15.2-21 l 15.3 Decrease in Reactor Coolant System Flow Rate . . .... .. ........... 15.3-1 l 15.3.1 Partial Loss of Forced Reactor Coolant Flow . . . ... ... . . . 15.3-1 l 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . .. . . 15.3-3 )
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| 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . . . . 15.3-5 l
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| 15.3.4 Reactor Coolant Pump Shaft Break . . . . .. ............ .. 15.3-10 t 15.3.5 Combined License Information . . . . . . . . . . . . . . . . . . ..... 15.3-10 15.3.6 References ....... ... ... . ......... ........ 15.3-11 15.4 Reactivity and Power Distribution Anomalies ........ ... .. . . . . 15.4 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Suberitical or Low-Power Stanup Condition .. .. .... . . 15.4-1 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power . . . . ........ . ..... ... . ... 15.4-5 15.4.3 Rod Cluster Control Assembly Misalignment (System Malfunction or Operator Error) .. . ......... ...... 15.4-11 15.4.4 Startup of an Inactive Reactor Coolant Pump at an Incorrect Temperature . . . . . . . . . . . . . . . . . .. ...... .. ..... . 15.4-17 i 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling ;
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| ,o Water Reactor Loop that Results in an Increased Reactor
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| () Coolant Flow Rate . . . . . . . . . .. .... ........... 15.4-19 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant . . . .. ... . . . ... .. . .. .. 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position . . . . . .. .... ......... . ... ..... 15.4-25 15.4.8 Spectmm of Rod Cluster Control Assembly Ejecti3n Accidents . . . 15.4-28 15.4.9 Combined License Information . ...... ... ..... .. . . 15.4-39 15.4.10 References . . . . . . . .... . .. .. .......... .... . 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory . . . . .. .. . . .. 15.5-1 15.5.1 Inadvenent Operation of the Core Makeup Tanks (CMT) During Power Operation . . ... .... . . . . . . . 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory . ..... .. . . 15.5-4 15.5.3 Boiling Water Reactor Transients . . ... .... .. . .. 15.5-8 15.5.4 Combined License Information . . ... . . . . 15.5-8 15.5.5 References ........... ... .. . .. .. ... 15.5-8 15.6 Decrease in Reactor Coolant Inventory . . . . . .... .... . . 15.6-1 15.6.1 Inadvertent Opening of a Pressurizer Safety Valve or Inadvertent Operation of the ADS .. . . .. . . .. 15.6-1 (O
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| v)
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| Master Table of Contents m-MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Eage, 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . .................. ... . . . . . . . 15.6-4 15.6.3 Steam Generator Tube Rupture .... . .. ... .... .. . . 15.6-5 15.6.4 Spectmm of BWR Steam System Piping Failures Outside of Containment . . . . . . .... . . . .. . 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . . . .... . . .. . . . . .... ... 15.6-15 15.6.6 References . . .... . ........ ....... . .. . ... 15.6-64 15.7 Radioactive Release From a Subsystem or Component .. .. . ... .... 15.7-1 ;
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| 15.7.1 Gas Waste Management System Leak or Failure . . .... . . 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ............. .. ...... .. . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure . ........... .. .. .. .. ..... . . . 15.7-1 15.7.4 Fuel Handling Accident . ... .. . .. . . . . . . . . . . 15.7- 1 15.7.5 Spent Fuel Cask Drop Accident . .. . . .............. . 15.7-6 15.7.6 Combined License Information . . . .. .. .... ........... 15.7-6 15.7.7 fleferences . .. . . . . . ..... ..... . . . . . . . . 15.7-7 15.8 Anticipt.ed Transients without Scram . . ... . .. ........... 15.8-1 15.8.1 General Background . .. .. .... ... ......... ..... 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . . . . ...... . 15.8-1 15.8.3 Conclusion . . . ............ ... . .. . ... . . . . 15.8-1 15.8.4 Combined License Information . . .. ................. . . 15.8-1 15.8.5 References . . . . . . . . . .... ...... .... . ............. 15.8-1 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS . ... . . 15A-1 1 SA.1 Offsite Dose Calculation Models . . . . . . . ... . ... . 15A-1 15A.1.1 Immersion Dose Models .... . .. .. . 15A-1 15A.I.2 Inhalation Dose (Committed Effective Dose Equivalent) . . ... 15A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) . . . 15A-2 15A.2 Main Control Room Dose Models . . . . ...... .... . 15A-2 15A.2.1 Immersion Dose Models .. . .... ... .... . 15A-2 15A.2.2 Inhalation Dose . .. . .. . ... .. . . . . 15 A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) . . . ... 15A-4 15A.3 General Analysis Parameters . . . .. . . ..... . 15A-4 15A.3.1 Source Terms . . .. ... ... ....... ... . 15A-4 15A.3.2 Nuclide Parameters . ..... . . . ..... .. . 15A-6 15A.3.3 Atmospheric Dispersion Factors . . . . ... . . 15A-6 15A.4 References ..... ... ........ .... . . .. . 15A-6 O
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| Revision: 10 ,
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| December 20,1996 xxiv [ WeStiligh0USS )
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| =>
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| Master Table of Contents g)
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| (_ MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Ea, ge.
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| Volume 10 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS ........... ........... . 16.1-1 16.1.1 Introduction to Technical Specifications . . ....... . . . . 16.1-1 1.0 Use and Application ... ....... ..... . . . 1.1-1 1.1 Definitions . . . . . . .. . . ... .. ... . . 1.1-1 1.2 Logical Connectors . . . . . . . . . . .. .... .. 1.2-1 1.3 Completion Times .. .. . ... . . . . .. 1.3-1 1.4 Frequency ....... ...... . . . .... ... . 1.4-1 2.0 Safety Limits (SLs) . ... . . .. . ..... ... 2.0-1 2.1 SLs .. ........ .. . . ...... .... ....... 2.0-1 2.2 SL Violations . . . . . . .... ...... . ... . 2.0-1 3.0 Limiting Conditions for Operation (LCO) Applicability ...... 3.0-1 3.0 Surveillance Requirement (SR) Applicability . ......... 3.0-4 3.1 Reactivity Control Systems ... . ..... .... ... . ... 3.1-1 3.1.1 Shutdown Margin (SDM) . . . ... ... .......... 3.1-1 3.1.2 Core Reactivity . . ..... . . .. . . .... . . . . 3.1 -2 rm 3.1.3 Moderator Temperature Coefficient (MTC) ..... 3.1-4 C
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| 3.1.4 Rod Group Alignment Limits ........ ...... .... 3.1-6 3.1.5 Shutdown Bank Insertion Limits . . . . .. ... ... . . 3.1-11 3.1.6 Control Bank Insertion Limits .. . . . . . . . . . . . . . . . . 3.1 - 13 3.1.7 Rod Position Indication ....................... 3.1-16 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . . . . . . . .. . 3.1-18 3.1.9 Chemical and Volume Control Syste n (CVS) Demineralized Water Isolation Valves . . . . . . . . . 3.1-20 3.2 Power Distribution Limits . . .. .. .... ..... ... 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fn (Z))
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| (FoMethodology) . .. .. ....... .... . 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) .. ..... .... . . . 3.2-5 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . ... . . 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QFTR) . . . . . .. . .. . 3.2-10 3.2.5 OPDMS-Monitored Power Distnbution Parameters . . . . . . . . . .. . .. .. . 3.2-14 3.3 Instrumentation . . . . . . .. . ...... .. ..... . 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation . .. .. 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation . . ... . . 3.3-17 3.3.3 Post Accident Monitoring (PAM) Instrumentation .. 3.3-45 im 3.3.4 Remote Shutdown Workstation . . . . .. ... . . 3.3-48 I h QJ Revision: 10
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| [ WeStingh0US8 xxy December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.4 Reactor Coolant System (RCS) . . . . . ...... .. . .. . . 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . . . . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . ...... . . 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . . .. . . 3.4-4 3.4.4 RCS Loops - Modes l and 2 . . . . .. . ... .. 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . . .. . . . . . 3.4-7 3.4.6 Pressurizer . . . ... ..... .. .... . ... . . . 3.4-9 3.4.7 Pressurizer Safety Valves 3.4-10 3.4.8 RCS Operational Leakage
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| )
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| . . . .. . . . . . . 3.4-12 !
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| 3.4.9 Minimum RCS Flow . . ..... .. . ... . . . 3.4-14 l 3.4.10 RCS Leakage Detection Instmmentation 3.4-15 l
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| 3.4.11 RCS Specific Activity . . .. .. .......... . . . . 3.4-18 !
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| 3.4.12 Automatic Depressurization System (ADS)- Operating . 3.4-20 3.4.13 Automatic Depressurization System (ADS)- Shutdown, RCS Intact ...... . . . . . . . . . . . . . . . . . . . . . . . . 3.4-2 2 3.4.14 Automatic Depressurization System (ADS)- Shutdown, RCS Open . . . .. ... ...... . .. . 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . ........ .. . . . . . . . . . . . 3.4-26 3.5 Passive Core Cooling System (PXS) . .... ..... . ... 3.5-1 3.5.1 Accumulators . . ........ .... .. .. . .. 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating ... .. . . . . . .. 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . . 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating ... . ... ......... 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . ... ..... . . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST) -
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| Operating . . . . . . . . . . . . . . . . ... . . ..... 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory High . . . . ...... 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low . . ... . . 3.5-18 3.6 Containment Systems . . . ..... . . . 3.6-1 3.6.1 Containment . . . . . ... .. ... . .. . . . 3.6-1 3.6.2 Containment Air Locks . ... . . . ..... . . 3.6-3 3.6.3 Containment Isolation Valves . ... .... . . . . 3.6-7 3.6.4 Containment Pressure . . . . . . . 3.6-12 3.6.5 Containment Air Temperature . . . . . . . . . . 3.6-13 O
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| Revision: 10 December 20,1996 xxvi W85tiligt10US8 l 1
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| Master Table of Contents i
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| t t V MASTER TABLE OF CONTENTS (Cont.)
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| Section Tith ,P_ age 3.6.6 Passive Containment Cooling System (PCS) - Operation . 3.6-14 3.6.7 Passive Containment Cooling System (PCS) - Shutdown 3.6-17 3.6.8 Containment Penetrations . . . . . . . . . . 3.6-19 3.6.9 pH Adjustment . . . . . . . .. .... .. ... . . 3.6-22 3.7 Plant Systems . . . . . . . . . . . .. ... .... .. . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . ..... ... 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves (MFIV and MFCV) .... ....... ..... . . 3.7-7 3.7.4 Secondary Specific Activity . . . . . ....... .... . 3.7-9 3.7.5 Spent Fuel Pool Water Level . . . . . . .......... . 3.7-10 3.7.6 Main Control Room Habitability System (VES) . . . 3.7-11 3.7.7 Startup Feedwater Isolation and Control Valves . . . . . . 3.7-15 3.8 Electrical Power Systems . . . . .. . .. . 3.8-1 3.8.1 DC Sources - Operating . . .. .. . . ... .. .. 3.8-1 3.8.2 DC Sources - Shutdown . . .... . .. .. .. ... 3.8-5 3.8.3 Inverters - Operating . . . . .. . ... ... . 3.8-7 3.8.4 Inveners - Shutdown . . . . .. . . ..... ...... 3.8-9 3.8.5 Distribution Systems - Operating . 3.8-11 (b'
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| 3.8.6 Distribution Systems - Shutdown .......... ..... 3.8 13 3.8.7 Battery Cell Parameters . . . . . . . . . . . . . . . . . . . . 3.8- 15 3.9 Refueling Operations . . . . . . ....... .. ... .. ... . 3.9-1 3.9.1 Boron Concentration . . . . ... .. ..... .. 3.9-1 3.9.2 Unborated Water Source Flow Paths . . .... ... 3.9-2 3.9.3 Nuclear Instrumentation . ... . . .. . ...... . 3.9-4 3.9.4 Refueling Cavity Water Level . . . . ......... .. 3.9-6 4.0 Design Features ........ ... .. . . .... . 4.0-1 4.1 Site . . . . ... ..... . . .... . ... 4.0-1 4.1.1 Site and Exclusion Boundaries .... .. . 4.0-1 4.1.2 Low Population Zone (LPZ) . . . . 4.0-1 4.2 Reactor Core ..... . . . . ... . . . 4.0-1 4.2.1 Fuel Assen:blies . . .. . .. . 4.0-1 4.2.2 Control Rod and Gray Rod Assemblies . . 4.0-1 4.3 Fuel Storage . . . . . . . . . .. . .. 4.0-2 4.3.1 Criticality . . . . . . ... ... . . 4.0-2 4.3.2 Drainage .... . . . 4.0-2 4.3.3 Capacity .... . . . ... . . 4.0-2 4.4 Hydrogen Control ... .... . .... . 40-3 4.4.1 Passive Autocatalytic Recombiners (PARS) . .. . 4.0-3 5.0 Administrative Controls . . . ... .. . . . .. . 5.0-1 5.1 Responsibility . .. .. . . ... . . 5.0-1 5.2 Organization . . 5.0-2 t
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| v Revision: 10 W8Stingh0USB xxvii December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pye 5.3 Unit Staff Qualifications ...... . . .... . .. 5.0-5 5.4 Procedures . . . . . ...... . .. .... . .. 5.0-6 l 5.5 Programs and Manuals . . . . . . . . ... .... .. .. 5.0-7 5.6 Reponing Requirements . ..... . . .. ... . 5.0-15 l B 2.0 Safety Limits (SLs) . .. .... .. .. . ... . . . B 2.0-1 !
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| B 2.1.1 Reactor Core Safety Limits (SLs) ...... . B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability ... . . . . B 3.0-1 ;
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| B 3.0 Surveillance Requirement (SR) Applicability . . . ...... . . . B 3.0-12 !
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| B 3.1 Reactivity Control Systems . .. .. . ..... B 3.1-1 B 3.1.1 Shutdown Margin (SDM) . . .. .. . . . B 3.1-1 B 3.1.2 Core Reactivity . . . . . . . . . . . . . . . . . . .. . B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . . . . . . . . . . . B 3.1-19 B 3.1.5 Shutdown Bank Insertion Limits . . .... . B 3.1-29 B 3.1.6 Control Bank Insenion Limits . .. B 3.1-34 B 3.1.7 Rod Position Indication . . . . . . . . . . . B 3.1-40 I B 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . . . . B 3.146 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves . . . . . B 3.1-53 B 3.2 Power Distribution Limits . . . . . . . . . . . . B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (Fq (Z))
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| (FoMethodology) . . ... ..... . . . . . B 3.2-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) ........ . .......... . .. B 3.2-10 B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QPTR) .. . B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters . ... .... . .... . . . . B 3.2-28 B 3.3 Instrumentation . ... .. . .. ..... B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instmmentation . . B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation . . . . B 3.3-53 B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation . .... . . . . B 3.3-115 B 3.3.4 Remote Shutdown Workstation ... . . B 3.3-125 B 3.4 Reactor Coolant System (RCS) . . . . . ... B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . B 3.4-1 O
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| Revision: 10 December 20,1996 xxviii 3 Westingh00S6
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| l.
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| Master Table of Contents un -
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| ,,-m i i kJ MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page B 3.4.2 RCS Minimum Temperature for Criticality . . B 3.4-6 ;
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| B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . B 3.4-9
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| {
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| B 3.4.4 RCS Loops - Modes 1 and 2 . . . . . . ... . B 3.4-17 B 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . . . . . . B 3.4-21 B 3.4.6 Pressurizer . . . . . . ..... . .. . . . . . B 3.4-25 l B 3.4.7 Pressurizer Safety Valves . . . . . ...,.. .. B 3.4-28 i B 3.4.8 RCS Operational Leakage .......... .. B 3.4-32 B 3.4.9 Minimum RCS Flow l
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| ... . ....... B 3.4-38 B 3.4.10 RCS Leakage Detection Instrumentation .. B 3.4-41 l B 3.4.11 RCS Specific Activity ... ....... . B 3.4-46 ,
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| B 3.4.12 Automatic Depressurization System (ADS) -
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| Operating ....... .. . . ..... . B 3.4-50 B 3.4.13 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Intact . . . . . . . . ... . . . B 3.4-54 B 3.4.14 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Open . . . . . . .. . . . . . B 3.4-57 i B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . ... ............. B 3.4-60 ,
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| (3 B 3.5 Passive Core Cooling System (PXS) . . . .... .. B 3.5-1 l
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| ( ,/ B 3.5.1 Accumulators . . . . . . . . . . . . . . . B 3.5- 1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . . . . B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, !
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| RCS Intact . . . . . . . . . .. . . . . . . . . B 3.5-15 l B 3.5.4 Passive Residual Heat Removal Heat l Exchanger (PRHR HX) - Operating .. ... B 3.5-18 B 3.5.5 Passive Residual Heat Removal Heat Exchanger ,
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| (PRHR HX) - Shutdown, RCS Intact . . . . . B 3.5-24 B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating . . .. . B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST)- Shutdown, RCS Inventory High . . B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low ...... ..... .. ..... B 3.5-38 B 3.6 Containment Systems . . . .. . ... .. . B 3.61 B 3.6.1 Containment . . . .. ....... .. . B 3.6-1 B 3.6.2 Containment Air Locks ...... . . .. . B 3.6-6 B 3.6 3 Containment Isolation Valves . . . ..... . B 3.6-13 B 3.6.4 Containment Pressure . . . .. B 3.6-23 B 3.6.5 Containment Air Temperature . . . .... B 3.6-26 B 3.6.6 Passive Containment Cooling System (PCS)- Operating . . . . . B 3.6-30
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| < t Q) -
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| Revision: 10
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| [ W85tkigh00Se xxix December 20,1996
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| Master Table of Contents l
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| l MASTER TABLE OF CONTENTS (Cont.)
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| 1 1
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| Section Title h B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . .... .. . . . . . . B 3.6-37 B 3.6.8 Containment Penetrations .... .. . . B 3.6-40 B 3.6.9 pH Adjustment ..... ..... .. B 3.6-47 B 3.7 Plant Systems . . . .... .. ........ . . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) .... ......... . B 3.7-13 B 3.7.4 Secondary Specific Activity . . . . .. . B 3.7-18 B 3.7.5 Spent Fuel Pool Water Level . . . .. . . B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability System . . . . . ........ .. . B 3.7-24 B 3.7.7 Startup Feedwater Isolation and Control Valves B 3.7-30 B 3.8 Electrical Power Systems ....... . . ... B 3.8-1 B 3.8.1 DC Sources - Operating . . . . . ... . B 3.8-1 B 3.8.2 DC Sources - Shutdown . . .... ....... B 3.8-11 B 3.8.3 Inverters - Operating . . . ....... .. . B 3.8-15 B 3.8.4 Inverters - Shutdown . . ..... ... B 3.8-20 B 3.8.5 Distribution Systems - Operating . . B 3.8-24 B 3.8.6 Distribution Systems - Shutdown . . .. . . B 3.8.33 B 3.8.7 Battery Cell Parameters .. . . . . . B 3.8-37 B 3.9 Refueling Operations . . . . . ... .... B 3.9-1 B 3.9.1 Boron Concentration . . . B 3.9-1 B 3.9.2 Unborated Water Source Flow Paths . . . . . B 3.9-5 B 3.9.3 Nuclear Instmmentation ..... . .. B 3.9-8 B 3.9.4 Refueling Cavity Water Level .. ... B 3.9-11 Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM .. . 16.2-1 16.2.1 Introduction ........ . ... . . 16.2-1 16.2.2 Scope .. .. .. . . . . . . . . .. 16.2-1 16.2.3 Design Considerations . . . .. .. .... . . .. 16.2-1 16.2.4 Relationship to Other Administrative Programs . . . . 16.2-2 16.2.5 The AP600 Design Organization .. .... ...... . . . 16.2-2 16.2.6 Objective . . . . ......... . . .... .... . 16.2-3 16.2.7 D-RAP, Phase I . . . .. .. . . . . ... . 16.2-4 16.2.8 Combined License Activities - O-RAP . . . . . 16.2-9 16.2.9 Glossary of Terms .. .... . .. . . . 16.2-10 0
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| Revision: 10 December 20,1996 xxx 3 WBSlitigh0USB
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| Master Table of Contents 7
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| ' I V MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h 16.2.10 References . . . ... . .. .. ... . ..... 16.2-11 CHAPTER 17 QUALITY ASSURANCE . . . . . . . ......... . ....... .... 17.1-1 17.1 Quality Assurance During the Design and Construction Phases . . . . . ..... 17.1-1 17.2 Quality Assurance During the Operations Phase . . . . . . . ....... . . . . 17.1-1 17.3 Quality Assurance During Design, Procurement, Fabrication. Inspection and/or Testing of Nuclear Power Plant Items and Services . ..... ... . 17.1-1 17.4 Combined License Information Items .. . ..... .......... ... 17.1-2 17.5 References . .. ... ...... . .. ............. ..... ... 17.1-2 CHAPTER 18 HUMAN FACTORS ENGINEERING . . .... ..... . ..... . . . . . 18.1-1 18.1 Overview . .... ...... ....... ... ... . ........ ... 18.1-1 18.1.1 References . . . . . . . . . . .. ... . . . ......... . . . . 18.1-4 18.2 Human Factors Engineering Program Management .... ..... . .. ... I8.2-1 18.2.1 Human Factors Engineering Program Goals, Scope, Assumptions, and Constraints . . . . . ..... . .. ... . .. 18.2-1 18.2.2 Human System Interfaces Design Team and Organization . . 18.2-4 18.2.3 Human Factors Engineering Processes and Procedures ... .. 18.2-11 p 18.2.4 Human Factors Engineering Issues Tracking ... . .. ..... . 180 57 (j 18.2.5 Human Factors Engineering Technical Progtams and Milestones . . . . . .. . . ..... . . ... . ..... 18.2.18 18.2.6 Combined License Information . .. ... . . ......... 18.2-19 18.2.7 References ....... . . . .... .. ... .... .. 18.2-19 18.3 Operating Experience Review . . . . . . .. .... . .... . . I8.3-1 18.3.1 Combined License Information . . . . .. .... . ... . 18.3-1 18.3.2 References . . . . . . . . . . . ...... . .. .. ..... ... 18.3-1 18.4 Functional Requirements Analysis and Allocation . . . .. . .... ... 18.4-1 18.4.1 Combined License Information . . . . . ... ..... .. ... .. .. 18.4-2 18.4.2 References . ....... . . .. ... . . . ... .. .. 18.4-2 18.5 AP600 Task Analysis Implementation Plan . .... .. ... . .. 18.5-1 18.5.1 Task Analysis Scope . . .. . . . .. . .. .. . 18.5-1 18.5.2 Task Analysis Implementation Plan ....... . . .. . . 18.5-2 18.5.3 Job Design Factors .. ... . ... . ..... .. . 18.5-5 18.5.4 Combined License Information Item .. . . .... . .. 18.5-5 18.5.5 References . ... .. .. . . .... . . .. . 18.5-5 18.6 Staffing . . . .. . ....... ... . ... .. . . 18.6-1 18.6.1 Combined License Information item . . ... . . 18.6-1 18.6.2 References .... .. . . . ... .... .. . . .. .. 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering 18.7-1 18.7.1 Combined License Information . . . ....... ... 18.7-1 18.7.2 References ... ..... . . .. ... . .. . . 18.7-1 18.8 Human System Interface Design . . . .. 18.8-1
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| Section Title g 18.8.1 Implementation Plan for the Human System Interface Design . 18.8-3 18.8.2 Safety Parameter Display System (SPDS) . .. ... . .. 18.8-11 18.8.3 Operation and Control Centers ...... .... ... ...... . 18.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Portion of the Plant . . . . . . . . . . . .. ..... ... . 18.8-20 18.8.5 Combined License lnformation . . . .. ... .. . . . 18.8-23 18.8.6 References . . ..... .. .. .. . ........ .. . . . . 18.8-23 18.9 Procedure Development ..... ... ...... ..... . .. . 18.9-1 18.9.1 Combined License Information . .... . . ............ . 18.9-1 18.9.2 Referencer . . .. ... . .... . . ... . . . . . . . 18.9-1 18.10 Training Program Development . .... . . . .. .. . ... . 18.10-1 18.10.1 Combined License Information . .. . .. . .. . .. I8.10-1 18.10.2 References . . . . .... ..... . . . . . .... 18.10-1 18.11 Human System Interface Design Test Program . . . . . .. .. 18.11-1 18.11.1 Combined License Information . . .. .......... . . I8.11-2 18.11.2 References . ... . ... . . . . . . .. . 18.11-2 18.12 Displays, Alarms, and Controls . . . .. .. ...... ...... . 18.12-1 18.12.1 Inventory of Displays, Alarms, and Controls . .... ...... I8.12-1 18.12.2 Minimum Inventory of Main Control Room Fixed Displays, Alarms, and Controls . .... .. ... ........... .. 18.12-1 18.12.3 Remote Shutdown Workstation Displays, Alarms, and Controls . . 18.12-7 18.12.4 Combined License Information . . .. .. .. ..... . I8.12-7 18.12.5 References . . . . ..,. . . . . . . . .. 18.12-8 l
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| v MASTER TABLE OF CONTENTS Section Title Page Volume 1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRII* TION OF PLANT .... . . 1.1-1 l 1.1 Introduction . . . . ..... .... . . .. .. .. . . .. ... 1.1-1 i 1.1.1 Plant Location . . .... . . .. ........ .. . .. . . . 1.1-1 l 1.1.2 Containraent Type ...... ... .......... ........ . 1.1-1 1.1.3 Reactor Type .............. ...... .. . .. .... . . . . 1.1 -1 1.1.4 Power Output . . .. . . ....... . . .... ...... 1.1-1 1.1.5 Schedule ... .......... .. ..... . ....... ..... 1.1-1 i
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| 1.1.6 Format and Content ......................... . . . . . .. 1.1-2 4 1.1.7 Combined License Information . . .. .... ... . . . .. 1.1-3 1.2 General Plant Description . . . . . . . . ..... . . .................... 1.2-1 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 ,
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| 1.2.2 Site Description . .... .... ...... .. . . . . . . . . . . 1.2- 15 !
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| 1.2.3 Plant Arrangement Description . ........ ........ . . . . . . 1.2- 16 l 1.2.4 Nuclear lsland . . . . . . . . ... .. .. ..... .. 1.2-17 ;
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| 1.2.5 Annex Building . . ..... .. .. .. .. .......... 1.2-24 1.2.6 Diesel Generator Building . . . . . . .. .. ........... ..... 1.2-25
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| ( ) 1.2.7 Radwaste Building .. ....... ..... . ........ . . . 1.2-26
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| '' l.2.8 Turbine Building ..... . . . .... ....... . .... .. 1.2-26 j 1.2.9 Combined License Inforn:Mion . . . . . . . .... .... . ... . 1.2-27 ;
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| 1.3 Comparisons with Similar Facility Designs . . . . . . . ...... .... . . 1.3-1 1.4 Identification of Agents and Contractors ... ..... ........... ..... 1.4-1 1.4.1 Applicant - Program Manager . .. .. . . . .. ..... . . 1.4-1 1.4.2 Other Contractors and Participants ..... .... ... .. ... . . 1.4-1 1.4.3 Combined License Information . . .... . . . .. . . 1.4-3 1.5 Requirements for Further Technical Information ..... . ..... . . . 1.5-1 1.5.1 AP600 Safety-Related Tests . .. . ... . ...... . 1.5-1 1.5.2 AP600 Component Design Tests .. . . .... ..... .. . 1.5-7 1.5.3 Combined License Information . .... . . . ....... . . 1.5-8 1.5.4 References . . . . . . . . . . . ............... . . ... .. 1.5-8 1.6 Material Referenced ....... ...... ............ . ... ... . 1.6-1 1.7 Drawings and Other Detailed Information .. . . . ... . .. . 1.7-1 1.7.1 Electrical and Instrumentation and Control Drawings . . ... . .. 1.7-1 1.7.2 Piping and Instrumentation Diagrams . . . . . . . . .... 1.7-1 1.7.3 Combined License Information . . . .... ... .... . . . 1.7-1 1.8 Interfaces for Standard Design . . . . . . . . . . . . ..... . .. .. . 1.8-1 1.9 Compliance with Regulatory Criteria . . . . ..... . ... 1.9-1 1.9.1 Regulatory Guides .... ... .. . ........ .. .. . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) . .. . . 1.9-3 1.9.3 Three Mile Island Issues . . . ........ .. ....... ... 1.9-3 m
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| Section Title Eage a
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| 1.9.4 Unresolved Safety Issues and Generic Safety Issues . . . . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues ... . . . 1.9-74 1.9.6 Combined License Information .. .. . .... . .. 1.9-107 1.9.7 References . .. .. ....... . . . ..... . .. 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES .. . ..... . l A-1 1 A.1 References .......... . ....... . ... ... . . 1 A-79 APPENDIX 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES , . . 1B-1 1 B.1 Introduction ....... .. . . .. . . ... .. . . . . IB-1 1 B.2 Summary . ..... . .... ..... .... .......... ... IB-1 IB.3 Selection of SAMDAS . .. ....... .. . ... .. . 1B-2 I B.4 Methodology . . ... .. .. . . . .... .. .. ... IB-2 IB.4.1 Risk Reduction ...... .. . ... ... . . IB-2 1B.4.2 Capital Cost Estimates ... . . .. .. . .. 1B-3 1B.4.3 Cost Benefit Analysis . .. .. . .. ..... . 1B-3 1 B.5 PRA Release Categories ........ . .. .. . . . . . 1 B-3 1B.5.1 Release Category OK . .. . ...... . .. . . . . 1B-4 1B.5.2 Release Category OKP . . . . .. . . .. ... . 1B-4 IB.5.3 Release Category CC . ... . .. . . . . . . . . . . . I B-5 IB.5.4 Release Category CI . .. . . .... . . IB-5 1 B.6 Total Population Dose . . ... . . .... . . . 1B-5 1 B.7 SAMDA Description and Benefit . . . . . . . .... . . . 1B-6 IB.7.1 Upgrade the CVCS for Small LOCAs . .. .. . . IB-6 IB.7.2 Filtered Vent . ..... ..... . .. . ....... . ... IB-6 IB.7.3 Locate Normal RHR Inside Containment .... . . IB-7 IB.7.4 Self-Actuating Containment Isolation Valves . . . .. .. . . IB-7 iB.7.5 Passive Containment Sprays . . ...... . . . 1B-7 1B.7.6 Active High Pressure Safety Injection System ... ..... ... 1B-7 IB.7.7 Steam Generator Shell-Side Heat Removal System .. 1B-8 1B.7.8 Direct Steam Generator Relief Flow to the IRWST , . . . . . . IB-8 1B.7.9 Increased Steam Generator Pressure Capability . . . . . . . 1B-8 IB.7.10 Secondary Containment Filtered Ventilation . .. IB-8 1 B.7.11 Diversify the IRWST Discharge Valves . .. . . . 1B-9 1B.7.12 Ex-Vessel Core Catcher .... . .. .... . 1B-9 IB.7.13 High Pressure Containment Design . . .. . .. . . IB-9 1 B.7.14 Increase Reliability of Diverse Actuation System . . . .. .. . IB-9 IB.8 Results .... . ... ... . . . .. . .. . ... IB-9 I B.9 References . . .. . . .. . . . . . . . 1B-11 O
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| Revision: 10 December 20,1996 i 3 Westingh00Se
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| Section Title ,Page CHAPTER 2 SITE CHARACTERISTICS .. ... .. .. . . ... . .. . ... 2-1 2.1 GeograpFy and Demography . . .. . ........ . ........... . 2-1 l 2.1.1 Combined License Information for Geogra,ohy and Demography . . . 2-1 l 2.2 Nearby Industrial, Transportation, and Military Facilities . .... . . .. . 2-1 !
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| 2.2.1 Combined License Information for Identification of Site-specific ,
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| Potential Hazards . . . . .. .. .. . .. . ... 2-2 l 2.3 Meteorology .. .... ....... . .. .. . . . .... .. 2-2 2.3.1 Regional Climatology ... ...... . . ..... . . . . 2-3 l 2.3.2 Local Meteorology . . . . . 2-3
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| 2.3.3 Onsite Meteorological Measurement Programs ... .. ... 2-3 2.3.4 Short-Term Diffusion Estimates . . . . . .. . .. ... . ... 2-3 2.3.5 Long-Term Diffusion Estimates ..... .. . .... .... 2-4 2.3.6 Combined Licensed Information . . ... .. ... ... .. 2-4 2.4 Hydrologic Engineering . . . . ... . . . ... . .. .... ... . 2-5 2.4.1 Combined License Information . ..... . . . ...... 2-5 2.5 Geology, Seismology, and Geotechnical Engineering . . . . . .. ... .... 2-6 2.5.1 Basic Geological and Seismic Combined License Information .... 2-6 2.5.2 Vibratory Ground Motion . . .......... ....... ... . 2-7 2.5.3 Surface Faulting Combined License Information . ... ...... 2-7 (V'T 2.5.4 Stability of Subsurface Materials and Foundations ............ 2-8 2.5.5 Combined License Information for St:bility of Slopes . ..... . 2-12 2.5.6 Combined License Information for Embankments and Dams . . .. 2-13 2.5.7 References . . . ........ . .. ... ........ 2-13 APPENDIX 2A DESIGN SOIL PROFILES . . . . . . . . . ...... ..... . .. .. 2A-1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. . . . 2A-1 2A.2 Generic Soil Profiles . ...... ........ ... .... .. .. .. 2A-2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . . ... 2A-4 2A.4 Free-Field Site Response Analysis .. . ....... .. ..... . . . 2A-5 2A.5 2D Soil-Structure Interaction Analysis ... .... . . . . . . . . 2A-7 2A.6 AP600 Design Soil Profiles . . . . . .. . .. . . . . . . 2A-12 2A.7 References . . . . .. .. . . . .. . .. .. .. 2A-14 APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL PROFILES . . ... ...... . .. . ....... . . . . 2B-1 2B.1 2D SSI Analysis Parameters and Procedures .. . . . .. .. 2B-2 2B. l .1 Structural Models . . . . ... ... ... ... .. . . . 2B-2 28.1.2 SASSI Foundation Models .. .... . . . . . . 2B-2 2B.I .3 Soil Properties for SSI Analysis . . . . . . . . 2B-2 28.1.4 Input Motion . . . . .. .......... .. .. . .. 2B-3 28.1.5 Two-Dimensional Enveloped SSI Results . .... . . . 2B-3 g 2B.2 Design Soil Profiles . .. . . . ... .. 2B-3 P
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| Section Title Eage a
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| 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . . . .. ... . 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) .. .. .. . ... .. . 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . 2B-5 2B.2.4 Variation of Soil Propenies and 60 Percent Requirement of Free-Field Spectra at Foundation Level .. .. . ...... . . 2B-5 2B.2.5 AP600 Design Soil Profiles . . . . . . .. . ... . . . . . . 2B-6 2B.3 Soil Profile Parametric Studies: . ... .. ... .. ... . .... . 2B-6 2B.3.1 Depth-to-Base Rock . . . . . . . . . ... .... ..... . . . 2B-7 2B.3.2 Soil Curves for Clay Material ..... .... . ... . .. .. 2B-7 2B.3.3 Poisson's Ratio for Soil above Water Table . . .... . . ... 2B-8 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site . . . . . . .. . 2B-8 2B.3.5 Idriss 1990 Soil Curves . . .. . . .. . ..... . . 2B-9 '
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| 2B.3.5 Soil Densitys ..... .... ... . . .. .. ........ . 2B-9 2B.4 References ..... . ... ... .. ... . ... ...... 2B-9A Volume 2 APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES . ........... . .. . . 2C-1 2C.1 2D SASSI Analysis for Seismic Lateral Eanh Pressure . ...... . . . . . 2C-1 2C.I .1 Analysis Method ...... .. .. ... ........ ... 2C-1 2C.I.2 Stmetural Models .... . .. . .. . .... .. ... . . 2C-1 2C.I.3 SASSI Foundation Models ... .. . .. ... . . . . 2C-1 2C.I .4 Representation of Adjacent Stmetures .. ......... . 2C-2 2C. I .5 Input Motion . .. .. .. . . . . .... . 2C-2 2C. I .6 Soil Propenies . .. . . . . ... . ........... 2C-2 l 2C l.7 2D SASSI Analyses Results ... . .. . . .. . 2C-2 !
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| 2C.2 Effect from Torsional Motion c.f the Nuclear Island . . ...... .. . 2C-2 2C.3 Local Distribution of Lateral Eaah Pressure .. .. ..... . .. .. . 2C-3 2C.4 References . . . . . . . ..... . . ... . .. . . . . 2C-4 l
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| CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS .......... ..... .... ... . .. .. 3.1-1 3.1 Conformance With Nuclear llegulatory Commission General Design Criteria . 3.1-1 3.1.1 Overall Requirements . . . . . . . . .. . . 3.1-1 3.1.2 Protection by Multiple Fission Product Barriers ... 3.1-4 j 3.1.3 Protection and Reactivity Controi Systems . .... . . 3.1-12 3.1.4 Fluid Systems .. .. . . . . . .. .. . 3.1-18 3.1.5 Reactor Containment ... . .. ... . . 3.1-30 3.1.6 Fuel and Reactivity Control . . . . . . . . . . 3.1-34 3.1.7 Combined License Information . . . . . 3.1-37 3.1.8 References . ... .. . ...... . .. ... 3.1-37 4
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| Revision: 10 December 20,19% iv [ WB5tiligt100SB 1
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| i Section Title Eage 3.2 Classification of Structures, Components, and Systems . . . . . . . .. 3.2-1 3.2.1 Seismic Classification . . . . . . ..... ..... . 3.2-1 3.2.2 AP600 Classification System . . . . ... .. . ... . 3.2-3 3.2.3 Inspection Requirements . ... ... .. . 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic ,
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| Classification System . .. . ... ... .. 3.2-13 !
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| 3.2.5 Combined License Information 3.2-16
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| 3.2.6 References .. .. ... . ... . . .. . 3.2-17 3.3 Wind and Tornado Loadings . . . . .......... ..... 3.3-1 !
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| 3.3.1 Wind Loadings . . . . . . ......... . ......... .. . 3.3-1 l 3.3.2 Tornado Loadings . . . . ..... .. .. ..... ... .. . 3.3-2 1 3.3.3 Combined License Information .. .. . . ...... . . 3.3-4 3.3.4 References ... ... . .. . ...... .. . .. 3.3-4 3.4 Water Level (Flood) Design .. .. . ... . ........ . 3.4-1 3.4.1 Flood Protection ... ..... .. . ....... . . . . 3.4-1 3.4.2 Analytical and Test Procedures . . . ... . .... 3.4-24 3.4.3 Combined License Information .. . . . . 3.4-24 !
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| 3.4.4 References . . . .. .. . . . . ..... . . . 3.4-24 i
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| , 3.5 Missile Protection ........ .... . 3.5-1 I
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| / ,i 3.5.1 Missile Selection and Description 3.5-4 )
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| b 3.5.2 Protection from Externally Generated Missiles
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| . . 3.5-13 l 3.5.3 Barrier Design Procedures . . ..... .... . . . . 3.5-13 3.5.4 Combined License Information . ..... ...... . ... . 3.5-16 3.5.5 References . . .. .. . . . . . .......... .. .. . 3.5-16 3.6 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping . . . . . . . . .. ....... ... . . 3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment .... .. .. . . ..... . . .. . .. 3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping . . . . . . .. 3.6-12 3.6.3 Leak-before-Break Evaluation Procedures . . .. . 3.6-31 3.6.4 Combined License Information . . ....... .. . . 3.6-38 3.6.5 References . ... . . . ... . 3.6-38 3.7 Seismic Design . . .. . . .. . . . .... .. . 3.7-1 3.7.1 Seismic Input . .... . . . .,.. .. .. . . 3.7-1 3.7.2 Seismic System Analysis . . . . . . . . . 3.7-6 3.7.3 Seismic Subsystem Analysis . .. . . 3.7-20 3.7.4 Seismic Instrumentation .. . . .. .. . . 3.7-46 3.7.5 Combined License Information . . ... . . .. 3.7-48 3.7.6 References . .. .. ... .. . . 3.7-49 3.8 Design of Category I Structures . ... .. . . 3.8-1 3.8.1 Concrete Containment . . .. . . . . . 3.8-1 3.8.2 Steel Containment . .. . . .. . . 3.8-1 v
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.8.3 Concrete and Steel Internal Structures of Steel Containment ... . 3.8-16 3.8.4 Other Category I Structures .. . .. ... ... . 3.8-39 3.8.5 Foundations .. .... .. .. . . . 3.8-53 3.8.6 Combined License Information .. .... .. ... . . . .. 3.8-60 3.8.7 References . . ... .... . . . . . 3.8-60 Volume 3 3.9 Mechanical Systems and Components . . .. ... ... . ... . 3.9-1 3.9.1 Special Topics for Mechanical Components .. .. .. . . 3.9-1 3.9.2 Dynamic Testing and Analysis . ... .. ... . ... . . 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Componems, Component Suppons, and Core Support Structures .. . . . . . . . 3.9-45 3.9.4 Control Rod Drive System (CRDS) .. .. . . .. . . . 3.9-71 3.9.5 Reactor Pressure Vessel Internals .... . .. 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . . . . ... . 3.9-89 3.9.7 Integrated Head Package . . . .... .. . . .. 3.9-97 3.9.8 Combined I,icense Information . . . ... . . .. 3.9-102 3.9.9 References . . . . ...... . .......... . . . . . . 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment . . . .. . ... ... ..... .... ... . . . 3.10-1 3.10.1 Seismic and Dynamic Qualification Criteria .... ...... .. 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Instrumentation, and Mechanical Components . . .. ... . . 3.10-3 3.10.3 Method and Procedures for Qualifying Suppons of Electrical Equipment, Instrumentation, and Mechanical Components . . . 3.10-7 3.10.4 Documentation . . . . .. .. ... ... .. . 3.10-7 3.10.5 Standard Review Plan Evaluation . ... .... . 3.10-7 3.10.6 Combined License Information Item on Experienced-Based Qualification . . .. . . . . ... ... . 3.10-8 3.10.7 References . . .. ... . . . ..... . .. . 3.10-8 3.11 Environmental Qualification of Mechanical and Electrical Equipment . . . . 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . . . 3.11-1 3.11.2 Qualification Tests and Analysis . . .... .. ... . 3.11-3 3.11.3 Loss of Ventilation . ... . .. . .. ... . . 3.11-4 3.11.4 Estimated Radiation and Chemical Environment .. .. ... 3.11-5 3.11.5 Combined License Information Item for Equipment Qualification File ... . ..... . ... . . .... 3.11-5 3.11.6 References .. ... .. .. . . . 3.11-6 O
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| Revision: 10 December 20,1996 y [ Westinghouse
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| Section Title Page i APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS . . .. .. .... . 3A-1 3A.1 Codes and Standards ..... . . .. .... ... . . . . . . . . 3 A-1 1 3A.2 Loads and Load Combinations ..... .. ..... . . . . . 3 A- 1 3A.2.1 Loads ... . .. . .... . .... ... . ... . 3A-1 3A.2.2 Load Combinata,ns . . ..... . . ... .. . . . . . 3A-3 3A.3 Analysis and Design . . . .. .... . . .. ... .. . 3 A-3 3A.3.1 Response Due to Seismic Loads . . . ... ...... . . 3A-3 3A.3.2 Deflection Criteria . . . . .... . . .. . ..... . 3A-3 3A.3.3 Relative Movement . . .. . .. .... . . 3A-3 3A.3.4 Allowable Stresses .. ... . . ...... . . . 3A-4 l 3A.3.5 Connections . ... . ... . . .. .. . . . 3A-4 l 1
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| APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING .. . . 3B-1 l 3B.1 Leak-Before-Break Crits ria for AP600 Piping . .. .. .. . . . 3B-2 l 3B.2 Potential Failure Meche.1 isms for AP600 Piping . . . . . . 3B-2 l
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| 3B.2.1 Erosion-Corrosion Induced Wall Thinning ... .. ... .. . 3B-2 !
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| 3B.2.2 Stress Corr.ssion Cracking .... . . .. .. . . . 3B-3 3B.2.3 Water Hammer .. .. .. ..... . . 3B-5
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| , 3B.2.4 Fatigue .. . ... . .. . . ..... . .. . 3B-9
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| ( } 3B.2.5 Thermal Aging .... . .. . . . . . . . 3B-9 V' 3B.2.6 Thermal Stratification . . . .. . . . .. ... 3B-10 3B.2.7 Other Mechanisms . . . .. .. ....... . 3B-13 3B.3 Leak-Before-Break Bounding Analysis . . . .... . . . . 3B-13 3B.3.1 Procedure for Stainless Steel Piping . . . . .. ..... .. 3B-13 3B.3.2 Procedure for Non-Stainless Steel Piping .. .. ..... 3B-16 ,
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| 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . . 3B-17 i 3B.3.4 Bounding Analysis Results . . ... ... . 3B-21 l 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe . . . .. . . . ... .. . .. .. . . 3B-21 3B.5 Differences in Inspection Criteria for Class I,2, and 3 Systems . .. .. .. 3B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping . .. .. . . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Lines .. . 3B-21 A 3B.8 Augmented In-Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators . . . . . . . . . . . 3B-21 A 3B.9 References .. . . .. .. . .. . . . 3B.21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSS METHODS .. .. 3C-1 3C.1 Reactor Coolant Loop Model Descriptica . . . .. . . 3C-1 3C. I . ] Steam Generator Model . . . . . . . 3C-1 3C.I .2 Reactor Coolant Pump Model .. . . . 3C-2 3C.I .3 Reactor Pressure Vessel Model . . ... . 3C-2 m
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| v Revision: 10 W85dligt100S8 December 20,1996 vii
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| m Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| S, Section Title Pqe 3C.1.4 Containment Interior Building Stmeture Model ...... ..... . . 3C-3 3C.I.5 Reactor Coolant Loop Piping Model . . ....... .. ..... .. . 3C-3 3C.2 Design Requirements . . . .. . . ... .. ... ... .... . 3C-3 3C.3 Static Analyses . ....... ... .. . . . .. . . ... . . 3C-4 3C.3.1 Deadweight Analysis . . . . .. ... . . .. 3C-4 3C.3.2 Internal Pressure Analysis .. . .... ... . . .... . 3C-4 3C.3.3 Thermal Expansion Analysis . . . . .. . . . . 3C-4 3C.4 Seismic Analyses . .... . . .... ..... ... ... . . 3C-4 3C.5 Reactor Coolant Loop Piping Stresses . . . .. . ... ... ... .. . . 3C-5 3C.6 Description of Computer Programs . . . . . . ... . ... .. . .. 3C-5 APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT . . .. . . . . . 3D-1 3D.1 Purpose ...... . ..... . . ........ . . . ... .. 3D-2 3D.2 Scope. .. ... .. . . . . . . . . . . 3D-2 3D.3 Introduction .. . .. .. .. . . . . .. . .. . ... . 3D-3 3D.4 Qualification Criteria . . ....... . . . .. . .... .. 3D-3 3D.4.1 Qualification Guides . . . . . ... ... . 3D-3 3D.4.2 Definitions . . . . ..... . .. . . . . .. . .. ... 3D-7 }
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| 3D.4.3 Mild versus Harsh Environments . .. ... .. . 3D-7 l
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| 3D.4.4 Test Sequence . . .. . .. .. . ... . .. . . . 3D-8 !
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| 3D.4.5 Aging ........ .... . .. .. . .... .. . 3D-9 I 3D.4.6 Operability Time .... .. ... . .. . .... . 3D-12 3D.4.7 Performance Criterion .. . . . . .... . . ... 3D-12 !
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| 3D.4.8 Margin .. .. . ... . . . ... . .. 3D-12 3D.4.9 Treatment of Failures . . . . . . . . .. . . . 3D-15 3D.4.10 Traceability ......... .. . . . ... .. 3D-16 I 3D.5 Design Specifications . . . . . .. . . .. . . . .. 3D-17 3D.5.1 Normal Operating Conditions . . .. .... . 3D-18 3D.5.2 Abnormal Operating Conditions . .. ... . . .. 3D-19 i 3D.5.2 Seismic Events . . . . . . .. .
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| . .. .. .. .. . 3D-20 3D.5.4 Containment Test Environment . . .. . . . 3D-20 3D.5.5 Design Basis Event Conditions . . ... . .... . . . 3D-20 3D.6 Qualification Methods . . .. .. . . ... . ... . .... 3D-24 3D.6.1 Type Test .. ... .. . .. .. . .... . . . 3D-25 3D.6.2 Analysis .... .. ... . . ..... . ... . . 3D-25 3D.6.3 Operating Er.perience . . .. . . .. . . 3D-30 3D.6.4 On-Going Qualifiation . . . . . .. . . . 3D-30 3D.6.5 Combinations of Methods . . . . 3D-30 0
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| Revision: 10 December 20,1996 viii [ W8Stiflgh00S8
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| / k O MASTER TABLE OF CONTENTS (Cimt.)
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| Section Title Page 3D.7 Documentation . . . . . . . . . . . . ......... . . . . . . . . . . . . . 3 D-31 3D.7.1 Equipment Qualification Data Package . . .. .. .. ........ . 3D-32 3D.7.2 Specifications . . . ... . .. .. .... . ..... ...... 3D-32 l 3D.7.3 Qualification Program . . . . . . . . .. .. ......... . . . 3D-34 j 3D.7.4 Qualification by Test . . . . .... .. . . ...... . 3D-34 3D 7.5 Qualification by Analysis ... . .. ........... . 3D-37 3D.7.6 Qualification by Experience . . . . .. .. . ...... ... 3D-37 i 3D.7.7 Qualification Program Conclusions . . . .. .. . . . . 3D-37 3D.7.8 Combined License Information . . .. . ............ 3D-38 <
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| 1 3D.8 References . . . . ... . ..... .. . ... .. . ........... 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package .... . . 3D-69 i 1
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| Appendix 3D-Attachment B - Aging Evaluation Program .. . 3D-87 )
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| B.1 Introduction . . . . ...... ... . ... . . . . . . . . . . . . . 3 D-87 I B.2 Objectives . ... . .. .. . .. . . . ....... 3D-87 i
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| B.3 Basic Approach . . . . . ...... . .. . . . ... . 3D-87 B.4 Subprogram A . . ................. . ... . . ... . 3D-88 !
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| B.4.1 Scope . ... ...... .... . .. .. . . . . . . . . . . . 3D-88 h('s B.4.2 Aging Mechanisms . . . . . ..... ... ........ . . 3D-88 B.4.3 Time . . . . . . ...... .... . . . ....... .. .. . 3D-88 B.4.4 Operational Stresses ... . ..... .. ... ... ..... . . 3D-89 B.4.5 External Stresses ..... . ...... . . . .... . . 3D-89 B.4.6 Synergism . . . . . . . . . . .. .. . ... . .... .... . 3D-91 B.4.7 Design Basis Event Testing . . . . .. . .. ........ . 3D-91 )
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| B.4.8 Aging Sequence . . . . . . ... .. .. . .. ...... . . 3D-91 B.4.9 Performance Criterion . . ..... .. . ... .. .. . . 3D-91 B.4.10 Failure Treatment ... . . . ... . .. ... . .. 3D-91 B.5 Subprogram B .... ........ . . . . . ... . 3D-92 B.5.1 Scope ..... .. .... .. . ... .... . ... . . 3D-93 B.5.2 Performance Criteria . .. ... ......... ........ . . . . . 3D-93 B.5.3 Failure Treatment . . . . .. . .. .. .. .. . . . . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials .. . . ... . 3D-96 C.1 Introduction .... . . . . .. .... . .... ..... 3D-96 C.2 Scope. .. . . .. . .. .. . ... . ...... . ... 3D-97 C.3 Discussion ... ..... .. .. .. . . ... ... . 3D-97 C.4 Conclusions .... .. .... .. . . . .. . . . ... . . . . 3D-98 C.5 References . . . ...... .... . . .. 3D-98 m
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| v Revision: 10 3 Westingh00S8 ix December 20,1996
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| i --
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| l 7 Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_ age Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters .. ... . 3D-103 D.1 Introduction . ... ........ . . . .. . . ...... . 3D-103 D.2 Arrhenius Model . ..... . . .. . ..... . . 3D-103 1 D.3 Activation Energy ..... .. . .. .. .. ..... . 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) . .. .. 3D-106 i D.4.1 Normal Operation Temperature . . . .. . .. .. 3D-1% ,
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| D.4.2 Accelerated Aging Temperature . . ... 3D-107 I D.4.3 Examples of Arrhenius Calculations . ... . . . 3D-107 l D.5 Post-Accident Thermal Aging . .. . . .... . ......... 3D-108 l D.5.1 Post-Accident Operating Temperatures . .... . .. . ... 3D-108 D.5.2 Accelerated Thermal Aging Parameters for Post-Accident Conditions ... . . . .. ... .... .. . . 3D-109 D.6 References . ... . . . . . . . ... . . . 3D-109 i Appendix 3D-Attachment E - Seismic Qualification Techniques . .... . . 3D-115 i
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| E.1 Purpose . ... .. ..... . . . ... 3D-115 E.2 Definitions . ...... . . .. .. . . ....... . 3D-115 i E.2.1 1/2 Safe Shutdown Eanhquake . .. . 3D-115 l E.2.2 Seismic Category I Equipment . . ... . . 3D-115 l E.2.3 Active Equipment . . . .. . . .. . 3D-115 E.2.4 Passive Equipment . . ... . . .. . . 3D-115 E.3 Qualification Methods . . .... .... . .. . . 3D-116 E.3.1 Use of Qualification by Testing . . . . . .. .. 3D-116 E.3.2 Use of Qualification by Analysis . .. ..... . . 3D-116 E.4 Requirements . . . ...... . . .... . . 3D-117 E.4.1 Damping . . . . .. . . .. . . 3D-117 E.4.2 Interface Requirements . . . . . . . 317-117 E.4.3 Mounting Simulation . . . . . . . . . . . 3D-118 E.4.4 1/2 Safe Shutdown Eanhquake . . 3D-118 E.4.5 Safe Shutdown Earthquake ... . . .. . . 3D-118 E.4.6 Other Dynamic Loads . ... .. 3D-118 E.5 Qualification by Test . . . ... . .. . .. . . 3D-118 E.5.1 Qualification of Hard-Mounted Equipment . . 3D-119 E.5.2 Qualification of Line-Mounted Equipment . ... . . 3D-120 E.5.3 Operational Conditions . . .. . 3D-122 E.5.4 Resonant Search Testing . . . . .. . ... . . 3D-123 E.6 Qualification by Analysis . .. . . .. . . . 3D-123 E.6.1 Modeling . ........ ... . . . 3D-124 E.6.2 Qualification by Static Analysis ... . . . 3D-124 E.6.3 Qualification by Dynamic Analysis . . . . . 3D-124 O
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| Revision: 10 December 20,1996 x We@WSe
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| :--u Master Table of Contents
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| ! ,)
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| O MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_ age E.7 Performance Criteria . . . . . ... ............ .. . . .... . 3D-126 E.7.1 Equipment Qualification by Test ... ..... .. ... . ... . 3D-126 E.7.2 Equipment Qualification by Analysis ..... .. . .. . ... . 3D-126 i
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| APPENDIX 3E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND . .. ... . 3E-1 i
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| APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS . . . . . . . . . . . . 3 F- 1 3F.1 Codes and Standards . . . . . .. ... . . . ..... .. .. . 3F-1 3F.2 Loads and Load Combinations . . .. ... .. ... . . . . . . . . . 3 F- 1 3F.2.1 Loads . ... .. .. .. ....... ... . ..... ... . 3F-1 3F.2.2 Load Combinations . . . ........ ..... ...... ..... 3F-2 3F.3 Analysis and Design . . . . . . .. ...... . . . ....... . . . . 3F-2 1 3F.3.1 Damping . . . . . . . . . . . . .. .. .. .... ....... . 3F-2 l 3F.3.2 Seismic Analysis ......... .......... .. . ...... . 3F-3 l 3F.3.3 Allowable Stresses . . . . . . . . .. . .... . ...... . . 3F-3 i 3F.3.4 Connections .. ... . .. . . .. .. ..... .. . . 3F-3 I CHAlrrER 4 REACTOR... .... ... . .... .... . . . . ... . 4.1-1
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| (]
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| (/
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| 4.1 Summary Description 4.1.1 Combined License Information .
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| .. ....... . . . .... ... . . 4.1-1
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| .... . . .. . ...... 4.1-4 4.1.2 References . . . ......... .. .. .. . . . ..... . . 4.1-4 4.2 Fuel System Design ... .. .... . .. . . .... ..... 4.2-1 4.2.1 Design Basis . . . . . . . . . . ...... .. . .. .... . 4.2-2 i 4.2.2 Description and Design Drawings .. ... . . ... . .. 4.2-9 4.2.3 Design Evaluation . . . ... ....... ... . . ....... . 4.2-20 !
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| 4.2.4 Testing and Inspection Plan . . . . . .. . .... . .... . 4.2-32 4.2.5 Combined License Information . ... .... . . . .. . 4.2-37 4.2.6 References . . . .. ... .. . . ..... . . ... .... 4.2-37 l 4.3 Nuclear Design . ...... ..... .. . ...... . ...... .... 4.3-1 4.3.2 Description . .. .. . .. . . . . . . . . 4.3-7 4.3.3 Analytical Methods . ... . . . .. . . . .. . 4.3-39 4.3.4 Combined License Information . . .... . ..... . . 4.3-42 4.3.5 References . . .. .. .... .. . . ... . ..... . 4.3-42 4.4 Thermal and Hydraulic Design . . . . . . . . . . .. ... . .. .. . 4.4-1 4.4.1 Design Basis . . . .. . ..... .. .. ... .... . 4.4-1 4.4.2 Description of'Ihermal and Hydraulic Design of the Reactor Core . . 4.4-4 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System ................ . . ..... . 4.4-201 l 4.4.4 Evaluation ....... . ..... ... . ... ... . . . 4.4-21 4.4.5 Testing and Verification . .... .. . . . . . 4.4-30 4.4.6 Instrumentation Requirements . . . . . . 4.4-31
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| ,, m. 4.4.7 Combined License Information . . .. . . ... 4.4-35 v
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| Revision: 10
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| Master Table of Contents
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| MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_aage 4.4.8 References . . .. . ..... .. .. . . ...... . 4.4-35 4.5 Reactor Materials . ... ..... .. . .. . . ... . . 4.5-1 4.5.1 Control Rod and Drive System Structural Materials . ... . . 4.5-1 4.5.2 Reactor Internal and Core Support Materials ....... . 4.5-3 4.5.3 Combined License Information . ... . .. . . 4.5-4 4.5.4 References . . . .... .. .... .... .... ... . . . . 4.5-4 4.6 Functional Design of Reactivity Control Systems . ..... ...... .. . 4.6-1 i 4.6.1 Information for Control Rod Drive System . ....... .. .. . 4.6-1 l 4.6.2 Evaluations of the Control Rod Drive System . ....... .... . . 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System . ..... 4.6-2 4.6.4 Information for Combined Performance of Reactivity Systems . . . . . 4.6-2 4.6.5 Evaluation of Combined Performance .. .. . .. .. . 4.6-3 4.6.6 Combined License Information . . .. . .. .. . . 4.6-4 Volume 4 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS . .... 5.1-1 5.1 Summary Description .......... . . ... ..... .. . 5.1-1 5.1.1 Design Bases . . .. .... . .. .... ..... . 5.1-1 5.1.2 Design Description . . . .. .. . . .. . .. . . 5.1-2 5.1.3 System Components . . . . . . . .. .... . ... . 5.1-4 ;
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| 5.1.4 System Performance Characteristics . . . ...... .. .. 5.1-7 5.1.5 Combined License Information . .. . . . . . . . .. . 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary . . . ... ..... 5.2-1 5.2.1 Compliance with Codes and Code Cases . . . . ... 5.2-1 5.2.2 Overpressure Protection ... .. . . .. .. 5.2-2 5.2.3 Reactor Coolant Pressure Boundary Materials . ... . . .. . 5.2-7 5.2.4 Inservice Inspection and Testing of Class 1 Components . . . . . . . . . 5.2-17 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary 5.2-20 5.2.6 Combined License Information Items . . . 5.2-29 5.2.7 References . . . ... . . . .. .. . 5.2-29 5.3 Reactor Vessel . ..... .. . . . . . . . ... 5.3-1 5.3.1 Reactor Vessel Design .. . . ... . . .. 5.3-1 5.3.2 Reactor Vessel Materials .. .. . . . . 5.3-4 5.3.3 Pressure-Temperature Limits .. . 5.3-13 5.3.4 Reactor Vessel Integrity .. .. . . .... . . 5.3-14 5.3.5 Combined License Information . . . . . . .. 5.3-19 5.3.6 References . .. . . .... . . . . . 5.3-20 5.4 Component and Subsystem Design . . . . . . . . 5.4-1 5.4.1 Reactor Coolant Pump Assembly . . 5.4-1 O
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| Revision: 10 December 20,1996 xii 3 Westiflgh0USS
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| Master Tchte of Contents IV) MASTER TABLE OF CONTENTS (Cont.)
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| \
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| l Section Title Page, 5.4.2 Steam Generators . . . .. ... ... ........ .. .. . 5.4-10 !
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| 1 5.4.3 Reactor Coolant System Piping . ...... . ... . ... . 5.4-23 '
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| 5.4.4 Main Steam Line Flow Restriction .. . ... . ....... 5.4-28 l
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| 5.4.5 Pressurizer . ... . ..... ... . . .... .. ... 5.4-29 5.4.6 Automatic Depressurization System Valves . . . . . . . . . 5.4-36 l 5.4.7 Normal Residual Heat Removal System 5.4-38 l
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| 5.4.8 Valves . . ... ..... . .. .. . . ........... . . 5.4-51 ;
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| 5.4.9 Reactor Coolant System Pressure Relief Devices . . . . . . 5.4-57 I 5.4.10 Component Supports ... .. .. .. . . .... . . . 5.4-60 5.4.11 Pressurizer Relief Discharge ....... .. .. . . . . 5.4-63 5.4.12 Reactor Coolant System High Point Vents . . . .. .. . . 5.4-65 5.4.13 Core Makeup Tank . . .. ...... ...... ... .. . . . . . 5.4-68 5.4.14 Passive Residual Heat Removal Heat Exchanger .... . . . . . 5.4-71 5.4.15 Combined License Information . . . . . .... . ... . 5.4-74 5.4.16 References ... .. .. . . . . ... .... ....... 5.4-74 1
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| 1 CHAPTER 6 ENGINEERED SAFETY FEATURES . ... . .... ...... ... ... . 6.0-1 6.1 Engineered Safety Features Materials .. .. ...... . ... . . ... . 6.1 -1 l
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| ~~N 6.1.1 Metallic Materials . . 6.1-1
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| ) l 6.1.2 Organic Materials . . . . . .. .. .. .. . . . 6.1-5 6.1.3 Combined License Information Items . ... ...... 6.1-11 6.1.4 References . .. .. .. . ...... . . .... . . 6.1-12 6.2 Containment Systems . ..... . . . .. . .... .... .... 6.2-1 6.2.1 Containment Functional Design ... .. ... . . .. . . . . 6.2-1 6.2.2 Passive Containment Cooling System . . .. . .... . . . 6.2-20 6.2.3 Containment Isolation System . . . . . . ... . . . . . . . . 6.2-28 6.2.4 Containment Hydrogen Control System .. . . . . 6.2-378 6.2.5 Containment Leak Rate Test System . ...... . . ... . 6.2-48 6.2.6 References . . . . ... . . . .. . . .. . .. . . . 6.2-55 6.3 Passive Core Cooling System . . . .. . . . . .. 6.3-1 6.3.1 Design Basis . . . . . . . . . . .. . . . . . 6.3-2 6.3.2 System Design . . . . . . . . . . .. . . . 6.3-6 6.3.3 Performance Evaluation ... ...... .. . . . .. . . 6.3-28 6.3.4 Post-72 Hour Actions . . . ... .. . . .. . 6.3-41 6.3.5 Limits on System Parameters . .. . . . . 6.3-41 6.3.6 Inspection and Testing Requirements ...... . ... .. 6.3-42 6.3.7 Instrumentation Requirements .. . . . ... . . . 6.3-43 6.3.8 Combined License Information ... ...... . . . ... 6.3-48 6.3.9 References . . . ... . ..... . .. . . . . . . . 62 48 6.4 Habitability Systems . .... ....... ..... . .. . .. 6.4-1 6.4.1 Safety Design Basis . . . . . ... . .. .... . . . 6.4-1 6.4.2 System Description .... .. . .. . . .. . 6.4-2 6.4.3 System Operation . ... . . .. .. . 6.4-6 O
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| V) t Revision: 10
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| [ Westingt10US8 xii December 20,19%
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| i i ----~ ! :
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| MASTER TABLE OF CONTENTS (Cont.)
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| 9, l
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| Section Title Page 6.4.4 System Safety Evaluation ... .. .... .. ... . ..... . 6.4-8 6.4.5 Inservice Inspection / Inservice Testing . . .... . . 6.4-10 6.4.6 Instmmentation Requirements . .. ...... ....... .. . 6.4-10 6.4.7 Combined License Information . . ..... .. 6.4-11 6.4.8 References ......... .... ... .. .. ..... . . . 6.4-11 6.5 Fission Product Removal and Control Systems ...... ... . . . . . . . . 6.5- 1 6.5.1 Engineered Safety Feature (ESP) Filter Systems .. .. . 6.5-1 6.5.2 Containment Spray System ..... . . ... . . . . . 6.5-1 6.5.3 Fission Product Control Systems .... .. .. ........... . 6.5-1 6.5.4 Combined License Information . ... . ... . . . . . 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components . . . ... ... 6.6-1 6.6.1 Components Subject to Examination .... . ... . . . 6.6-1 6.6.2 Accessibility . . .......... ........ ..... . 6.6-1 6.6.3 Examination Techniques and Procedures . . . . .. . . .. . 6.6-2 ,
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| 6.6.4 Inspection Intervals .. ...... . .. .. .......... 6.6-3 6.6.5 Examination Categories and Requirements . . . . . . . . . . . . 6.6-3 6.6.6 Evaluation of Examination Results . . ....... . . . . . . . 6.6-3 l 1
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| 6.6.7 System Pressure Tests . . . . ............ .. ..... . .. . 6.6-3 6.6.8 Augmented Inservice Inspection to Protect against Postulated Piping Failures . . . .. . .. .. . . .. .. ..... .... 6.6-3 6.6.9 Combined License Information Items .. ... .. . . 6.6-4 CHAPTER 7 INSTRUMENTATION AND CONTROLS . . ..... . ... 7.1-1 7.1 Introduction . .. .. .... .. . . . .. .. . 7.1-1 7.1.1 The AP600 Instrumentation and Control Architecture . . . . . . . . 7.1-2 7.1.2 General Protection Subsystem Configuration .. . .... .. 7.1-6 7.1.3 Plant Control System . ... . .. .. . ..... ... . 7.1-27 7.1.4 Identification of Safety Criteria . ..... .... 7.1-32 7.1.5 AP600 Protective Functions .... . . . .. ... . 7.1-48 7.1.6 Combined License Information . . . .. . 7.1-48 7.1.7 References . . . . . . . .... . . .. .... .. . . 7.1-49 7.2 Reactor Trip . ..... .. . . .... . . . 7.2-1 7.2.1 Description ....... . . . . . .... . . 7.2-14 7.2.2 Analyses . . ...... ... ... ........... .. ... . . 7.2-14 7.2.3 Combined License Information . . . . . . . ... .. . 7.2-17 7.2.4 References . .. .. .. .. . .. . . . . . 7.2-17 7.3 Engineered Safety Features . . . . .. . .. . .. ... . . 7.3-1 7.3.1 Description . ...... . . . . . .. . ... . . . 7.3-1 7.3.2 Analysis for Engineered Safety Features Actuation . .. .... . 7.3-19 7.3.3 Combined License Information . . . . .... .. . . 7.3-22 7.4 Systems Required for Safe Shutdown . .. . 7.4-1 O
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| Revision: 10 December 20,1996 xiv [ Westinghouse
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| a Master Table of Contents f
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| 1 l3 V) i MASTER TABLE OF CONTENTS (Cont.) I i
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| Section Title Page !
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| 7.4.1 Safe Shutdown . . . . . . . . . . ... ... ... .... . . 7.4-3 7.4.2 Safe Shutdown Systems . . . . . . . ...... ....... .. . . 7.4-10 i 7.4.3 Safe Shutdown from Outside the Main Control Room . . .. . . 7.4-11 !
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| 7.4.4 Combined License Information . . . . .... . . .. . 7.4-14 i 7.4.5 References . ... .. ..... ..... .. .. . 7.4-14 7.5 Safety-Related Display Information . . ... . . .. ... . . . . 7.5-1 3 7.5.1 Introduction .. . .... . .. . ... .. .. . . . 7.5-1 ;
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| 7.5.2 Variable Classifications and Requirements . ..... ... . . . 7.5-1 7.5.3 Description of Variables ... ... ..... . .. . . .. .. 7.5-9 7.5.4 Processing and Display Equipment . . . ..... . . . .. . 7.5-11 7.5.5 Combined License Information . .... .. . ..... .. . 7.5-13 7.6 Interlock Systems Important to Safety . . . . ..... .. . .... ...... 7.6-1 7.6.1 Prevention of Overpressurization of Low-Pressure Systems . . . ... . 7.6-1 7.6.2 Availability of Engineered Safety Features ........ ... . . 7.6-2 !
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| 7.6.3 Combined License Information . . . .. . ... 7.6-5 7.7 Control and Instrumentation Systems ..... . . ... .. . . 7.7-1 7.7.1 Description .... . .... . . ....... .. . . . 7.7-2 7.7.2 Analysis ...... . . ...... . . ... .. . . 7.7 20 Og 7.7.3 Combined License Information . . . . .. .. .. . 7.7-21 t ;
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| v Volume 5 l
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| CHAPTER 8 CECTRIC POWER . . . . .. ... .. .. . . .... . 8.1-1 l 8.1 Introduction . . . . .. ... ...... .. . . ....... . ... . . 8.1-1 8.1.1 Utility Grid Description . . . . .... . ........ . . 8.1-1 8.1.2 Onsite Power System Description . .. ....... .. . . 8.1-1 8.1.3 Safety-Related Loads . .. . . .... . .. ... 8.1-2 8.1.4 Design Basis . ......... .. . .... . . . . 8.1-2 8.1.5 Combined License Information . .. . .. . ... 8.1-5 l 8.2 Offsite Power System . .. .. ..... ... ... . . . 8.2-1 8.2.1 System Description .. . .. . . . . . 8.21 8.2.2 Conformance to Criteria ..... . ..... .. . 8.2-2 8.2.3 Standards and Guides . . . . . . . .. . . . 8.2-2 8.2.4 Combined License Information for Offsite Electrical Power . . 8.2-2 8.2.5 References . . .... . . .. .... . . 8.2-2 8.3 Onsite Power Systems .. ....... . . . .. . . . . . 8.3-1 8.3.1 AC Power Systems . . . . .. ..... . . 8.3-11 8.3.2 DC Power Systems . . . . .. ... . . . . . 8.3-13 8.3.3 Combined License Information for Onsite Electrical Power . . . . . 8.3-21 8.3.4 References . . . ... .. . . . 8.3-22 b
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| Revision: 10 3 Westillgt100S8 xy December 20,1996
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| ;_n Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) 9l l Section Title Pm CHAPTER 9 AUXILIARY SYSTEMS . . . ..... . .. . . .. ...... ...... 9.1-1 9.1 Fuel Storage and Handling . . . . ... ... ...... . . . .. . .. 9.1-1 9.1.1 New Fuel Storage . . . . . . .. ... . .... . .. ..... ... 9.1-1 9.1.2 Spent Fuel Storage . . .... . . . . . ... . ... . 9.1-5 9.1.3 Spent Fuel Pool Cooling System . . . .. .... .... 9.1-10 9.1.4 Light Load Handling System (Related to Refueling) . . . . . . . . . 9.1-21 9.1.5 Overhead Heavy Load Handling Systems . . . ........ . 9.1-34 9.1.6 Combined License Information for Fuel Storage Handling . . . . 9.1-40 9.1.7 References . . . . ........ .... .. . .. ... ... . 9.1-40 9.2 Water Systems ..... . ... . .... ....... .. . 9.2-1 9.2.1 Service Water System . . . . . . . . . . . . ... . . .. . 9.2-1 9.2.2 Component Cooling Water System . . . . . .. ... .. ..... . 9.2-7 9.2.3 Demineralized Water Treatment System .... . . .. ..... . 9.2-16 9.2.4 Demineralized Water Transfer and Storage System . . . . . . 9.2-20 9.2.5 Potable Water System . . . . . . . . . . . . .... . ... ...... 9.2-25 9.2.6 Sanitary Drainage System .... ... .. . . . . . . 9.2-28 9.2.7 Central Chilled Water System . .. .. .. . . .... . . . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . . . ..... . 9.2-36 9.2.9 Waste Water System .... .. . . . .. ... . 9.2-40 9.2.10 Hot Water Heating System . . . . .. ........ . . . . 9.2-44 9.2.11 Combined License Information . . . . . . . . .. . . . . . . . 9.2-47 9.2.12 References . . .. ... .. ....... . . .... . . . . . . . 9.2-48 9.3 Process Auxiliaries . . . . . ... . .... .. .. . .. ............. 9.3-1 9.3.1 Compressed and Instrument Air System . . .... . ... . 9.3-1 9.3.2 Plant Gas System . . . . .. . .. . . . .... . . 9.3-7 9.3.3 Primary Sampling System . . . . . . .. . . ..... . . . 9.3-10 9.3.4 Secondary Sampling System . . .. . . . . . . 9.3-15 ,
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| 9.3.5 Equipment and Floor Drainage Systems . .... 9.3-17 9.3.6 Chemical and Volume Control System . .. . .. . . 9.3-22 9.3.7 Combined License Information . ... .. . ... 9.3-43 9.3.8 References .. . .. .. . . .. . . . .. . 9.3-43 Volume 6 9.4 Air-Conditioning, Heating, Cooling, and Ventilation System ... . ... . 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System . .. . .. . 9.4-1 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System . . 9.4-15 9.4.3 Radiologically Controlled Area Ventilation System . . .. .. 9.4-26 9.4.4 Balance-of-Plant Interface ...... . . . . . ... 9.4-36 9.4.5 Engineered Safety Features Ventilation System . . . 9.4-36 O
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| Revision: 10 December 20,1996 xvi [ W65tingt10USB
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| Master Tcble of Contents L
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| (m i i
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| V) MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P,. a_ge 9.4.6 Containment Recirculation Cooling System ... .. ......... 9.4-36 9.4.7 Containment Air Filtration System . .. ............... .. . 9.4-41 9.4.8 Radwaste Building HVAC System ...... .... ......... 9.4-49 9.4.9 Turbine Building Ventilation System . .. ..... . . . . . . . 9.4-54 i 9.4.10 Diesel Generator Building Heating and Ventilation System ... .. 9.4-59 l 9.4.11 Health Physics and Hot Machine Shop HVAC System . . . 9.4-65 9.4.12 Combined License Information . . . . ... ... . ...... . 9.4-70 9.4.13 References .. ... ..... . .... .. . ... ... . . 9.4-70 9.5 Other Auxiliary Systems .. . ... .. . .. ... . .. . 9.5-1 9.5.1 Fire Protection System . . .. . .. ..... . . .... .. . 9.5-1 -
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| 9.5.2 Communication System . .. .. .. .. ... ..... . 9.5-14 9.5.3 Plant Lighting System . . . . . . . ... ...... .. . .... .. . 9.5-18 I 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System ..... . . 9.5-21 9.5.5 References . . . . . . . . . .. .... . .... . ....... . . . . 9.5-27 l
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| APPENDIX 9A FIRE PROTECTION ANALYSIS . ... .. . ...... . . . 9A-1 i 9A.1 Introduction . .. . . ..... .. .. ... .. ..... ... . . . 9A-1 9A.2 Fire Protection Analysis Methodology . . . . . . . .. . ..... 9A-1
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| / 9A.2.1 Fire Area Description . . 9A-1 (3) 9A.2.2 Combustible Material Survey . . .. ... ..... .... . 9A-2 9A.2.3 Fire Severity Categorization . . ., ..... ...... . ....... . 9A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations . . . . ......... ....... ...... . ...... . 9A-2 1 9A.2.5 Fire Protection Adequacy .. . . .. .... .. ........ . 9A-3 9A.2.6 Fire Protection System Integrity . . . . ... .... ... .... . 9A-4 9A.2.7 Safe Shutdown Evaluation . .. . .. ... . ... ........ 9A-4 9A.3 Fire Protection Analysis Results .. . . . . . .... .. 9A-8 9A.3.1 Nuclear Island . ..... ... ... .. ......... . . 9A-9 9A.3.2 Turbine Building .... . . . .. . ... .. ... . . 9A-61 9A.3.3 Yard Area And Outlying Buildings . . . . .. .. . .... . 9A-72 9A.3.4 Annex 1 and II Buildings . .. . .. . .... . . 9A-72 9A.3.5 Radwaste Building ... .. . ... . . 9A-88 9A.3.6 Diesel Generator Building . . . .. .. .. . . . . . . . . . 9A-90 9A.3.7 Special Topics . . . ..... .. .. . .. . .. . 9A-94 9A.4 References ... . ... . . ... .. .. .. . . . . . 9A-97 Volume 7 1
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| l CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM . ... . .... . 10.1-1 10.1 Summary Description ... . ..... .. . .. . .. .. 10.1-1 10.1.1 General Descriptionn . .. . . ... 10.1-1 10.1.2 Protective Features . . . . . ... . ... . 10.1-2
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| U l Revision: 10
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| ! WeStiflgh0LISO December 20,1996 xvii i
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| ma-Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P, age 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . 10.1-4 10.2 Turbine-Generator . . . . . . .. .. . . . . . ... . . . 10.2-1 10.2.1 Design Basis ..... .. . .... . . .. . . 10.2-1 10.2.2 System Description ...... .. . . . . .. . . 10.2-1 10.2.3 Turbine Rotor Integrity . . . . . .. . .. .. ...... . 10.2-11 10.2.4 Evaluation . . . . ....... . . ... ... . . ... . 10.2-17 10.2.5 Instrumentation Applications . . ..... ... .. ...... . 10.2-17 10.2.6 Combined License Information on Turbine Maintenance and Inspection . . . .. .. .. .... .. . . . . . . 10.2-19 10.2.7 References . ... .. ....... . .. . .. .. . .... 10.2-19 10.3 Main Steam Supply System . .... .. . .... ..... ... . . . 10.3-1 10.3.1 Design Basis ... .... . .. . . .. .. . 10.3-1 10.3.2 System Description . ....... . .. . .... 10.3-4 10.3.3 Safety Evaluation . . . . .. ... . . .. . . . 10.3-10 10.3.4 Inspection and Testing Requirements . . . . . ... .... 10.3-12 10.3.5 Water Chemistry .. .. . .... .. ... .. .. . . 10.3-12 10.3.6 Steam and Feedwater System Materials . .. .. . . 10.3-16 10.3.7 Combined License Information . . ... ..... ... . . 10.3-17 10.3.8 References . . . .. ... . . . . . . . . .. . 10.3-17 10.4 Other Features of Steam and Power Conversion System ... ..... . . 10.4-1 10.4.1 Main Condensers .. .. . .... . . .. . . . . . 10.4-1 l 10.4.2 Main Condenser Evacuation System . . .. .. .. ........ 10.4-4 10.4.3 Gland Seal System .. .. . .. ... . . ... .... . . 10.4-6 10.4.4 Turbine Bypass System ..... . ... ... . . 10.4-8 10.4.5 Circulating Water System .. . . . . ... .. 10.4-12 10.4.6 Condensate Polishing System . . . . .... .. . 10.4-17 10.4.7 Condensate and Feedwater Systems . . . . ....... 10.4-20 10.4.8 Steam Generator Blowdown System . . . . . . . ... . .. 10.4-35 10.4.9 Startup Feedwater System . . . . . . . 10.4-44 10.4.10 Auxiliary Steam System ... . . . . ...... 10.4-53 10.4.11 Turbine Island Chemical Feed . . .... 10.4-56 10.4.12 Combined License Information . .. . . . . . . . . .. 10.4-59 10.4.13 References . ... .... .. . 10.4-59 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT . . . ... .. . . . I1.1-1 11.1 Source Terms . . . .. . . ... . . . .. ... . .. . .. 11.1-1 11.1.1 Design Basis Reactor Coolant Activity .... ... .. . I1.1-1 11.1.2 Design Basis Secondary Coolant Activity . ..... I1.1-3 11.1.3 Realistic Reactor Coolant and Secondary Coolant Activity . I1.1-4 11.1.4 Core Source Term ......... . . 11.1-4 O
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| Revision: 10 December 20,1996 xy;i; T Westinghotise 1
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| Master Table of Contents O
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| 1 l 1
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| MASTER TABLE OF CONTENTS (Cont.)
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| Section Title ,Pmte 11.1.5 Process Leakage Sources . . . . . . ........ . . . I1.1-4 11.1.6 Combined License Information . . .. . .. .. . .. . 11.1-4 j 11.1.7 References . .... . . . . . . . .. . 11.1-5 i 11.2 Liquid Waste Management Systems .. . . .. . . . . . . .. I1.2-1 11.2.1 Design Basis . . ... .. ... . . ... .... . . . 11.2-1 11.2.2 System Description . . . . . . ..... ... ..... .. . . . . 11.2-6 i
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| 11.2.3 Radioactive Releases . . . . . . . . ... ... . . 11.2-18 11.2.4 Combined License Information . ... . .... ..... I1.2-20 11.2.5 References .... . .... . . . . .. .. .. .... . 11.2-20 j 11.3 Gaseous Waste Management System . . .. . . 11.3-1 l
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| 11.3.1 Design Basis . . . . ... .. ...... .... .. . .... 11.3-1 l 11.3.2 System Description . . . .. ... ... . . . . .. I1.3-4
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| 11.3.3 Radioactive Releases . . . . . . . . .. . .... 11.3-9 1 i
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| 11.3.4 Combined License Information . ....... . . ... I1.3-11 '
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| 11.3.5 References ... ... .. .. . . . . ... ... I1.3-11 11.4 Solid Waste Management ...... . .... ... ... . . . . I1.4-1 11.4.1 Design Basis . . . . . . . ... ... .. . . .... I1.4-1 11.4.2 System Description . .. ... .. .. . .. . . . . . 11.4-3 (3 11.4.3 System Safety Evaluation . ...... ... . .. . I1.4-13 V 11.4.4 Tests and Inspections . . . . . . ... . ...... . . I1.4-13 11.4.5 Quality Assurance . . . . . . . .. . . ... . .. . . I1.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program . .. ...... 11.4 13 11.4.7 References . . . . . . . . . . . . ... . ..... I1.4-14 l 11.5 Radiation Monitoring ..... .. .. . . .... .. 11.5-1 l 11.5.1 Design Basis .. . .. . ... . .. . . . . ..... 11.5-1 11.5.2 System Description . . .. . . .. . .. .... I1.5-2 11.5.3 Effluent Monitoring and Sampling . . .. ..... .... .. I1.5-13 11.5.4 Process and Airborne Monitoring and Sampling ... . . . I1.5-13 l 11.5.5 Post-Accident Radiation Monitoring . .. . .. .. . 11.5-14 11.5.6 Area Radiation Monitors ... . ... . .... I1.5-14 11.5.7 Combined License Information . . ... . . .. .. I1.5-17 CHAPTER 12 RADIATION PROTECTION . . . . . . . .. .. . . . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As. Low-As-l Reasonably Achievable (ALARA) . . . . . 12.1-1 l 12.1.1 Policy Considerations .. . .. .. .. 12.1-1 12.1.2 Design Considerations ... .. . . .. . . 12.1-2 12.1.3 Combined License Information . ... . .. 12.1-6 12.2 Radiation Sources . ....... . . . . . .. 12.2-1 12.2.1 Contained Sources ... . .. .. . . . 12.2-1 73 12.2.2 Airborne Radioactive Material Sources . . . . 12.2-6 Revision: 10
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| [ W85tingh00Se xix December 20,1996
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| a Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Eage a
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| 12.2.3 Combined License Information . . .. .. ....... .. . 12.2-8 12.2.4 References . . . . . . . . . . . . . .. . . . .... ...... . . 12.2-8 12.3 Radiation Protection Design Features ... ... ........ .. . 12.3-1 12.3.1 Facility Design Features . .. .. . . .. .. ........ 12.3-1 12.3.2 Shielding . .... ... . . . .. . .. .... . . 12.3-9 12.3.3 Ventilation . . . . . . . . . . . . ... . . . . ........ 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation . . ... . ... . . . . .. . 12.3-19 12.3.5 Combined License Information . .... . ... . .. . 12.3-19 12.3.6 References .. .... .. . . . .... . .... 12.3-19 12.4 Dose Assessment .. .. . . .. ... .. . . . .. . 12.4-1 12.4.1 Occupational Radiation Exposure . . ... ... . . 12.4-1 12.4.2 Radiation Exposure at the Site Boundary ... . . .. . . 12.4-4 12.4.3 Combined License Information . . .. . .. .. . . 12.4-4 12.5 Health Physics Facilities Design . . . ... .. . .... . 12.5-1 12.5.1 Objectives . .. . . . ..... .. ... . . . 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities .. . . ........... 12.5-1 12.5.3 Other Design Features .... ... . .. ... ...... . 12.5-3 12.5.4 Controlling Access and Stay Time .. . .. . 12.5-4 12.5.5 Combined License Information . . .. . .. . ... 12.5-5 Volume 8 CHAPTER 13 CONDUCT OF OPERATION . ....... . . . . . .. 13-1 l
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| 13.1 Organizational Structure of Applicant .. .... . ... . . ... . . 13-1 i 13.1.1 Combined License Information Item . .. . . . .. . . .. . 13-1 13.2 Training .... .. . .... .. . ... .. . . . 13-1 13.2.1 Combined License Information Item . . ...... . 13-1 13.3 Emergency Planning . . . .. . .. . . .. . . . . 13-1 !
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| 13.3.1 Combined License Information Item . . . .... . 13-2 l 13.4 Operational Review . . . . .. . . . 13-2 13.4.1 Combined License Information Item . . ..... .. 13-2 13.5 Plant Procedures . . . .. . . ..... 13-2 13.5.1 Administrative Procedures . . . 13-2 13.6 Industrial Security . ... . . .. .. . . . 13-3 13.6.1 Preliminary Planning .......... . . .. . 13-3 13.6.2 Security Plan . . . . ...... . .. . ... . . . 13-3 13.6.3 Plant Protection System . . . .. . . 13-3 13.6.4 Physical Security Organization . . . . .... . 13-5 l 13.6.5 Physical Barriers . . .. . . 13-5 O
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| Revirion: 10 December 20,1996 xx W85tingh0USB
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| Master Table of Contents T
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| V MASTER TABLE OF CONTENTS (Cont.)
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| l 1
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| Section i Ii_tle Page 13.6.6 Access Requirements ..... . ... . .... . .. .. .. 13-6 !
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| 13.6.7 Detection Aids .... ... ... .. .. ..... ......... .. 13-7 l 13.6.8 Security Lighting . . . ........ . .... .. . .... 13-7 !
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| 13.6.9 Security Power Supply System . . .. . ......... 13-7 l 13.6.10 Communications . . . . . . . . . . . .. . . .... . ... 13-7 !
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| 13.6.11 Testing and Maintenance . ..... ..... .. . .. 13-8 l 13.6.12 Response Requirements . .. . .. . . . .. 13-8 I 13.6.13 Corabined License Information Item . . .. ... . . . 13-8 !
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| 13.7 References . . . .. .... .. . .... . ......... ... 13-8 1
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| CHAPTER 14 INITIAL TEST PROGRAM . . . . . . . . . . . . .... . . . . .... 14.1-1 !
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| 14.1 Specific Information to be Included in Preliminary / Final Safety ,
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| Analysis Repons ..... ...... .. .. ....... .... . . . 14.1-1 !
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| 14.2 Specific Information to be Included in Standard Safety Analysis Reports . . . 14.2-1 l 14.2.1 Summary of Test Program and Objectives . . .... .. . . 14.2-1 14.2.2 Organization, Staffing, and Responsibilities ...... . .... . 14.2-4 14.2.3 Test Specifications and Test Procedures ...... .. ... . 14.2-4 14.2.4 Compliance of Test Program with Regulatory Guides ...... .. 14.2-6 14.2.5 Utilization of Reactor Operating and Testing Experience in the V(~~N Development of Test Program . . . . . ... . . . . .. 14.2-6 14.2.6 Use of Plant Operating and Emergency Procedures . . . .. .. 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality .... . .. .... 14.2-7 14.2.8 Test Program Schedule . . .. .. ... ... . . . . 14.2-10 14.2.9 Preoperational Ter,t Descriptions . . . . ... . . . . 14.2-10 14.2.10 Startup Test Procedures . . . . . . . . . .. . 14.2-80 l 14.3 Certified Design Material . . . . . . ... . .. .. ... . . 14.3-1 14.3.1 CDM Section 1.0, Introduction . . ..... . . . 14.3-2 14.3.2 CDM Section 2.0, System Based Design Descriptions and ITAAC . ...... . . . . . ... 14.3-3 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC . .... . . . .. . .. . . 14.3-9 14.3.4 Certified Design Material Section, 4.0 Interface Requirements 14.3-10 14.3.5 CDM Section 5.0, Site Parameters . ... . 14.3-10 14.3.6 Initial Test Program ..... ... . . 14.3-10 14.3.7 Summary . . . .. . . .. . . . 14.3-11 14.3.8 References .... ....... . ... . . . 14.3-11 14.4 Combined License Applicant Responsibilities . .. .. 14.4-1 14.4.1 Organization and Staffing . . . . . . . . 14.4-1 14.4.2 Test Specifications and Procedures . . . . 14.4-1 14.4.3 Conduct of Test Program . . . . . . 14.4-1 14.4.4 Review and Evaluation of Test Results . 14.4-1 g
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| Revision: 10
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| [ Westingt10US8 xxi December 20,1996
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| s.-- 4 Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pm CHAPTER 15 ACCIDENT ANALYSES .. . ...... . .... ..... .. . . 15.0-1 15.0.1 Classification of Plant Conditions . . . . . . . . . . . . .. .... .. . 15.0-1 15.0.2 Optimization of Control Systems . . . . . . . . . . . ... .... . ... . 15.0-5 15.0.3 Plant Characteristics and Initial Conditions Assumed in the Accident Analyses . . . . . .... .... ... ......... . . . 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysis . . . . .... . 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics . . . .. ... . 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses . . . 15.0-8 15.0.7 Instrumentation Drift and Calorimetric Errors, Power Range Neutron Flux . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . ... . . .... .. ..... .... . 15.0-10 15.0.10 Residual Decay Heat . . ..... .... . .. .. ... .. . 15.0-10 15.0.11 Computer Codes Utilized . . . . . . . . . .... . ... ...... 15.0-11 15.0.12 Component Failures . .... ... . ..... .. . ..... ... . 15.0-13 15.0.13 Operator Actions . ....... ....... . . . . ... ... . 15.0-14 15.0.14 Combined License Information ..... .. . . . . .... 15.0-14 15.0.15 References . . ... . ........... . . . . .. . ........ 15.0-14 15.1 Increase in Heat Removal from the Primary System ... ... .. ... . 15.1-1 U.l.1 Feedwater System Malfunctions that Result in a Decrease in Feedwater Temperature . . . . .... . .. . 15.1-1 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow . . . .. . .. . . . ... . . ... . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow .. .. ... 15.1-5 15.1.4 Inadvertent Opening of a Steam Generator Relief or Safety Valve . . 15.1-8 15.1.5 Steam System Piping Failure . . . . . . . . . . . ....... 15.1-11 15.1.6 Inadvenent Operation of the Passive Residual Heat Removal Heat Exchanger . ..... .... .. . . . .. . 15.1-20 15.1.7 Combined License Information ... . .. . .. ... . 15.1-24 15.1.8 References .. .... . . ... .. ... .. .. 15.1-24 15.2 Decrease in Heat Removal by the Secondary System . . .... . 15.2-1 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . . . . . . .. .. .... . 15.2-1 15.2.2 Loss of Extemal Electrical Load . . . . . . 15.2-1 15.2.3 Turbine Trip ... ... . . ... .. .. . .... . . 15.2-3 15.2.4 Inadvertent Closure of Main Steam Isolation Valves . . .. . . 15.2-7 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries ....... . . . . . . . 15.2-8 15.2.7 Loss of Normal Feedwater Flow .. . . ... . .. 15.2-12 15.2.8 Feedwater System Pipe Break .. . . ..... 15.2-16 15.2.9 Combined License Information .. . .. ....... 15.2-21 O
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| Revision: 10 December 20,1996 xxi; [ W85tingh0US8
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| ;-- u
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| b MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age, 15.2.10 References . .. ... .. . . . ... . .... . 15.2-21 15.3 Decrease in Reactor Coolant System Flow Rate . . . . ...... ....... 15.3-1 15.3.1 Partial Loss of Forced Reactor Coolant Flow . . . . . .. .. .... . 15.3-1 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . . . . . . ... 15.3-3 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . . . 15.3-5 l
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| 15.3.4 Reactor Coolant Pump Shaft Break .. ..... . . ... ... 15.3-10 !
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| 15.3.5 Combined License Information .. ... ......... .. . . 15.3-10 15.3.6 References . . . . .... ..... .. .. .. .. . . . 15.3-11 15.4 Reactivity and Power Distribution Anomalies ... .. .... .... .. . 15.4-1 .
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| 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Suberitical or Low-Power Stanup Condition .... .. .. 15.4-1 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power . . . . . ..... .......... ...... . ...... . 15.4-5 15.4.3 Rod Cluster Control Assembly Misalignment (System Malfunction or Operator Error) . . .... .. .. . . 15.4-11 15.4.4 Startup of an Inactive Reactor Coolant Pump at an Incorrect Temperature ..... .. ...... ........ ... .. ... . 15.4-17 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling Water Reactor Loop that Results in an Increased Reactor O)
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| C Coolant Flow Rate .. . . ...... . .... . . 15.4-19 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant . . . . ... . .. . . .. . ... . 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position ...... .... .. ..... . ... 15.4-25 15.4.8 Spectmm of Rod Cluster Control Assembly Ejection Accidents .. 15.4-28 15.4.9 Combined License Information . . .. . ..... . .. 15.4-39 15.4.10 References . . . . . ..... . ..... .... . . .. . 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory .. . . . .. . .. .. . 15.5-1 15.5.1 Inadvenent Operation of the Core Makeup Tanks (CMT) During Power Operation .. .. ... .. . .. .. . ... 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory . . . ... . .. . 15.5-4 15.5.3 Boiling Water Reactor Transients . . . . ... .. . 15.5-8 15.5.4 Combined License Information . . ... .... . . 15.5-8 15.5.5 References . . . . . .... .. . .... .. .. .. 15.5-8 15.6 Decrease in Reactor Coolant inventory . . . . ... .. . 15.6-1 15.6.1 Inadvertent Opening of a Pressurizer Safety Valve or Inadvenent Operation of the ADS . . . 15.6-1
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| [v,\
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| 1 LI ' ; -- ; .
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| G, Section Title Page 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . . . . . . . ..... . ... .. .. .... . . 15.6-4 15.6.3 Steam Generator Tube Rupture .. ........ . .. . . . . . . 15.6-5 15.6.4 Spectrum of BWR Steam System Piping Failures Outside of Containment ... . . ..... ... . 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . .. .. . .. . . . ... 15.6-15 15.6.6 References ... .. .... ... .. . . ... . .. 15.6-64 15.7 Radioactive Release From a Subsystem or Component . . . .... 15.7-1 15.7.1 Gas Waste Management System Leak or Failure .... .. ... . 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ....... .. ..... ........ . . . . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a LiceH Tank Failure ... . .. . . .. .. ..... . . . . . 15.7-1 l 15.7.4 Fuel Handling Accident . . .... .. .. . .. . .. .. 15.7-1 l 15.7.5 Spent Fuel Cask Drop Accident . . ... .. .... . . 15.7-6 15.7.6 Combined License Information . . . . . .. . ... . .. . 15.7-6 l
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| 15.7.7 References . . . . . . . . .... . .. . ... . ..... .. . 15.7-7 15.8 Anticipated Transients without Scram . . . . . . . . . . . 15.8- 1 15.8.1 General Background ..... . ... . .. . ... . 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . .. .. . 15.8-1 15.8.3 Conclusion . . . .. ...... ... ... . . . . . 15.8-1 15.8.4 Combined License Information . .. ... . .. .. . 15.8-1 .
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| 15.8.5 References . . . . . . . .. .. ... .... . .. .. ... . 15.8-1 I APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS .. .... 15A-1 15A.1 Offsite Dose Calculation Models . . ... .. . . . . 15A-1 15A.1.1 Immersion Dose Models . . .... .. . 15A-1 l 15A.I.2 Inhalation Dose (Committed Effective Dose Equivalent) ..... 15A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) . . . ... . 15A-2 15A.2 Main Control Room Dose Models . .... . . . 15A-2 15A.2.1 Immersion Dose Models . . .... . .. . . . . 15A-2 15A.2.2 Inhalation Dose .. . . . .. .. . . 15A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) . . 15A-4 15A.3 General Analysis Parameters . ... ..... . . 15A-4 l 15A.3.1 Source Terms . . . .. ....... . .. . .. .. 15A-4 15A.3.2 Nuclide Parameters . . . . . .. . 15A-6 15 A.3.3 Atmospheric Dispersion Factors .. .. . 15A-6 l 15A.4 References . . . . .. . 15A-6 i Revision: 10 December 20,1996 xx y [ Westilighouse
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| \ l V MASTER TABLE OF CONTENTS (Cont.) l l
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| Section Title Page '
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| Volume 10 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS ....... . ... ..... . . . . . . . 16.1 -1 16.1.1 Introduction to Technical Specifications ... .... ... . . . 16.1-1 1.0 Use and Application .......... .. .... ..... . . . .. . 1.1-1 1.1 Defm' itions . . . .... . ... . . . . .. . . . . .. 1.1-1 1.2 Logical Connectors ...... ... . .. ... . . .. 1.2-1 1.3 Completion Times . .. . . .. .. .. . ... 1.3-1 1.4 Frequency ..... .. ...... ...... . . . . .. . 1.4-1 2.0 Safety Limits (SLs) . . . . . . . . . . . . .. ........... . 2.0-1 2.1 SLs .. . .......... .... .............. .. . 2.0-1 2.2 SL Violations .. ....... ..... ........ . .. . . 2.0-1 3.0 Limiting Conditions for Operation (LCO) Applicability . . . . . . . 3.0-1 3.0 Surveillance Requirement (SR) Applicability ... . . .. . . .. 3.0-4 3.1 Reactivity Control Syrems . . . . . . . . . . .... . . . . . . . . . . 3.1-1 3.1.1 Shutdown Marpn (SDM) . ..... . ....... .. . 3.1-1 3.1.2 Core Reactivity . . . . ... ... . . ........ . . . 3.1-2
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| ( 3.1.3 Moderator Temperature Coefficient (MTC) ... ..... 3.1-4 V] 3.1.4 Rod Group Alignment Limits . . . .. . .. . . .. . . .. . . . 3.1-6 3.1.5 Shutdown Bank Insenion Limits . .
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| . . . . . . . . . . . . . 3.1 - 1 1 3.1.6 Control Bank Insenion Limits ........ . . . . . 3.1-13 3.1.7 Rod Position Indication . .. .. .......... . .. . 3.1-16 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . . . . . . . . . 3.1 -18 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves . . . . . 3.1-20 3.2 Power Distribution Limits . . . . . . . . ............... .. 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fn (Z))
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| (FqMethodology) ... ..... .. ... .. ... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) ... . . . . .... .... . . 3.2-5 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial j Offset Control (RAOC) Methodology) .. ... ... 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . . . . .... .. . 3.2-10 3.2.5 OPDMS-Monitored Power Distribution i Parameters ........ . ...... ... . ... . . . 3.2-14 )
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| 3.3 Instmmentation . . . . . . . . 3.3-1 3.3.1 Reactor Trip System (RTS) Instmmentation . . .
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| .. 3.3-1
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| l 3.3.2 Engineered Safety Feature Actuation !
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| System (ESFAS) Instrumentation . . . . . ...... 3.3-17 3.3.3 Post Accident Monitoring (PAM) Instrumentation . . 3.3-45
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| : c. 3.3.4 Remote Shutdown Workstation . ... .. . 3.3-48 (v) 1
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| , Revision: 10
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| I li.NJ1 1 c l Master Table of Contents l EM -
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| l l l MASTER TABLE OF CONTENTS (Cont.) O1j l
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| Section Title Page i 3.4 Reactor Coolant System (RCS) . . . ..... ..... .... . . 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ... ... 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . .... 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits ...... .. 3.4-4 3.4.4 RCS Loops - Modes 1 and 2 .. . .... .. . . 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . ... ... . .. . 3.4-7 3.4.6 Pressurizer . ....... . . ... .. . ... .. 3.4-9 3.4.7 Pressurizer Safety Valves . . ... ... . . 3.4-10 3.4.8 RCS Operational Leakage ... .. . .. . . 3.4-12 ,
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| 3.4.9 Minimum RCS Flow . . . . .. .... . ... . . . 3.4-14 l 3.4.10 RCS Leakage Detection Instrumentation . . . ..... . . 3.4-15 ;
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| 3.4.11 RCS Specific Activity . ... .. . ..... . . . 3.4-18 j 3.4.12 Automatic Depressurization System (ADS)- Operating . 3.4-20 )
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| 3.4.13 Automatic Depressurization System (ADS) - Shutdown, ]
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| RCS Intact .... .... . .... ...... ... . . 3.4-22 !
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| 3.4.14 Automatic Depressuri.tatic:: System (ADS) - Shutdown, !
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| RCS Open . . . . . . . . . . . . . . . . . ....... . . . . . 3.4-24 j 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . . . . . ..... . ....... ... 3.4-26 !
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| 3.5 Passive Core Cooling System (PXS) ... . .......... . . 3.5-1 !
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| 3.5.1 Accumulators . . . . . . . .. . .. ... . . 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating . . . . . . . . . . . . 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . . 3.5-7 1 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating ..... .............. ... 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown. RCS Intact . . ......... . . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST)-
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| Operating . . .... . . . . . ... 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory High . ... . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low .. ... . ... 3.5-18 3.6 Containment Systems .. . . . ... . . . 3.6-1 3.6.1 Containment . . . . .. . .. . . . .. . . . 3.6-1 3.6.2 Containment Air Locks .. .... . . . .. .. 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . .. .. . 3.6-7 3.6.4 Containment Pressure . . . ... . . 3.6-12 3.6.5 Containment Air Temperature . . .. .. . . 3.6-13 O
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| Revision: 10 December 20,1996 xxvi 3 Westiligt10USB
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| Master T;ble of Contents V MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 3.6.6 Passive Containment Cooling System (PCS)- Operation . 3.6-14 3.6.7 Passive Containment Cooling System (PCS)- Shutdown . 3.6-17 3.6.8 Containment Penetrations . ...... . . . . . . . . . . 3.6- 19 3.6.9 pH Adjustment . . .............. .. . .. .. . 3.6-22 1 3.7 Plant Systems . . . . . . .. ............. .. .. . 3.7-1 l 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . ........ 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . . . . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves (MFIV and MFCV) . . .. .. .. ..... ... . .. .. 3.7-7 3.7.4 Secondary Specific Activity . . . . . . . . . . . . . . . . . .. 3.7-9 l 3.7.5 Spent Fuel Pool Water Level . . . . . . .. ... ..... 3.7-10 3.7.6 Main Control Room Habitability System (VES) . . . . . . 3.7-11 3.7.7 Startup Feedwater Isolation and Control Valves .. . . . 3.7-15 3.8 Electrical Power Systems . . . . . . . . . . ..... .......... 3.8-1 3.8.1 DC Sources - Operating . .. . ...... .... ... .. 3.8-1 3.8.2 DC Sources - Shutdown . . ........ . .. ... . 3.8-5 3.8.3 Inverters - Operating . . . . . . . . . ... ...... ... 3.8-7 3.8.4 Inveners, - Shutdown . . . . . . . ........ ...... . . . . 3.8-9 O 3.8.5 Distribution Systems - Operating .... ... ...... 3.8-11
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| () 3.8.6 Distribution Systems - Shutdown .... . . . . . . . . . . . . 3.8- 13 3.8.7 Battery Cell Parameters . . ........... . . . . . . . . . 3.8-15 3.9 Refueling Operations . . . . . . . . . . . ............. . .. . 3.9-1 ,
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| 3.9.1 Boron Concentration . . . . .. ...... ..... .... 3.9-1 l 3.9.2 Unborated Water Source Flow Paths . . 3.9-2 3.9.3 Nuclear Instrumentation . . . ....... .
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| . . 3.9-4
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| 3.9.4 Refueling Cavity Water Level . ..... . ..... .. . 3.9-6 4.0 Design Features . . . . ....... .. .... . ... ... . 4.0-1 4.1 Site . ..... .... .... . ....... . . .. 4.0-1 4.1.1 Site and Exclusion Boundaries . . .. .. . . . 4.0-1 4.1.2 Low Population Zone (LPZ) . . . ... . . 4.0-1 4.2 Reactor Core .. .... .. ... .......... .. 4.0-1 4.2.1 Fuel Assemblies . . . .. . .. . 4.0-1 4.2.2 Control Rod and Gray Rod Assemblies . .. . 4.01 4.3 Fuel Storage . ....... . ..... . .... . 4.0-2 4.3.1 Criticality . . . ... . . .... ... . .. 4.0-2 l 4.3.2 Drainage ..... ... .. .. . . .. . 4.0-2 4.3.3 Capacity .. ... . . ... .. . 4.0-2 4.4 Hydrogen Control . . .. .. . . ...... .. 4.0-3 4.4.1 Passive Autocatalytic Recombiners (PARS) .. .. 4.0-3 5.0 Administrative Controls . . . . . .. . .... . .. 5.0-1 5.1 Responsibility ........ . ... ... . .. .. . 5.0-1 5.2 Organization . . ..... . . .. . .. . . 5.0-2 i i v
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| Revision: 10
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| i!=- E Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) l Section Title P, age 5.3 Unit Staff Qualifications .. .... ..... .... . . 5.0-5 5.4 Procedures . . . . . . . . . .... . . ..... 5.0-6 5.5 Programs and Manuals . . ... ..... .. .. .... 5.0-7 5.6 Reponing Requirements . . . . . . . . 5.0-15 B 2.0 Safety Limits (SLs) . ...... ... .. .. ... . . . . B 2.0-1 B 2.1.1 Reactor Core Safety Limits (SLs) . . . . . . . B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . . . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability ... . . B 3.0-1 B 3.0 Surveillance Requirement (SR) Applicability . ... . ..... B 3.0-12 B 3.1 Reactivity Control Systems . . . ....... . . . . . B 3.1 - 1 B 3.1.1 Shutdown Margin (SDM) .. . . . . . . B 3.1 - 1 B 3.1.2 Core Reactivity ..... ...... . . . B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . . . . . . B 3.1-19 B 3.1.5 Shutdown Bank Insenion Limits . . . . . . . B 3.1-29 is 3.1.6 Control Bank Insenion Limits .... ..... B 3.1-34 B 3.1.7 Rod Position Indication .... ... . . B 3.1-40
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| " 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . . B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves .. . B 3.1-53 B 3.2 Power Distribution Limits . . . . . .. .......... . B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (Fn(Z))
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| (FqMethodology) . . ......... .... . . B 3.2-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F",w) . . . . ........... . . . . B 3.2-10 B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (Ql%) . . . . B 3.2-22 I B 3.2.5 OPDMS-Monitored Power Distribution Parameters . .. . .... .... ... B 3.2-28 B 3.3 Instrumentation . . ... .. . ... .... B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation . . B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System j (ESFAS) Instmmentation . . . . B 3.3-53 B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation . . . . .. ... . . . . B 3.3-115 B 3.3.4 Remote Shutdown Workstation . . . . . B 3.3-125 B 3.4 Reactor Coolant System (RCS) ..... . B 3.4-1 J
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| B 3.4.1 RCS Pressure, Temperature, and Flow Depanure from Nucleate Boiling (DNB) Limits . . . B 3.4-1 O
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| Revision: 10 December 20,1996 xxvii 3 Westirigh0USe 1 ,
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| (/ MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page B 3.4.2 RCS Minimum Temperature for Criticality . . . . B 3.4-6 B 3.4.3 RCS Pressure and Temperature (P/F) Limits . . B 3.4-9 B 3.4.4 RCS Loops - Modes 1 and 2 . .... ..... B 3.4-17 B 3.4.5 RCS Loops - Modes 3,4, and 5 . ........ B 3.4-21 B 3.4.6 Pressurizer . . . . . . . . . . . . . . . . ..... B 3.4-25 B 3.4.7 Pressurizer Safety Valves . . .... .... B 3.4-28 B 3.4.8 RCS Operational Leakage . ...... ..... B 3.4-32 B 3.4.9 Minimum RCS Flow . . ...... . ... . B 3.4-38 B 3.4.10 RCS Leakage Detection Instrumentation . . . . B 3.4-41 B 3.4.11 RCS Specific Acti rity . . . . . . . . . . . . . . . B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)-
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| Operating . . . . . . . . . . . . . . . . . . . . ..... B 3.4-50 B 3.4.13 Automatic Depressurization System (ADS.
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| Shutdown, RCS Intact . . . . .. ........ J 3.4-54 B 3.4.14 Automatic Depressurization System (ADS)-
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| Shutdown. RCS Open . . . . . . . . . . . . . ... B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . ............ . .. B 3.4-60 m
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| () B 3.5 Passive Core Cooling System (PXS) . . . . ...
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| B 3.5.1 Accumulators ... ........... .
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| B 3.5.2 Core Makeup Tanks (CMT) - Operating . . . . . B 3.5-8
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| . . . B 3.5-1
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| . . . . . B 3.5-1 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . .. . . . . . . . . . . .. .... . . B 3.5-15 B 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . . . . . . . B 3.5-18 I B 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . .... B 3.5-24 B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating ... . . B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory High B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low .. . .... .. B 3.5-38 B 3.6 Containment Systems . . ... . .. ... . B 3.6-1 B 3.6.1 Containment .. .. . ... . . . . . . B 3.6- 1 B 3.6.2 Containment Air Locks . ... . ... B 3.6-6 B 3.6.3 Containment Isolation Valves .. ... . B 3.6-13 B 3.6.4 Containment Pressure . . .. . ... B 3.6-23 B 3.6.5 Containment Air Temperature .... . B 3.6-26 B 3.6.6 Passive Containment Cooling System (PCS) - Operating . ..... .. . B 3.6-30 L)
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| Revision: 10 3 Westiligh00Se xx x December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown .. .. .... .. . . . B 3.6-37 B 3.6.8 Containment Penetrations . ... .... . . B 3.6-40 B 3.6.9 pH Adjustment ... ...... . . B 3.6-47 B 3.7 Plant Systems . . . ..... ... .......... . . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . B 3.71 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . .. B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) . ... . .. . . B 3.7-13 B 3.7.4 Secondary Specific Activity ... . . B 3.7-18 B 3.7.5 Spent Fuel Pool Water Level . . ...... B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability Systern . . . . ... . . . . . . . . . . B 3.7-24 B 3.7.7 Stanup Feedwater Isolation and Control Valves B 3.7-30 I B 3.8 Electrical Power Systems .... ... .... . . . . B 3.8-1 B 3.8.1 DC Sources - Operating ............... B 3.8-1 B 3.8.2 DC Sources - Shutdown . ... ...... . . . B 3 8-11 B 3.8.3 Inverters - Operating . . . . . . . . . . . . . . B 3.8- 15 '
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| B 3.8.4 Inveners - Shutdown . .. ...... ... . B 3.8-20 1 B 3.8.5 Distribution Systems - Operating ....... . B 3.8-24 B 3.8.6 Distribution Systems - Shutdown .... . . B 3.8.33 B 3.8.7 Battery Cell Parameters . . ........ ... B 3.8-37 ,
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| B 3.9 Refueling Operations . . ...... ........... . B 3.9-1 i B 3.9.1 Boron Concentration ........... . B 3.9-1 I B 3.9.2 Unborated Water Source Flow Paths . . . . . B 3.9-5 B 3.9.3 Nuclear Instrumentation . .... . . . . . . . . . . B 3.9-8 l B 3.9.4 Refueling Cavity Water Level .. .. .. B 3.9-11 ,
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| Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM . .. . ... . 16.2-1 16.2.1 Introduction . . . . .. ... ... . . .. 16.2-1 16.2.2 Scope .. ... . . . . .. . .. .. . . 16.2-1 16.2.3 Design Considerations . .. . ... . . .. . . . 16.2-1 16.2.4 Relationship to Other Administrative Frograms .. . .... 16.2-2 16.2.5 The AP600 Design Organization ... .... .. . . .. 16.2-2 16.2.6 Objective .. . ... . . .. ... .. .. .. . 16.2-3 16.2.7 D-RAP, Phase I . . ...... .... . . . ... . . 16.2-4 16.2.8 Combined License Activities - O-RAP . ..... ... . . 16.2-9 16.2.9 Glossary of Terms . . ..... . . ....... . . 16.2-10 0
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| Revision: 10 December 20,1996 xxx 3 Westilighouse
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| l Master Table of Contents
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| l G' MASTER TABLE OF CONTENTS (Cont.) l l
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| l Section Title, Page l 1
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| i 16.2.10 References . . . .. ... . . ... ... .. ... .. 16.2-11 .
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| 4 CHAPTER 17 QUALITY ASSURANCE . . . . . . . . .... ............ ... 17.1-1 17.1 Quality Assurance During the Design and Construction Phases . . . . . . . . 17 1-1 17.2 Quality Assurance During the Operations Phase . .... ..... . . 17.1-1 17.3 Quality Assurance During Design, Procurement, Fabrication, inspection and/or Testing of Nuclear Power Plant Item' and Services ..... . . . . . . . 17.1 -1 17.4 Combined License Information Items ....... ... .. .. . . 17.1-2 l 17.5 Refere nce s . . . . . . . . . . . . . . . . . . . . . . ...... . .... . . 17.1-2 l CHAPTER 18 HUMAN FACTORS ENGINEERING .. . ... .... .... . . . . . . 18.1-1 18.1 Overview . . ....... ......... ..... ..... .... 18.1-1 l 18.1.1 References ................ . .... .. .. .. . . 18.1-4 18.2 Human Factors Engineering Program Management . ... ..... . .... 18.2-1 18.2.1 Human Factors Engineering Program Goals, Scope, Assumptions, and Constraints . . . . . .......... .... . . 18.2-1 18.2.2 Human System Interfaces Design Team and Organization ...... 18.2-4 18.2.3 Human Factors Engineering Processes and Procedures , . . . . . . . . I8.2-11 l8.2.4 Human Factors Engineering Issues Tracking . . . . . . . . . ... ... 18.2-17 (Q) 18.2.5 Human Factors Engineering Technical Programs and Milestones . . . ...... . ............. .. .... . 18.2.18 18.2.6 Combined License Information . . . . . . . .... . .......... 18.2-19 18.2.7 References . . . . ...... ... .. ........ ...... .. 18.2-19 18.3 Operating Experience Review . . . . . . .... ..... . .. ....... . 18.3-1 18.3.1 Combined License Information . .. ..... . .. ...... . 18.3-1 18.3.2 References . .. ..... .. ... . . .. . . .. . 18.3-1 18.4 Functional Requirements Analysis and Allocation ........... .... . 18.4-1 18.4.1 Combined License Information . . . . ... ... ... .. . . . 18.4-2 18.4.2 References . . . . . . . . .. ..... .. ....... .. ........ 18.4-2 18.5 AP600 Task Analysis Implementation Plan ...... .... .. 18.5-1 18.5.1 Task Analysis Scope . . ... . .. .. . ...... 18.5-1 18.5.2 Task Analysis Implementation Plan . ... . . 18.5-2 18.5.3 Job Design Factors . . . . . . .. . .. . .. . . 18.5-5 18.5.4 Combined License Information Item . .. ... 18.5-5 18.5.5 References . .. .. .. .... . . . ... . . 18.5-5 18.6 Staffing . ..... . ... . . . . . 18.6-1 18.6.1 Combined License Information Item . . . . . . . . 18.6-1 18.6.2 References . . .. .... . ..... .... . . . 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering . 18.7-1 18.7.1 Combined License Information . . . . . .. ... 18.7-1 18.7.2 References ...... .. ... .. .... ... .... .... 18.7-1 m 18.8 Human System Interface Design ... .. .. ... . . ..... . I8.8-1 (nj )
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| Section Title a Page 18.8.1 Implementation Plan for the Human System Interface Design .. . . 18.8-3 18.8.2 Safety Parameter Display System (SPDS) .... . .. .... . 18.8-11 18.8.3 Operation and Control Centers . . . . . . . ... . .... . . . . I 8.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Portion of the Plant . . . . . .. . . ... .... ....... . 18.8-20 18.8.5 Combined License Information . . . . ......... ..... . I8.8-23 18.8.6 References ... . ... .. ...... ..... . .. ....... 18.8-23 18.9 Procedure Devrilopment . ... . . . . . . .. . ... .. . 18.9-1 i 18.9.1 Combmed License Information . . . . . .. ...... . 18.9-1 18.9.2 References . . . . . . . . . ... ... . . . ... ... 18.9-1 18.10 Training Program Development .......... . . ...... I8.10-1 18.10.1 Combined License Information . . .. . . . . . . .. . 18.10-1 18.10.2 References . . . . . .. ... . . . ......... . . 18.10-1 18.11 Human System Interface Design Test Program . . . .. ........ . 18.11-1 18.11.1 Combined License Information . . . ... .... .. .. 18.11-2 18.11.2 References ..... .. .. . ... .. . ......... 18.11 2 18.12 Displays, Alarms, and Controls . . . . . . . . . . . . ..... ... ..... . 18.12-1 18.12.1 Inventory of Displays, Alarms, and Controls .... ......... I8.12-1 18.12.2 Minimum Inventory of Main Control Room Fixed Displays, Alarms, and Controls .......... ..... . . .. .... :'' 12-1 18.12.3 Remote Shutdown Workstation Displays, Alarms, and Controls .. 18.12-7 18.12.4 Combined License Information . . . . . . . . . . . . . . . . . . . . . ..... 18.12 7 18.12.5 References . . . . . .. ... . .. ......... ...... 18.12-8 4
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| MASTER TABLE OF CONTENTS Section Title P_ age Volume 1 CHAMER 1 INTRODUCTION AND GENERAL DESCRINION OF PLANT . . . . . . 1.1-1 1.1 Introduction . .. ...... .. .. . . ...... . . . .. . 1.1-1 1.1.1 Plant Location .......... .. .... . .. . 1.1-1 1.1.2 Containment Type . .. . . . .... .. .. . . . 1.1-1 1.1.3 Reactor Type . .............. . ...... .. . .. . 1.1-1 1.1.4 Power Output .......... .. ........ .... .. .. . . . 1.1-1 1.1.5 Schedule .... . .... . ... ..... .... . ... . . 1.1-1 1.1.6 Format and Conteni ...... .. . . ...... ........... . . 1.1-2 1.1.7 Combined License Irformation . ...... .. ...... . 1.1-3 1.2 General Plant Description . . . . . . .. .. ........ .. . . ... . . 1.2-1 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 1.2.2 Site Description ... . ... .. . ..... ..... ..... . 1.2-15 1.2.3 Plant Arrangement Description . . . . . ..... ... . . .... 1.2-16 1.2.4 Nuclear Island . . ........ .. . ..... . . . . .... 1.2-17 1.2.5 Annex Building . . . . . . . . . . . ..... ... . . . 1.2-24
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| - 1.2.6 Diesel Generator Building ....... . .... . . ... . . 1.2-25 (3") 1.2.7 1.2.8 Radwaste Building . ................
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| Turbine Building . . . . . . . . . . .
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| 1.2-26 1.2-26 1.2.9 Combined License Information . . . .. ........ ............ 1.2-27 1.3 Comparisons with Similar Facility Designs ....... .... ..... ..... .. 1.3-1 1.4 Identification of Agents and Contractors . . . ................ . . . 1.4-1 1.4.1 Applicant - Program Manager . . .. ...... .. ......... 1.4-1 i 1.4.2 Other Contractors and Participants . . . . . . . . . . . . . . . . . . . . 1.4-1 l .4.3 Combined License Information . . . . . ... ....... . . . 1.4-3 1.5 Requirements for Further Technical Information ...... . . .. . . 1.5-1 1.5.1 AP600 Safety-Related Tests ........ ..... ... .. . . 1.5-1 1.5.2 AP600 Component Design Tests .. .... .... . . .. 1.5-7 ;
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| 1.5.3 Combined License Information . . . ... ... ... . 1.5-8 1.5.4 References . ....... . .. .. . ...... .. . ... . 1.5-8 1.6 Material Referenced .... ....... .. . ...... .. . . . 1.6-1 1.7 Drawings and Other Detailed Information .... .. ...... ........ . 1.7-1 j 1.7.1 Electrical and Instrumentation and Control Drawings . .... .. . 1.7-1 1 1.7.2 Piping and Instrumentation Diagrams ...... .... . . . 1.7-1 1.7.3 Combined License Information . . . ..... .. . . ... 1.7-1 i 1.8 Interfaces for Standard Design . .... .... . . ... . 1.8-1 1.9 Compliance with Regulatory Criteria . ... ... . ..... . . 1.9-1 1.9.1 Regulatory Guides . . .. . .. . . . . . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) .. . 1.9-3 1.9.3 Three Mile Island Issues . . . ....... . .. . . ... 1.9-3 gs
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| Section Title Page a
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| 1.9.4 Unresolved Safety Issues and Generic Safety Issues . . ....... . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues ........ 1.9-74 1.9.6 Combined License Information . . . . . .... .. ..... 1.9-107 1.9.7 References . . . .... . . ..... ....... . . 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES . . ..... . . . I A-1 1 A.1 References . . . . . ... ... . . . .. ... . 1 A-79 APPENDIX 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES . .... . 1 B-1 IB.1 Introduction . .. . ...... .. .... .... . . IB-1 1B.2 Summary . .. . . . ... ..... ... . .. . . . IB-1 I B.3 Selection of SAMDAS . . . . ... .. . .. . . ...... IB-2 1B.4 Methodology ....... . . . .... .. . . . .. . . IB-2 IB.4.1 Risk Reduction ... . ... . . ... .. ..... . 1B-2 ;
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| 1B.4.2 Capital Cost Estimates .... . .. .... ... . . . I B-3 !
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| 1 B.4.3 Cost Benefit Analysis . . .. . .. . . . . . . . . . . . . . 1 B-3 1B.5 PRA Release Categories . ..... .. ... ... ..... ............ 1B-3 ,
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| 1 B.5.1 Release Category OK . .......... . . .... . . . . . . . . . . 1 B-4 i
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| 1B.5.2 Release Category OKP . ..... . .. ... ............ 1B-4 1B.S.3 Release Category CC . . . .. . ..... .. .. . IB-5 1 B.S.4 Release Category CI . .... .... . . .. .. .. .. 1B-5 1B.6 Total Population Dose . . . . . .. ... .. . . .... .. .. . . . . I B-5 IB.7 SAMDA Description and Benefit . . . . . . . . . ...... . . 1B-6 1B.7.1 Upgrade the CVCS for Small LOCAs . ... . ....... . . I B-6 IB.7.2 Filtered Vent . . . . . . . . . . . . . . .. . .. .. . .. .... . IB-6 1B.7.3 Locate Normal RHR Inside Containment . .. ....... . 1B-7 1B.7.4 Self-Actuating Containment Isolation Valves ... . ... . . 1B-7 1B.7.5 Passive Containment Sprays . .... . . .... 1B-7 IB.7.6 Active High Pressure Safety Injection System . . . . ... IB-7 IB.7.7 Steam Generator Shell-Side Heat Removal System . . IB-8 1B.7.8 Direct Steam Generator Relief Flow to the IRWST . .. . IB-8 1 13.7 .9 Increased Steam Generator Pressure Capability .. . IB-8 IB.7.10 Secondary Containment Filtered Ventilation .. . . . . IB-8 IB.7.11 Diversify the IRWST Discharge Valves . . . . . . IB-9 1B.7.12 Ex-Vessel Core Catchet . ... . . . . . . 1B-9 1B.7.13 High Pressure Containment Design . . . . ... . . IB-9 IB.7.14 Increase Reliability of Diverse Actuation System . . I B-9 1 B.8 Results . . .. .. . .. . .. ... ....... . . . . . . 1 B-9 I B.9 References . ... . . . . .. ... .... ... IB-ll O
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| i C MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P,_ age P
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| CHAPTER 2 SITE CHARACTERIS"JCS ..... ....... . ........ .......... 2-1 2.1 Geography and Den ography . . . . . . . .. . . . . . . . . . . . . . . . . . . . ....... 2-1 !
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| 2.1.1 Combineo License Information for Geography and Demography . . . 2-1 2.2 Nearby Industria', Transportation, and Military Facilities ...... ....... 2-1 2.2.1 Combined License Iriormation for Identification of Site-specific ,
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| Potential Hazards ....... ...................... . 2-2 i 2.3 Meteorology . . . . . . . . . . . . . . . . . . . . . . . . ... .... ....... ... 2-2 2.3.1 Regional Climatology . . . . . . . . . . . . ......... .. ....... 2-3
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| . 2.3.2 Local Meteorology . . . . . . . . . . ................ . ... 2-3 '
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| 2.3.3 Onsite Meteorological Measurement Programs ..... .... .. 2-3 ,
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| 2.3.4 Short-Term Diffusion Estimates . . . . ............ ........ 2-3 2.3.5 Long-Term Diffusion Estimates . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 2.3.6 Combined Licensed Information . . . . . . . . . . . . . . . . . . . . . . . .. 2-4 2.4 Hydrologic Engineering . ................... ......... .... .. 2-5 2.4.1 Combined License Information ......................... . 2-5 2.5 Geology, Seismology, and Geotechnical Engineering . . ............... 2-6 2.5.1 Basic Geological and Seismic Combined License Information .... 2-6 2.5.2 Vibratory Ground Motion . . . . . . ...................... 2-7
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| (~' 2.5.3 Surface Faulting Combined License Information ..... ........ 2-7 ,
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| ( 2.5.4 Stability of Subsurface Materials and Foundations . . . . . . . . . . . . . 2-8 l 2.5.5 Combined License Information for Stability of Slopes . . . . . . . . . . 2-12 l 2.5.6 Combined License Information for Embankments and Dams . . . . . . 2-13 2.5.7 Re ferences . . .. . . . . . . . . . . . . . . . . ................... 2-13 APPENDIX 2A DESIGN SOIL PROFILES .,................................2A-1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. . . . . 2A-1 2A.2 Generic Soil Profiles . . . . . . . . . . . . . . . . . . .................. . . 2A-2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . .. . . 2A-4 2A.4 Free-Field Site Response Analysis . . .. ... .......... . . . . 2A-5 2.A.5 2D Soil-Structure Interaction Analysis ... .. . .............. . . . 2A-7 !
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| 2A.6 AP600 Design Soil Profiles .......... . ........... . . . . . . 2 A- 12 j 2A.7 References . . ....... ........... .. . ...... .. .... 2A-14 i APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DF9GN SOIL PROFILES . ... ................. .... .... ...... . . 2B-1 1 2B.1 2D SSI Analysis Parameters and Procedures ..... .. .... ... . 2B-2 2B.l.1 Structural Models ...... . .. . .. . .... ........ . 2B-2 i 2B.I.2 SASSI Foundation Models ..... ................ . 2B-2 2B.I .3 Soil Properties for SSI Analysis . . . . . . . . . . . . . . . . . . . . . . . . 2 B-2 2B.1.4 Input Motion ... ... .... .... .... . . . . . . . . 2B-3 2B.I .5 Two-Dimensional Enveloped SSI Results . .......... .. . 2B-3 2B.2 Design Soil Profiles .. ... .... . . ......... .. ... . 2B-3 V
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| Revision: 10 WilS8 iii December 20,1996
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| Section Title P, age 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . . . .. . ... . 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) ........ .. . . . . . . . . 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . . 2B-5 2B.2.4 Variation of Soil Propenies and 60 Percent Requirement of Free-Field Spectra at Foundation Level . . . . .. ... ... . 2B-5 2B.2.5 AP600 Design Soil Profiles ... . .... . . ....... . 2B-6 28.3 Soil Profile Parametric Studies: ..... .. . . ..... . 2B-6 2B.3.1 Depth-to-Base Rock . . . . . . . ... ..... . .. . ... 2B-7 2B.3.2 Soil Curves for Clay Material .. ... ... ......... 2B-7 2B.3.3 Poisson's Ratio for Soil above Water Table . . . . ... 2B-8 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site .. . . . . . 2B-8 2B.3.5 Idriss 1990 Soil Curves . . . . .. . . . .. 2B-9 2B.3.5 Soil Densitys . . . . .... . . . . . . . . 2B-9 2B.4 References . ..... ...... ... . .. . . . . .. . . 2B-9A Volume 2 APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES . . . . . . ..... .. ..... . 2C-1 2C.1 2D SASSI Analysis for Seismic Lateral Eanh Pressure . . .. .. .... . 2C-1 2C.l.1 Analysis Method . . . . . . . ... . .. .. .. .. . 2C-1 2C.1.2 Structural Models . .... .. ..... . . ... .. . 2C-1 2C.I .3 SASSI Foundation Models . .... . .. .......... . 2C-1 2C.I .4 Representation of Adjacent Structures . . .. .. 2C-2 2C.I.5 Input Motion . . .. . .. ........ . .. . . . 2C-2 2C.I.6 Soil Properties . . .. . . ..... . .. . 2C-2 2C.I .7 2D SASSI Analyses P.esults .. ..... .. .. . .. . 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island . .. . 2C-2 2C.3 Local Distribution of Lateral Earth Pressure . . . . . . ... . 2C-3 2C.4 References . .. ...... . ... . . . .. . 2C-4 CHAI'TER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUfPMENT AND SYSTEMS . . ... . . . . ...... . .. . . 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria . 3.1 1
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| ; 3.1.1 Overall Requirements . . .. .... ... . 3.1 -1 l 3.1.2 Protection by Multiple Fission Product Barriers . . . . . 3.1-4 l 3.1.3 Protection and Reactivity Control Systems . . 3.1-12 l 3.1.4 Fluid Systems ... .... . .. . . . . 3.1-18 3.1.5 Reactor Containment . ... .. . . . . . 3.1-30 3.1.6 Fuel and Reactivity Control ... . . . . . . ... '1-34 3.1.7 Combined License Information . . .. .. 3.1-37 3.1.8 References . ..... . .. . . . .. . 3.1-37 Revision: 10 December 20,1996 iv [ Westingh0USe
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| Section Title Page 3.2 Classification of Structures, Components, and Systems ........... . . 3.2-1 3.2.1 Seismic Classification . . . . . .. .. . .... .... . 3.2-1 3.2.2 AP600 Classification System .. . . .. .. . .... 3.2-3 3.2.3 Inspection Requirements . . ... . . ... .. . 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System . . . . . . .. . ..... 3.2-13 3.2.5 Combined License Information .. .. .. ... . 3.2-16 3.2.6 References . . . .. .. . . . .. . ... .. . . 3.2-17 3.3 Wind and Tornado Loadings . . ... . . . .. 3.3-1 3.3.1 Wind Loadings . ... . .. .. . . . . .. . ... . 3.3-1 3.3.2 Tornado Loadings . . .. . . .... .... ... 3.3-2 3.3.3 Combited License Information .. .. . .. .... . . 3.3-4 3.3.4 References . . . . ... . .. . . . 3.3-4 3.4 Water Level (Flood) Design ... . . .. ... . . .. 3.4-1 3.4.1 Flood Protection .. ... .. .. .. . 3.4-1 3.4.2 Analytical and Test Procedures .... .. .. . . . 3.4-24 3.4.3 Combined License Information . .. . . . .... . . . 3.4-24 3.4.4 References . . . .... . . .. ... ... . . . 3.4-24 ;
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| 3.5 Missile Protection . . . . .... 3.5-1 O
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| 3.5.1 Missile Selection and Description . . . .. ... .. ......... 3.5-4 b 3.5.2 Protection from Externally Generated Missiles .. ..... . . . . 3.5-13 ;
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| 3.5.3 Barrier Design Procedures .. .... ... ...... . . . 3.5-13 l 3.5.4 Combined License Information . ... ........ .. .. 3.5-16 j 3.5.5 References . . . . 3.5-16 3.6 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping . .... ., . . ....... . .. . 3.6-1 l 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment . ........ .. . . ... .. . .. 3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping .. . .. 3.6-12 3.6.3 Leak-before-Break Evaluation Procedures .. ...... ... . 3.6-31 3.6.4 Combined License Information . . ... 3.6-38 3.6.5 References . .. ... . . . . ... 3.6-38 3.7 Seismic Design .. . . ... ..... . 3.7-1 3.7.1 Seismic Input . . . .. . .. . .. . 3.7-1 3.7.2 Seismic System Analysis . .. . ... . 3.7-6 3.7.3 Seismic Subsystem Analysis . . . . . 3.7-20 3.7.4 Seismic Instrumentation . . . . . . 3.7-46 3.7.5 Combined License Information .. . . . 3.7-48 3.7.6 References . . . . ... 3.7-49 3.8 Design of Category I Structures . . . . . . .. . . 3.8-1 3.8.1 Concrete Containment .. . . . .. . 3.8-1 3.8.2 . Steel Containment . . . . . ..... 3.8-1 A
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| Section Title Page 3.8.3 Concrete and Steel Intemal Structures of Steel Containment ... 3.8-16 3.8.4 Other Category I Structures ...... . . .... .. . . . 3.8-39 3.8.5 Foundations .... .. ... . . . .. . . . 3.8-53 3.8.6 Combined License Information . .... .. . . . 3.8-60 3.8.7 References ... .... . . . ... . . . . 3.8-60 Volume 3 3.9 Mechanical Systems and Components . . . . .. ... . . . 3.9-1 3.9.1 Special Topics for Mechanical Components . .. . .... . . . 3.9-1 3.9.2 Dynamic Testing and Analysis . . ... . .. . .... . 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Components, Component Supports, and Core Support Structures .. . ... . 3.9-45 3.9.4 Control Rod Drive System (CRDS) .. . .. . . . 3.9-71 3.9.5 Reactor Pressure Vessel Intemals . . . . . .............. 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . . . . . . . ... . . 3.9-89 3.9.7 Integrated Head Package . .. . . .. . . ... . . . . 3.9-97 3.9.8 Combined License Information . ................... 3.9-102 3.9.9 References . . . . . .. . . .. ... .... . . . . . . . 3.9-103 ;
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| 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and '
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| Electrical Equipment . . . . . . . .... . ...... . ... . . . . . . . . 3.10- 1 3.10.1 Seismic and Dynamic Qualification Cdteria .. ..... ..... 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Instrumentation, and Mechanical Components ........ . . 3.10-3 3.10.3 Method and Procedures for Qualifying Supports of Electrical Equipment, Instrumentation, and Mechanical Components . . . . . . 3.10-7 3.10.4 Documentation . ... .. .. .. .... . .. . .. . . 3.10-7 3.10.5 Standard Review Plan Evaluation . .. ... .... .... 3.10-7 3.10.6 Comoined License Information Item on Expedenced-Based Qualification . . ... ... . . . . . . . . 3.10-8 3.10.7 References . . . ... ... . .. . . ... .... . . 3.10-8 3.11 Environmental Qualification of Mechanical and Electrical Equipmect . . . . . . 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . 3.11-1 3.11.2 Qualification Tests and Analysis . ... . . . 3.11-3 3.11.3 Loss of Ventilation . . . . ... . . . . . 3.11-4 3.11.4 Estimated Radiation and Chemical Environment .. . . . 3.11-5 3.11.5 Combined License Information Item for Equipment Qur.iification File . ... .... .. . . . . 3.11-5 3.11.6 References .. ... .. . . . . . . . . 3.11-6 O
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| Revision: 10 December 20,1996 y [ Westiligh00Se
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| i Section Title Pm APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS .......... . . . . . . . . . . . . . 3 A- 1 3 3A.1 Codes and Standards . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .........3A1 !
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| 3A.2 Loads and Load Combinations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 A- 1 l
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| ' 3A.2.1 Loads ..................... ............ . . . . . . . . . 3 A- 1 l 3A.2.2 Load Combinations . . . . .......
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| . . . . . . . . . . . . . . . . . . . . . . 3 A-3 3A.3 Analysis and Design . . . . . . . . . . . . . . . . . . ... ... . . . . . . . . . . . . . . 3 A-3 3 A.3.1 Response Due to Seismic Loads . . . .. . . . . . . . . . . . . . . . . . . . . . . 3 A-3 3A.3.2 Deflection Criteria ... .................. ............ 3A-3 3A.3.3 Relative Movement . ........... .... ... ... ..... . . 3 A-3 3A.3.4 Allowable Stresses . . . . ........ ..... .........., . . . 3A-4 3A.3.5 Connections . . . . . . . . . . . . . . . . . . . . . . . . . ........ . . . . . . 3 A-4 APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . . . . . . 3B-1 3B.1 Leak-Before-Break Criteria for AP600 Piping . . . . . . . . . . . . . . . . . . . . . . . 3B-2 l 3B.2 Potential Failure Mechanisms for AP600 Piping . .. .. ........... . . 3B-2 3B.2.1 Erosion-Corrosion Induced Wall Thinning . . . . . . . . . . . . . . . . . . . 3 B-2 3B.2.2 Stress Corrosion Cracking ............. ................ 3B-3 3B.2.3 Water Hammer ..... ..... ...... .. . . . . . . . . . . . . . . . 3 B-5 3B.2.4 Fatigue . . . . . . . . . . . . ................... . . . . . . . . . 3 B-9 3B.2.5 Thermal Aging ........... ... ........ ..... .... . . 3B-9 3B.2.6 Thermal Stratification . . . . . . . . . . . . . . ... ... . . . . . . . . . . 3B-10 3B.2.7 Other Mechanisms , . . . . . ..........................3B-13 3B.3 Leak-Before-Break Bounding Analysis . . . . . . . . . . .............. . 3B-13 3B.3.1 Procedure for Stainless Steel Piping . . . .. ...... . . . . . . . . 3B-13 3B.3.2 Procedure for Non-Stainless Steel Piping . . . . . . . . . . . . . . . . . . . 3 B- 16 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . . . . 3B-17 3B.3.4 Bounding Analysis Results .. ....... ... ... 3 B-21
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| 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and
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| Ferritic Steel Pipe . . . . . . . . . . . . . . . . . . . . . . . . . . . .... . . . . . . . . . 3 B 21 3B.5 Differences in Inspection Criteria for Class 1, 2, and 3 Systems . . . . . . . . . . 3B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, i
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| Class 2, and Class 3 Piping . . . . . . . . . . . . . . . . . .. . . . . . . . . 3 B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Lines . . . . . 3B-21 A .
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| 3B.8 Augmented In-Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators .... .... ....... . ..... . . 3B-21 A l 3B.9 References . . .... ............. .. . . . . . . . . . . . . . . . . . . 3 B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS . . . . . ...... . . 3C-1 )
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| l 3C.1 Reactor Coolant Loop Model Description . . . . .. . . . . . . . . . . . . . . . . . 3C- 1 l 3C.1.1 Steam Generator Model . . . .... . .... ... .. ..... . . 3C-1 '
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| l 3C.I.2 Reactor Coolant Pump Model . . . .......... .. ..... .. 3C-2 3C.I.3 Reactor Pressure Vessel Model .... . .... ... . . 3C-2 rr d
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| l Revision: 10 Y W85tilighouse vi December 20,1996
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| L-- !
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| B Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title fage a
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| 3C.l .4 Containment Interior Building Structure Model . . .... .. . 3C-3 3C.I.5 Reactor Coolant Loop Piping Model . . . . . . . .. . ... ... . 3C-3 3C.2 Design Requirements . . . .... ... .. . . . ... . . 3C-3 3C.3 Static Analyses . . . . . . .. .. ... . ...... .. ...... 3C-4 3C.3.1 Deadweight Analysis . . . . . . ... ... ... ...... . 3C-4 3C.3.2 Internal Pressure Analysis . . .. . ... .... .. . . . 3C-4 3C.3.3 Thermal Expansion Analysis . . . . . ... . . .. . . . 3C-4 3C.4 Seismic Analyses ... . . . .. . . ... .. . . . 3C-4 3C.5 Reactor Coolant Loop Piping Stresses . . . .. . .. .. ....... 3C-5 3C.6 Description of Computer Programs . . . . . .... . . . ... 3C-5 APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT . . . .. . . . . 3D-1 3D.1 Purpose . . . . ..... . ..... . ... .. .. . . . .. . . . 3D-2 3D.2 Scope.. . . .... ... ... . ... . .. ... .. . 3D-2 3D.3 Introduction . . . . . ... .... . . . . .. . . .. . . 3D-3 i 3D.4 Qualification Criteria . .. .. ... . . . . 3D-3 l
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| 3D.4.1 Qualification Guides . ... ... .. .. .. . ... . . 3D-3 1 3D.4.2 Definitions . . ..... . . .. .... ..... ..... . . 3D-7 3D.4.3 Mild versus Harsh Environments . .... . . . . . 3D-7 3D.4.4 Test Sequence .... ....... . ... ... .. ..... ... 3D-8 3D.4.5 Aging . . . . . ... ........ . .. ... . . . .. . . 3D-9 3D.4.6 Operability Time . .... . . ........ . . 3D-12 3D.4.7 Performance Criterion . . . . . . .. .... ....... . 3D-12 3D.4.8 M argin . .. ... .... . .. .. . . 3D-12 3D.4.9 Treatment of Failures . . .. . . .. .. . . 3D-15 3D.4.10 Traceability . . . .... . . .. . . . 3D-16 3D.5 Design Specifications . .. .... ... . .... . . . 3D-17 3D.5.1 Normal Operating Conditions . . . .. .. . 3D-18 3D.5.2 Abnormal Operating Conditions . . . . .. . 3D-19 l 3D.5.3 Seismic Events . .. .. . ..... .. . 3D-20 3D.5.4 Containment Test Environment . . .... .. 3D-20 l 3D.5.5 Design Basis Event Conditions . . . . . 3D-20 3D.6 Qualification Methods . ... . . . . ... . . . . 3D-24 3D.6.1 Type Test .. .... . ... . .. . .. . . . 3D-25 3D.6.2 Analysis . .. .. .. . . . . . 3D-25 3D.6.3 Operating Experience . ...... .. . . .. 3D-30 3D.6.4 On-Going Qualification . . . . . . 3D-30 l 3D.6.5 Combinations of Methods . . .. 3D-30 Revision: 10 December 20,1996 viii W85tkigh0USB
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| Master Table of Contents g) i U
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| MASTER TABLE OF CONTENTS (Cont.)
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| l Section Title M '
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| 3D.7 Documentation . . ..... . .. .. ... ... ...... ... . . . 3D-31 3D.7.1 Equipment Qualification Data Package . .. . ... .... . . 3D-32 3D.7.2 Specifications . .... ..... ........ .. . ... . . . 3D-32 I 3D.7.3 Qualification Program . . .. . .. .. ... .... . 3D-34 3D.7.4 Qualification by Test . .. .... . . .. . . . 3D-34 ,
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| 3D.7.5 Qualification by Analysis
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| . .. .... .. . .. . 3D-37 3D.7.6 Qualification by Experience . . . .. .... . . . . . . 3D-37 3D.7.7 Qualification Program Conclusions ..... . . . .. . . . . . 3D-37 l 3D.7.8 Combined License Information . . . . . . . . 3D-38 3D.8 References .. ..... . . . . ... .... . . ...... ..... . 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package . . . . . . . . . 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program . . . ..... . 3D-87 l B.1 Introduction . .. .. ...... . . . .. . 3D-87 l B.2 Objectives .... .... . . . . . .. . 3D-87 B.3 Basic Approach . . . ........ . .. . .. . . . . . . 3D-87 B.4 Subprogram A . ..... . .. .. . . ....... ....... 3D-88
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| /G B.4.1 Scope ... ...... . . . .... . . . . . . 3D-88
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| () B.4.2 Aging Mechanisms . . .. . ... . .... . . . . 3D-88 B.4.3 Time . ....... .. .. . .. . . ..... . 3D-88 B.4.4 Operational Stresses ...... . .. . ... . ...... 3D-89 i B.4.5 Extemal Stresses ... . .. .. . .. . ... 3D-89 B.4.6 Synergism . . . . . . . . ... ..... .. . . . . 3D-91 B.4.7 Design Basis Event Testing . .. . . .. ....... . 3D-91 ,
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| B.4.8 Aging Sequence . . . . . . . . ... .. . .. ..... . 3D-91 B.4.9 Performance Criterion . . ... .. . . . . 3D-91 B.4.10 Failure Treatment . . . .... .. . ... . . .. ... . . 3D-91 I B.5 Subprogram B . . .... . ... . . . .... . 3D-92 B.5.1 Scope . . ...... . . . ... . . 3D-93 B.5.2 Performance Criteria . . .. . .. . . 3D-93 B.5.3 Failure Treatment . . . . . . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials . . . .. 3D-96 l C.1 Introduction . . .. . ... . . 3D-96 C.2 Scope.... . . ... . . . . . 3D-97 C.3 Discussion . . . .. . . . 3D-97 C.4 Conclusions . . .. . . . . . . 3D-98 l C.5 References . . . .. . . ... 3D-98 i
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| .A i
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| , v l Resision: 10 3 W85tingh0USS x December 20,1996
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| ; Master Table of Contents 1
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| i MASTER TABLE OF CONTENTS (Cont.)
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| O l
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| Section Title Page
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| ! Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . . . . . . . . . . ... . 3D-103 D.1 Introduction ... .. ...... ....... ... ..... ... .. . 3D-103 D.2 Arrhenius Model . . . ....... ..... . .. .. ... .... . 3D-103 D.3 Activation Energy ..... ..... . .. . . . ... ...... 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) . . . . . . . 3D-106 D.4.1 Normal Operation Temperature . . . . . . . . . . . 3D-106 D.4.2 Accelerated Aging Temperature .. ... .. ... . 3D-107 D.4.3 Examples of Arrhenius Calculations . .. ... . . . . . . 3D-107 D.5 Post-Accident Thermal Aging . .... ... .. . . ... . .. . 3D-108 D.5.1 Post-Accident Operating Temperatures . .... ...... . . . 3D-108 D.5.2 Accelerated Thermal Aging Parameters for Post-Accident Conditions . . . . . . . . . . . ......... .. .. .......... 3D-109 D.6 References . .. . .. .......... . ... ... .. ... . 3D-109 Appendix 3D-Attachment E - Seismic Qualification Techniques . . .. .. . . . . . . . 3 D- 1 15 E.1 Purpose . . . . . . . . .. ..... .. .. .. .. . ... . 3D-Il5 E.2 Definitions . . . . . . . ........ . .. ... ... .. .. .. . . 3D-115 E.2.1 ' Safe Shutdown Earthquake
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| ./2 . . .. . .. . 3D-115 E.2.2 Sei:mic Category I Equipment . . . .. ............. . 3D-115 E.2.3 Active Equipment . .. .. .. .. .. ... . . . 3D-115 E.2.4 Past;ve Equipment . .... .. ... ... ......... . . 3D-115 E.3 Qualification Methods . . . . . .... ... .... .. . . . . . 3D-116 E.3.1 Use of Qualification by Testing .. . . . .. . .. .. . . 3D-116 E.3.2 Use of Qualification by Analysis . . . . . .. . . . . . . . . . . . . . . 3 D- 1 16 E.4 Requirements ............. .. .. ..... .. .. .... . 3D-Il7 E.4.1 Damping . . . ... ...... .. . . ... ..... . 3D-117 E.4.2 Interface Requirements . . . . . . . . . ... 3D-117 E.4.3 Mounting Simulation . ..... . .. ..... . 3D-118 E.4.4 1/2 Safe Shutdown Earthquake . ... . 3D-118 E.4.5 Safe Shutdown Earthquake .. . .. . . .. .. 3D-118 E.4.6 Other Dynamic Loads . .... . .. . . . . 3D-118 E.5 Qualification by Test . ......... ..... ..... . . 3D-118 E.5.1 Qualification of Hard-Mounted Equipment .. . 3D-Il9 E.5.2 Qualification of Line-Mounted Equipment .... .. . . 3D-120 E.5.3 Operational Conditions . . . . . . . 3D-122 E.5.4 Resonant Search Testing . . . . .. ..... . 3D-123 E.6 Qualification by Analysis . . . . ... .. . ... .. . . . . 3D-123 E.6.1 Modeling ... . .... . .. . . . . . 3D-124 E.6.2 Qualification by Static Analysis . . .. . . . . 3D-124 E.6.3 Qualification by Dynamic Analysis . . . .. . . . . 3D-124 O
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| Revision: 10 December 20,1996 x 3 Westingh0USe
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| na l Master Table of Contents
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| : /m I l \
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| l tU MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _Page E.7 Performance Criteria ... .... ..... ..... . ...... . . . . 3D-126 E.7.1 Equipment Qualification by Test . ...... ...... . . .. 3D-126 E.7.2 Equipment Qualification by Analysis . . .... ........ ... 3D-126 APPENDIX 3'E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND . . . . . . . . . 3E-1 APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS . . . . . . . . . . . 3F-1 3F.1 Codes and Standards .. ...... .. .. . .. .. . .. . . . . 3F-1 3F.2 Loads and Load Combinations . . . . .. ... . .. . .. . . 3F-1 3F.2.1 Loads .... ...... .... . .... . ... . . . . . . . . . 3 F- 1 3F.2.2 Load Combinations . . . . . . . . . .. .. .. . . . .. . . . 3F-2 3F.3 Analysis and Design ... ..... . .. . .. . . . . . . . . . 3F-2 3F.3.1 Damping . . . .... . .. .. .. . . . .. .. . .. 3F-2 3F.3.2 Seismic Analysis ... ..... ....... . . ... . . 3F-3 3F.3.3 Allowable Stresses . . .. . . . ........ .... . 3F-3 3F.3.4 Connections .. .. .... . . . ... .. .. . . . . . . 3 F-3 CHAIYTER 4 REACTOR..... ........ .... .. . . .. . .. . . . 4.1-1
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| (("x 4.1 Summary Description ........... 4.1-1
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| ,)
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| 4.1.1 Combined License Information . . ... .. . .... . . . 4.1-4 4.1.2 References . ... .. . . .. . ....... .... ........ 4.1-4 4.2 Fuel System Design . . . . . . . . . ..... .. . .. ...... ........ 4.2-1 4.2.1 Design Basis . . . . ....... . .... . .. ... . ... . . 4.2-2 4.2.2 Description and Design Drawings . .. ....... .......... . 4.2-9 4.2.3 Design Evaluation . . . . . . ...... .. ... . . . . . . 4.2-20 4.2.4 Testing and Inspection Plan . .... . .... ... . . . . . . . . 4.2-3 2 4.2.5 Combined License Information . .. . .. . .... . . . . 4.2-37 4.2.6 References . . . ... .. . . . . ... ........ . . . 4.2-37 4.3 Nuclear Design . . . ... .. ... . . . .... .. .. .. . 4.3-1 4.3.2 Description . ..... . . .. . . . 4.3-7 4.3.3 Analytical Methods . . . . . . . .. ... . . 4.3-39 4.3.4 Combined License Information . . . . .. . . 4.3-42 4.3.5 References . .... . . . .. . . . 4.3-42 4.4 Thermal and Hydraulic Design . . ... . .. .. . . . . . 4 A-1 4.4.1 Design Basis ... . . .... .. . . . 4.4-1 4.4.2 Description of Thermal and Hydraulic Design of the Reactor Core . . . 4.4-4 4.4.3 Description of tne Thermal and Hydraulic Design of the Reactor Coolant System ... .. . . .. . 4.4-201 4.4.4 Evaluation . . . . . . . ........ . . . . 4.4-21 l 4.4.5 Testing and Verification . . . . ... . . . 4.4-30 4.4.6 Instrumentation Requirements .. . . . 4.4-31 4.4.7 Combined License Information . . . 4.4-35
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| V Revision: 10
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| [ W85tiligt10USS x December 20,1996 1
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| :=u Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pm 4.4.8 References . . . .. . . .. .. . .... . . 4.4-35 4.5 Reactor Materials .. .. .. .... .. .. . ... .. . 4.5-1 4.5.1 Control Rod and Drive System Structural Materials ..... .. 4.5-1 4.5.2 Reactor Internal and Core Support Materials . . . 4.5-3 4.5.3 Combined License Information . . . .. . ... 4.5-4 4.5.4 References . .... ....... .. ... .. . . . 4.5-4 4.6 Functional Design of Reactivity Control Systems . ... . ..... .... 4.6-1 4.6.1 Information for Control Rod Drive System . . . . .... ... 4.6-1 4.6.2 Evaluations of the Control Rod Drive System .. ....... . . 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System .... . 4.6-2 4.6.4 Information for Combined Performance of Reactivity Systems . .. . 4.6-2 4.6.5 Evaluation of Combined Performance . . . ....... 4.6-3 4.6.6 Combined License Information . .. . . ... . .. .. 4.6-4 Volume 4 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS . . . . . . . . 5.1-1 5.1 Summary Description . . .... .. . . . ...... .. .. . 5.1-1 5.1.1 Design Bases . . . ... .. ... .. ....... .... ..... . 5.1-1 5.1.2 Design Description . . . . . . ... ... ... . .. . . 5.1-2 ;
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| 5.1.3 System Components . . . . . . .... . . ..... ... ....... 5.1-4 1 5.1.4 System Performance Characteristics . . ... . ...... .. . 5.1-7 5.1.5 Combined License Information . . .. .. . ... .. ... . 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary . . . ............ 5.2-1 ,
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| 5.2.1 Compliance with Codes and Code Cases . .. . . . . . 5.2-1 j 5.2.2 Overpressure Protection . . ... .. . . .. . . 5.2-2 l 5.2.3 Reactor Coolant Pressure Boundary Materials . . . .... . 5.2-7 !
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| 5.2.4 Inservice Inspection and Tecting of Class 1 Components . .. .. 5.2-17 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary . 5.2-20 5.2.6 Combined License Information Items . . ... . ... . . 5.2-29 5.2.7 References . . .. . ... . ... .... ... . .. 5.2-29 5.3 Reactor Vessel . . . . . ... . .... .. .. .. . ... ..... 5.3-1 5.3.1 Reactor Vessel Design . . ... . . . .. . . 5.3-1 5.3.2 Reactor Vessel Materials . . . .. ... .. 5.3-4 5.3.3 Pressure-Temperature Limits . . . . .. . . 5.3-13 5.3.4 Reactor Vessel Integrity .. . .. . . ... 5.3-14 5.3.5 Combined License Information .. .. .. . 5.3-19 5.3.6 References . ... .. .... . . . . . . . . 5.3-20 l 5.4 Component and Subsystem Design . .. . . . . . 5.4-1 5.4.1 Reactor Coolant Pump Assembly . . .... . .. . 5.4-1 O
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| Revision: 10 December 20,1996 xii [ W85tiligh0USB
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| :-+ !
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| Master Table of Contents f
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| (D
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| () MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Eaye i 5.4.2 Steam Generators . . .. . .. . . .. .. . 5.4-10 5.4.3 Reactor Coolant System Piping . . . . . ..... .. . .. 5.4-23 5.4.4 Main Steam Line Flow Restriction . . . . . . . .... .... .. . 5.4-28 i 5.4.5 Pressurizer . . . ...... ........ .. .. 5.4-29 l
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| 5.4.6 Automatic Depressurization System Valves . . . . . . .... . . 5.4-36 l 5.4.7 Normal Residual Heat Removal System . 5.4-38 5.4.8 Valves . . .
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| )
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| .... ...... .. . ... .. .. . .. . 5.4-51 ;
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| 5.4.9 Reactor Coolant System Pressure Relief Devices . 5.4-57 i
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| 5.4.10 Component Supports . . . .... . .. ... . . . . 5.4-60 5.4.11 Pressurizer Relief Discharge . . ... . . ... ... . 5.4-63 5.4.12 Reactor Coolant System High Point Vents . . . . . .. . . . 5.4-65 5.4.13 Core Makeup Tank ... . . .. .... . . . . . . 5.4-68 l 5.4.14 Passive Residual Heat Removal Heat Exchanger . . .... . . 5.4-71 5.4.15 Combined License Information . . . ....... ... .... . . 5.4-74 5.4.16 References ... ............ . ....... ... .. .. . 5.4-74 CHAPTER 6 ENGINEERED SAFETY FEATURES . . . .. .... .... . .. 6.0-1 I 6.1 Engineered Safety Features Materials ... . ............. .... .. . 6.1-1 l o 6.1.1 Metallic Materials . . . . . . . . . . . . . . . . . ... . . .. 6.1 1 ;
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| (' ) 6.1.2 Organic Materials .... .. . ...... .... . .. . .. 6.1-5 l 6.1.3 Combined License Information Items . .. ..... .. ... . 6.1-11 l 6.1.4 References . . .. ....... . .. ..... .. .. .. . 6.1-12 6.2 Containment Systems . ... ......... . . .. ... ....... . . 6.2-1 I 6.2.1 Containment Functional Design . . ....... .. ...... . .. 6.2-1 6.2.2 Passive Containment Cooling System . . .... . . . . 6.2-2G 6.2.3 Containment Isolation System .. .. . ... ... .. .. . 6.2-28 6.2.4 Containment Hydrogen Control System . . ... ... . . . 6.2-378 l 6.2.5 Containment Leak Rate Test System . . .... ..... . 6.2-48 6.2.6 References . .... ...... ..... ..... .. 6.2-55 6.3 Passive Core Cooling System . . .. . . .... . . . . 6.3-1 6.3.1 Design Basis . . . . . . . .. . .. . 6.3-2 6.3.2 System Design .. . .. ... . .. .. . 6.3-6 6.3.3 Performance Evaluation . .... . .. .. . . . . 6.3-28 6.3.4 Post-72 Hour Actions . . . .. . ..... 6.3-41 6.3.5 Limits on System Parameters . . . . . 6.3-41 6.3.6 Inspection and Testing Requirements .. .. .. 6.3-42 6.3.7 Instrumentation Requirements . . .. .... . . 6.3-43 6.3.8 Combined License Information . .. . .. . 6.3-48 6.3.9 References . . ... ... ... .. . . 6.3-48 6.4 Habitability Systems .. .... . .. .. . . ... . 6.4-1 6.4.1 Safety Design Basis . . . . . . .. .. . . . 6.4-1 6.4.2 System Description . . .. . . . . . .. . . 6.4-2 6.4.3 System Operation . . . . . .. . . . 6.4-6 im I k V
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| Revision: 10 W85dligh0USC December 20,1996 xiii
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| 1 l
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| l j Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h 6.4.4 System Safety Evaluation ... . .... . . . .. . 6.4-8 ;
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| 6.4.5 Inservice Inspection / Inservice Testing . . . .... . . . . . . . . . 6.4-10 j 6.4.6 Instrumentation Requirements ..... . . .. .. . 6.4-10 i 6.4.7 Combined License Information . . .. .. . . . 6.4-11 ,
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| 6.4.8 References . ... ....... ... . . . ....... . 6.4-11 l 6.5 Fission Product Removal and Control Systems ...... . . .. .... . 6.5-1 l 6.5.1 Engineered Safety Feature (ESF) Filter Systems . . .. ... .. 6.5-1 6.5.2 Containment Spray System .... . . ... ... . 6.5-1 6.5.3 Fission Product Control Systems . . . . . . 6.5-1 6.5.4 Combined License Information . . .. . . ..... . .... 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components . 6.6-1 6.6.1 Components Subject to Examination . .. . .. . . . . .. 6.6-1 i 6.6.2 Accessibility ... ... . . . . . ...... . 6.6-1 6.6.3 Examination Techniques and Procedures ... .. .... ... 6.6-2 6.6.4 Inspection Intervals . . . . . . . . ... . .. . .... .. .... ... 6.6-3 6.6.5 Examination Categories and Requirements . . ... ..... .... 6.6-3 6.6.6 Evaluation of Examination Results . . . ... . .. .. . .. 6.6-3 l 6.6.7 System Pressure Tests . . . .. . ... . ... . ...... . 6.6-3 6.6.8 Augmented Inservice Inspection to Protect against Postulated '
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| Piping Failures . . . . . . . . . . . . . . . ...... ... . 6.6-3 o.6.9 Combined License Information Items . .. . ... .. ... 6.6-4 CHAPTER 7 INSTRUMENTATION AND CONTROLS ... . . .. ... . .... 7.1-1 7.1 Introduction . .. .... .. ....... . ....... .. . .. .... 7.1-1 7.1.1 The AP600 Instmmentation and Control Architecture .. .. .. .. 7.1-2 7.1.2 General Protection Subsystem Configuration . ... .... . . 7.1-6 7.1.3 Plant Control System .. . .. . ..... . . . . 7.1-27 7.1.4 Identification of Safety Criteria . .. . . . . . . . . . . 7.1-32 7.1.5 AP600 Protective Functions . . . . . . .. . 7.1-48 7.1.6 Combined License Information . . . . . . 7.1-48 7.1.7 References ..... . . . . ... .. . 7.1-49 7.2 Reactor Trip .. . . .... . . . . . . 7.2-1 7.2.1 Description .. . ... . . . 7.2-14 7.2.2 Analyses . .. .... . .. .. . .. . .. .. 7.2-14 7.2.3 Combined License Information . . . . . . . . . 7.2-17 7.2.4 References . . . . . . . . . . 7.2-17 7.3 Engineered Safety Features . . . .. . . .. ... . 7.3-1 7.3.1 Description ........ ... ... .. . . .. . . . 7.3-1 l 7.3.2 Analysis for Engineered Safety Features Actuation . . . 7.3-19 7.3.3 Combined License Information . ... . . . . .. 7.3-22 7.4 Systems Required for Safe Shutdown . . .. ... . . .. 7.4-1 O
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| Revision: 10 December 20,1996 xiv 3 Westinghouse
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| 7.4.1 Safe Shutdown . . . . . . . . . . . . . ... .... ... ... . . . 7.4-3 1 7.4.2 Safe Shutdown Systems . . ... ....... . . ......... 7.4-10 l 7.4.3 Safe Shutdown from Outside the Main Control Room . ...... .. 7.4-11 7.4.4 Combined License Information . . .... .. . .... . . . 7.4-14 7.4.5 References . . . . . . . . . . . . . . . .... . ........ . ... 7.4-14 ;
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| 7.5 Safety-Related Display Information . . . .. .. .. . . . 7.5-1 l
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| 7.5.1 Introduction . . . . . . .... . . . ... .. . ..... . 7.5-1 7.5.2 Variable Classifications and Requirements . . ... ........ .. . 7.5-1 7.5.3 Description of Variables . . . . .... . ... .. .... .... 7.5-9 7.5.4 Processing and Display Equipment . . ... ... .. . . . . . . . . 7.5- 1 1 7.5.5 Combined License Information ... ... . . . . . . . 7.5- 13 7.6 Interlock Systems Important to Safety . ...... ...... .. ..... ... 7.6-1 7.6.1 Prevention of Overpressurization of Low-Pressure Systems . . . 7.6-1 7.6.2 Availability of Engineered Safety Features . .. . . .. .... 7.6-2 7.6.3 Combined License Information . . .. .... .. . 7.6-5 7.7 Control and Instrumentation Systems . . .... . .. ... .. .. 7.7-1 i 7.7.1 Description ... . .. .... . . . . . . . . .. . .. . 7.7-2 7.7.2 Analysis ..... ... .... ... ...... . .. . .. . 7.7-20 (3
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| i 4 7.7.3 Combined License Information . ..... .... . . . . 7.7-21 LJ Volume 5 CHAPTER 8 ELECTRIC POWER . . .. ....... . .... .. ... ...... . . 8.1 -1 8.1 Introduction . . . .......... .. . . . ..... .. .. .... . . 8.1-1 8.1.1 Utility Grid Description . . . . . . . .. ... .. . .... . . 8.1-1 8.1.2 Onsite Power System Description . . .... ... .. . . . 8.1-1 8.1.3 Safety-Related Loads .... ...... ... .. . . . 8.1-2 8.1.4 Design Basis . . ....... . ... . . ..... ... 8.1-2 8.1.5 Combined License Information . . . .. ... .. . 8.1-5 8.2 Offsite Power System . . . . ... .. . . 8.2-1 8.2.1 System Description . .. . . . . . 8.2-1 8.2.2 Conformance to Criteria . . . .. . . .. . 8.2-2 8.2.3 Standards and Guides .... . . . . . 8.2-2 8.2.4 Combined License Information for Offsite Electrical Power . . . . 8.2-2 8.2.5 References . .... .. . . .. . . .. . . 8.2-2 8.3 Onsite Power Systems .. . . . .. ... . . 8.3-1 8.3.1 AC Power Systems . . . ..... . .. . .. . 8.3-11 8.3.2 DC Power Systems . . . . . .. . ... . 8.3-13 8.3.3 Combined License Information for Onsite Electrical Power 8.3-21 8.3.4 References .. .. .. ... . .. . 8.3-22 l
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| Revision: 10
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| Section Title Page CHAlrl'ER 9 AUXILIARY SYSTEMS . . . ... ... .............. . . . . . 9.1-1 9.1 Fuel Storage and Handling . ... .. .. .. . . ... . ... . . 9.1-1 9.1.1 New Fuel Storage . . . . . ....... .... ....... .... . . 9.1-1 9.1.2 Spent Fuel Storage . . . .... .. . ... . . .. . .. . . 9.1-5 9.1.3 Spent Fuel Pool Cooling System .. . . ...... . . . . . . . 9.1-10 9.1.4 Light Load Handling System (Related to Refueling) ... ... . . 9.1-21 9.1.5 Overhead Heavy Load Handling Systems .... . .. . .. . 9.1-34 9.1.6 Combined License Information for Fuel Storage Handling . ... . 9.1-40 9.1.7 References . . . . . . ....... .. .... . .... . . . 9.1-40 9.2 Water Systems . ....... .......... . . .. ... .. . ... 9.2-1 9.2.1 Service Water System .. . . .. . . .... . . . .. . . 9.2-1 9.2.2 Component Cooling Water System . .. .... . . . .. . . . 9.2-7 9.2.3 Demineralized Water Treatment System .... .. . ... . . . . 9.2-16 9.2.4 Demineralized Water Transfer and Storage System . .... .. . . 9.2-20 9.2.5 Potable Water System . . . . .. .... .. . ..... . . . . . . . 9.2-25 9.2.6 Sanitary Drainage System . . . .. . .... . . . . . . 9.2-28 9.2.7 Central Chilled Water System . . .. ..... .......... . . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . ... . . . . . . . 9.2-36 9.2.9 Waste Water System ..... . . . ........... .... 9.2-40 9.2.10 Hot Water Heating System . .... ..... ......... . .. . . 9.2-44 9.2.11 Combined License Information . . ..... . ..... . . . . . . . 9.2-87 9.2.12 References . . . . ........ .. . .... . . ..... . . . . . 9.2-48 9.3 Process Auxiliaries . . . . . . . . . . . . . . . . . . .... ..... . . . . . . . 9.3-1 9.3.1 Compressed and Instmment Air System ....... .... . . . . . . 9.3-1 9.3.2 Plant Gas System . . . . . . ...... .. . . . . .. . . . 9.3-7 9.3.3 Primary Sampling System . . .. .... ..... . . . . . 9.3-10 9.3.4 Secondary Sampling System ... ... ... .... ... . 9.3-15 9.3.5 Equipment and Floor Drainage Systems .. . ... ..... . 9.3-17 9.3.6 Chemical and Volume Control System . .. . . ... . 9.3-22 9.3.7 Combined License Information . . . ... .. . . . . 9.3-43 9.3.8 References ... ... ... .. .. . .. . . 9.3-43 Volume 6 9.4 Air-Conditioning, Heating, Cooling, and Ventilation System . . . . .. 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System .. .. . 9.4-1 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System . 9.4-15 9.4.3 Radiologically Controlled Area Ventilation System .. . .. 9.4-26 9.4.4 Balance-of-Plant Interface . . . . .. ........ . .. 9.4-36 9.4.5 Engineered Safety Features Ventilation System .......... . 9.4-36 O
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| Section Title ,P_ age 9.4.6 Containment Recirculation Cooling System . . . . . . . . . ... . . 9.4-36 9.4.7 Containment Air Filtration System ...... . ... . . . . . . . . . . 9.4-41 9.4.8 Radwaste Building HVAC System . .. .. . . . . . . . . . . . 9.4-4 9 9.4.9 Turbine Building Ventilation System ............ ... . . . 9.4-54 9.4.10 Diesel Generator Building Heating and Ventilation System ... 9.4-59 9.4.11 Health Physics and Hot Machine Shop HVAC System . . . . . . . . . 9.4-65 9.4.12 Combined License Information .. . ... .... . .. 9.4-70 9.4.13 References . . . . . . . .... . .. . .. .. . . 9.4-70 9.5 Other Auxiliary Systems .. .. .. . . . . .. ... . . 9.5-1 9.5.1 Fire Protection System .... .... . .... . . .. .. .. . 9.5-1 9.5.2 Communication System ... . . . . . . . 9.5-14 9.5.3 Plant Lighting System . .. . . .. . . . . . . . . . . . 9.5- 18 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System ... . . . . . . 9.5-21 9.5.5 References . . ......... . ... . . . ... . . 9.5-27 APPENDIX 9A FIRE PROTECTION ANALYSIS . . .. .. . . . . . . . . 9 A- 1 9A.1 Introduction .. ....... ........ . . .. . ...... . . . . 9A-1 9A.2 Fire Protection Analysis Methodology . . . . . . ... . . . . . . . . 9A-1
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| /" 's 9A.2.1 Fire Area Description . .. ... ............. ..
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| (), 9A.2.2 Combustible Material Survey . .. .......... ..........
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| . . .. . 9A.1 9A-2 9A.2.3 Fire Severity Categorization . . . . . . . .... .... . . . . . . . . . . 9 A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations ........... .. ........... .. . ... . . . . 9A-2 9A.2.5 Fire Protection Adequacy ..... ... .... . . . ..... . . . 9 A-3 9A.2.6 Fire Protection System Integrity . . . .... ........ . . . . . 9A-4 9A.2.7 Safe Shutdown Evaluation . . .. . .. . . ....... ... 9A-4 9A.3 Fire Protection Analysis Results . ....... .. . .. . ..... . . . 9A-8 9A.3.1 Nuclear Island . . . . . . . . .. .. . .. ... . . . 9A-9 9A.3.2 Turbine Building ........ ... . . ... . 9A-61 9A.3.3 Yard Area And Outlying Buildings 9A-72 l 9A.3.4 Annex ! and II Buildings .. ... . .. . 9A-72 !
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| 9A.3.5 Radwaste Building . . . . . . . ..... . . .. 9A-88 9A.3.6 Diesel Generator Building . ...... .. . . . . . 9A-90 9A.3.7 Special Topics . . .. .. .. . . 9A-94 9A.4 References . . . ... .. . .. . . .. 9A-97 Volume 7 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM , . . . . 10.1-1 10.1 Summary Description ...... . . . ... ...... . . 10.1-1 10.1.1 General Descriptionn . . . . .. . . .. ... . . 10.1-1 10.1.2 Protective Features . . . . . . . . . 10.1-2 6
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| Revision: 10 3 W85tiflgh0US8 xvii December 20,1996
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| Section Title a Page 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . 10.1-4 10.2 Turbine-Generator . ..... . ... .. ,. . .. . 10.2-1 10.2.1 Design Basis .. .. . ... .. . .... . 10.2-1 10.2.2 System Description . . . . . .. .... . 10.2-1 10.2.3 Turbine Rotor Integrity ... .. .. .... 10.2-11 10.2.4 Evaluation ...... . .. ..... . ....... . .. .. 10.2-17 10.2.5 Instrumentation Applications . ... . . . . .. 10.2-17 10.2.6 Combined License Information on Turbine Maintenance and Inspection .. .... . . .. . . . .. 10.2-19 10.2.7 References . . . . .. .. . . .. . . .. . . 10.2-19 10.3 Main Steam Supply System .. .. . . . . . . 10.3-1 10.3.1 Design Basis. . . ... . .... . . .. 10.3-1 10.3.2 System Description . . ... .. . . .. . 10.3-4 10.3.3 Safety Evaluation . . .. .... .. .. . 10.3-10 10.3.4 Inspection and Testing Requirements . .... ... . 10.3-12 10.3.5 Water Chemistry . .. . . ... .... . . .... 10.3-12 10.3.6 Steam and Feedwater System Materials . . ...... .. . 10.3-16 10.3.7 Combined License Information . ..... . ... .. .. 10.3-17 10.3.8 References ..... . ....... ... . . . .. ..... 10.3-17 10.4 Other Features of Steam and Power Conversion System .. .... . . . . 10.4-1 10.4.1 Main Condensers . . . . . . .... . ... . .... .. . 10.4-1 10.4.2 Main Condenser Evacuation System . ... .. ... ... 10.4-4 10.4.3 Gland Seal System .. ... .. . . ... .... .. 10.4-6 10.4.4 Turbine Bypass System .. . .... .. . . ........... 10.4-8 10.4.5 Circulating Water System . . . .. .. . . . . 10.4-12 10.4.6 Condensate Polishing System . . . . . .. ... . .. . 10.4-17 10.4.7 Condensate and Feedwater Systems . . . . . . . . . .... 10.4-20 10.4.8 Steam Generator Blowdown System .. . ... . ... . . 10.4-35 10.4.9 Startup Feedwater System . . . . . . . . . 10.4-44 10.4.10 Auxiliary Steam System .... .. .. ...... . 10.4-53 10.4.11 Turbine Island Chemical Feed . . . . .. . . 10.4-56 10.4.12 Combined License Information . . .. .. . 10.4-59 10.4.13 References . . . .. . .. .. . . . 10.4-59 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT . . . . . . I1.1-1 11.1 Source Terms . . .. . . . . ... .. . . . I1.1-1 11.1.1 Design Basis Reactor Coolant Activity . . .. . I1.1-1 11.1.2 Design Basis Secondary Coolant Activity . .... . I1.1-3 11.1.3 Realistic Reactor Coolant and Secondary Coolant Activity .. . 11.1-4 11.1.4 Core Source Term . . . . . .. . . I1.1-4 O
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| Revision: 10 December 20,1996 xvii Westinghouse
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| () MASTER TABLE OF CONTENTS (Cont.) l Section. Title P,_ age 11.1.5 Process Leakage Sources .. . . .... ..... 11.1-4 11.1.6 Combined License Information . ...... . ... ... . . 11.1-4 11.1.7 References . ........... .. .. ... . . . . 11.1-5 11.2 Liquid Waste Management Systems . ... . . ... .... I1.2-1 11.2.1 Design Basis . ......... . ..... .. . . .. I1.2-1 11.2.2 System Description . .. . . . .. . ......... .. I1.2-6 11.2.3 Radioactive Releases . . . . . . .. ... .. .. . ...... I1.2-18 11.2.4 Combined License Information . ... .... . ........ . 11.2-20 11.2.5 References . . .. ....... ...... .. . ..... . . . 11.2-20 11.3 Gaseous Waste Management System . .. .. .... . ... 11.3-1 l 11.3.1 Design Basis . ..... . . ... .. . . ..... I1.3-1 ,
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| 11.3.2 System Description .. .. . . . .. .. .. .. .. . I1.3-4 l 11.3.3 Radioactive Releases . . . ... . . . .... . 11.3-9 ;
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| 11.3.4 Combined License Information . ..... . .. . ...... I1.3-11 i 11.3.5 References . . . . . . . ........ . ... . .. I1.3-11 11.4 Solid Waste Management .. .. . . . .. . . . . . . . 11.4- 1 ;
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| 11.4.1 Design Basis . . . . .... . . ... ... .... . . .. . 11.4-1 l 11.4.2 System Description . ... . . . .... .... .... I1.4-3 (3 .I1.4.3 System Safety Evaluation .. .. ....... ....... . 11.4-13
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| ( ,/ 11.4.4 Tests and Inspections ..... . .. . ... ......... 11.4-13 11.4.5 Quality Assurance . . .. . .. .... .... . ..... . 11.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program . .. ... .. ......... I1.4-13 11.4.7 References . . ...... .. . .. ....... 11.4-14 11.5 Radiation Monitoring ... . .. . . . .. ... . . . . . . 11.5 1 11.5.1 Design Basis .......... . ..... . . ........ . . 11.5-1 11.5.2 System Description . . . . ..... .. ... .. . 11.5-2 11.5.3 Effluent Monitoring and Sampling . ... . . .. .. . 11.5-13 11.5.4 Process and Airborne Monitoring and Sampling . . ... . 11.5-13 11.5.5 Post. Accident Radiation Monitoring . .. .. . 11.5-14 11.5.6 Area Radiation Monitors . . . .. . .. .. .. . .. . I1.5-14 11.5.7 Combined License Information . . . . . . 11.5-17 CHAPTER 12 RADIATION PROTECTION . . . . . . . . . . . . . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As-Low-As-Reasonably Achievable (ALARA) . . . . . .. . 12.1-1 12.1.1 Policy Considerations .. . . . . 12.1-1 12.1.2 Design Considerations . . . . .. . . . . 12.1-2 12.1.3 Combined License Information .. . . . . 12.1-6 12.2 Radiatien Sources . .. .... .. . . 12.2-1 12.2.1 Contained Sources . . . .. ... ... . .. .. . .... 12.2-1 c.s 12.2.2 Airborne Radioactive Material Sources .... ... . .. 12.2-6 Ih v
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| Resision: 10
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| [ Westingt10USB xx December 20,1996
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| Section Title ,Pm 12.2.3 Combined License Information . . . . . . . . . .. ..... . . 12.2-8 12.2.4 References . . . . . . . . . ................. . . .... .. 12.2-8 12.3 Radiation Protection Design Features . . . .. . .. . . . .. 12.3-1 12.3.1 Facility Design Features . .. . . . .. .. 12.3-1 12.3.2 Shielding . . . . . . . .. .. .. .. .... .. . 12.3-9 12.3.3 Ventilation . . . . .. .. ....... .. . . . ... .. 12.3-15 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instmmentation . . .. .. . . . .. .... ... .. 12.3-19 12.3.5 Combined License Information . . . . . . . . . 12.3-19 12.3.6 References ... .... ... . .... 12.3-19 12.4 Dose Assessment ... ... .... . .. .... . ....... 12.4-1 12.4.1 Occupational Radiation Exposure . . .... . . 12.4-1 12.4.2 Radiation Exposure at the Site Boundary . ... .. . 12.4-4 12.4.3 Combined License Information . . . . ... . . 12.4-4 12.5 Health Physics Facilities Design . . .... . . . ... . 12.5-1 12.5.1 Objectives . . . . . ..... ... . .. . ... .. . . 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities , . . . . .. . . ....... 12.5-1 12.5.3 Other Design Features . . .. .. . . ... ...... .. 12.5-3 12.5.4 Controlling Access and Stay Time . . .. .......... 12.5-4 12.5.5 Combined License Information . .. . .. .......... 12.5-5 Volume 8 CHAPTER 13 CONDUCT OF OPERATION . . . . .. ... . ..... .. ... 13-1 13.1 Organizational Structure of Applicant .. ... . . . .... .. ... . 13-1 13.1.1 Combined License Information Item . . . ... . .. ... .. 13-1 13.2 Training .. .......... .. . .. . . .... .. . 13-1 13.2.1 Combined License Information Item . . . . . .. . . 13-1 13.3 Emergency planning .. .. . . . . .. . . .. 13-1 13.3.1 Combined License Information Item . . . 13-2 13.4 Operational Review .. . . 13-2 13.4.1 Combined License Information Item . . . .. 13-2 13.5 Plant Procedures .. . . . . . ..... . 13-2 13.5.1 Administrative 140cedures . . 13-2 13.6 Industrial Security .. ... .. . . . . . 13-3 13.6.1 Preliminary Planning . ... . . . . . . 13-3 13.6.2 Security Plan ......... .. . . . . . 13-3 13.6.3 Plant Protection System . . . . . . . . 13-3 13.6.4 Physical Security Organization . . . . . 13-5 13.6.5 Physical Barriers .. .. ... . . . .. 13-5 O
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| Revision: 10 December 20,1996 xx Westinghouse
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| Section Title Page 13.6.6 Access Requirements .... ...... . . ..... .... . 13-6 13.6.7 Detection Aids . . . . . . . . . . ... . ... . . .. ........ . 13-7 13.6.8 Security Lighting . . ......... . ............ ... ..... 13-7 13.6.9 Security Power Supply System . . . . .. . ..... . . . 13-7 13.6.10 Communications . . ..... . . .. .. . .... . 13-7 13.6.11 Testing and Maintenance . . . . . .... . ... .. ... 13-8 13.6.12 Response Requirements . .......... . .... ... . . . 13-8 13.6.13 Combined License Information Item . . . . .. . 13-8 13.7 References . . . . . . . . . . . . . . .. ...... . . ......... . 13-8 ,
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| 1 CHAPTER 14 INITIAL TEST PROGRAM .. .... ... .. ... ......... . . . 14.1-1 l 14.1 Specific Information to be Included in Preliminary / Final Safety 1 Analysis Reports . . ............... .. .. ........ . . . . . 14.1 - 1 j 14.2 Specific Information to be Included in Standard Safety Analysis Reports . . . 14.2-1 ;
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| 14.2.1 Summary of Test Program and Objectives . . ...... . . 14.2-1 j 14.2.2 Organization, Staffing, and Responsibilities . . ...... . . . . . . 14.2-4 14.2.3 Test Specifications and Test Procedures .. ..... . . . . . 14.2-4 14.2.4 Compliance of Test Program with Regulatory Guides . ..... . . 14.2-6 (q,j 14.2.5 Utilization of Reactor Operating and Testing Experience in the Development of Test Program . ... . ... .. 14.2-6 14.2.6 Use of Plant Operating and Emergency Procedures . .. .. . . . 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality . . . . . .... .... . 14.2-7 14.2.8 Test Program Schedule ... .. . . ... .. .. . . 14.2-10 14.2.9 Preoperational Test Descriptions . ... .. . .... .. . 14.2-10 14.2.10 Startup Test Procedures . . . . . . .. . . ... .. . ... . 14.2-80 14.3 Certified Design Material . . . . . . . . . . ... .. .... ... . . . 14.3-1 14.3.1 CDM Section 1.0,Introduct;on . .. . ... .. . . . . 14.3-2 14.3.2 CDM Section 2.0, System Based Design Descriptions and ITAAC . . . ... ... . . ........ . 14.3-3 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC . . .... . ... ... ...... ... . 14.3-9 14.3.4 Certified Design Material Section, 4.0 Interface Requirements . . . 14.3-10 14.3.5 CDM Section 5.0, Site Parameters . . . ..... . . . 14.3-10 14.3.6 Initial Test Program . . . . . . ... .. . 14.3-10 14.3.7 Summary . .... ... .. .. . .. . . 14.3-11 14.3.8 References .... . . . . . . .... . . 14.3-11 14.4 Combined License Applicant Responsibilities .. .. .. 14.4 1 14.4.1 Organization and Staffing . . . . . . ..... . . 14.4-1 14.4.2 Test Specifications and Procedures .. .. . .. . 14.4-1 14.4.3 Conduct of Test Program . . . . .. .. .. . 14.4-1 14.4.4 Review and Evaluation of Test Results . . . 14.4-1 V
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| Section Title h j l
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| l CHAirTER 15 ACCIDENT ANALYSES . .. .... .. . . ............ 15.0-1 15.0.1 Classification of Plant Conditions .. . . ... . . .. . . . . 15.0-1 15.0.2 Optimization of Control Systems , . . . . ..... . ........ ...... 15.0-5 l 15.0.3 Plant Characteristics and Initial Condi: ions Assumed ;
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| in the Accident Analyses . ..... ..... .. ....... .... . .. 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysis . ... .. . . 15.0-7 ;
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| 15.0.5 Rod Cluster Control Assembly Insertion Characteristics . .. ..... . 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses . . . 15.0-8 15.0.7 Instrumentation Drift and Calorimetric Errors, Power Range Neutron Flux . . . 15.0-9 l 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . . . . .. . . .... . .... .... 15.0-10 !
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| 15.0.10 Residual Decay Heat . . . . ... ... . .. . . .. ... .... 15.0-10 15.0.11 Computer Codes Utilized . .. .. ... ..... . .. . .. .... . 15.0-11 15.0.12 Component Failures . . . . . ..... . ....... . ...... 15.0-13 l 15.0.13 Operator Actions . . .. . .. .. . . . . . .. .... 15.0-14 15.0.14 Combined License Information . . . . ... ..... . .. . . 15.0-14 15.0.15 References . .... ............. .... ... . .. . ..... 15.0-14 15.1 Increase in Heat Removal from the Primary System . . .. .. . ... 15.1-1 15.1.1 Feedwater System Malfunctions that Result in a Decrease m l Feedwater Temperature . . . . .. ... .. . . .. 15.1-1 l 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow . . . . . . .... .. . ..... . 15.1-3 j 15.1.3 Excessive Increase in Secondary Steam Flow . .. . . . ...... 15.1-5 15.1.4 Inadvertent Opening of a Steam Generator Relief or Safety Valve . . 15.1-8 15.1.5 Steam System Piping Failure . .. . ... .. ... . . .. 15.1-11 15.1.6 Inadvertent Operation of the Passive Residual Heat Removal Heat Exchanger . .. ...... .. . . ...... 15.1-20 15.1.7 Combined License Information ....... ... 15.1-24 15.1.8 References . . .. . . .. . . .. .. .. 15.1-24 15.2 Decrease in Heat Removal by the Secondary System . . .... 15.2-1 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . . ... . .. .. . . ...... 15.2-1 15.2.2 Loss of Extemal Electrical Load . ..... .. . . .. . 15.2-1 15.2.3 Turbine Trip ...... . .... ..... . ... . . 15.2-3 15.2.4 Inadvertent Closure of Main Steam Isolation Valves . .... .. . 15.2-7 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries . . . .. . .... 15.2-8 15.2.7 Loss of Normal Feedwater Flow . . . ... . .. .. . 15.2-12 15.2.8 Feedwater System Pipe Break . . . . 15.2-16 15.2.9 Combined License Information .. .. . . . 15.2-21 O
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| Revision: 10 December 20,1996 xxi Westilighouse
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| Section Title P. age 15.2.10 References .. ....... ......... . .... 15.2-21 15.3 Decrease in Reactor Coolant System Flow Rate .. .. ... . . . . . . . . 15.3-1 15.3.1 Panial Loss of Forced Reactor Coolant Flow 15.3-1
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| . .. ... . . . . l 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . . .... . . . 15.3-3 j 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . . . . ... . 15.3-5 15.3.4 Reactor Coolant Pump Shaft Break . . . .. . . ..... . . 15.3-10 15.3.5 Combined License Information . . . . . . . . ... ..... . . 15.3-10 1 1
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| 15.3.6 References ... .. . ......... ... . ..... ..... 15.3-11 l
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| 15.4 Reactivity and Power Distribution Anomalies . . . .. .. . . . . . . . . . 15.4-1 -
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| j 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a I Suberitical or Low-Power Stanup Condition .. . . . . .. 15.4-1 l 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal l at Power . . . . . . .. . .... ... .. .... . .. 15.4-5 15.4.3 Rod Cluster Control Assembly Misalignment (System i Malfunction or Operator Error) .. .. .. . .. . . . .. . 15.4-11 l 15.4.4 Stanup of an Inactive Reactor Coolant Pump at an Incorrect Temperature . . .. .... .... ... .. .. ..... . .. 15.4-17 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling
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| ,O Water Reactor Loop that Results in an Increased Reactor V Coolant Flow Rate . . . . .....
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| 15.4.6 Chemical and Volume Control System Malfunction That
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| . .. . ..... .. 15.4-19 Results in a Decrease in the Boron Concentration in the Reactor Coolant . .... . .... . .. ... .. .. . . 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position . . . . . . . . ..... .. . . . .... 15.4-25 15.4.8 Spectrum of Rod Cluster Control Assembly Ejection Accidents . . . 15.4-28 15.4.9 Combined License Information ... .. . . . .... . . 15.4-39 15.4.10 References . . ...... .. .. . .. .. . .. ...... 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory .. . . .. . . . .. . 15.5-1 15.5.1 Inadvertent Operation of the Core Makeup Tanks (CMT) During Power Operation . ... . . . .... . . . . . . 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory . . . . 15.5-4 15.5.3 Boiling Water Reactor Transients . . .. .. . . . 15.5-8 15.5.4 Combined License Information . .. ...... . . . 15.5-8 15.5.5 References . . ......... . . .. . ... . 15.5-8 15.6 Decrease in Reactor Coolant Inventory . . . .. 15.6-1 15.6.1 Inadvertent Opening of a Pressurizer Safety Valve or Inadvenent Operation of the ADS . . . . . 15.6-1 5
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| %.-l Revision: 10
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| [ W8Stingh0US8 xx i December 20,1996
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| .=i Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . . . . ... . . . .. . . . ... ... 15.6-4 15.6.3 Steam Generator Tube Rupture .... . ... .. ... 15.6-5 15.6.4 Spectrum of BWR Steam System Cping Failures Outside of Containment . ...... . ...... ... . .. . 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . . . . .. . . .. . .. .. .. . 15.6-15 15.6.6 References . ... .... .... ..... . . . . 15.6-64 15.7 Radioactive Release From a Subsystem or Component . . . . . . . . . . 15.7-1 15.7.1 Gas Waste Management System Leak or Failure . . ,.. . . 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ...... ... . .. ...... . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure . .......... ... . . . .. 15.7-1 15.7.4 Fuel Handling Accident . .. .. . . . . . . . 15.7-1 15.7.5 Spent Fuel Cask Drop Accident .. . . .. .. . 15.7-6 15.7.6 Combined License Information . . . . 15.7-6 15.7.7 References . . . .... .. . .. . .. 15.7-7 15.8 Anticipated Transients without Scram . .. . . . 15.8-1 15.8.1 General Background .. .. . . . . . . . 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . . 15.8-1 15.8.3 Conclusion . . ......... . . 15.8-1 15.8.4 Combined License Information . . . . .... .... . 15.8-1 15.8.5 References . . ..... .. . .. ... . . . 15.8-1 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS . 15A-1 15A.1 Offsite Dose Calculation Models . . .. . . 15A-1 15A.1.1 Immersion Dose Models . 15A-1 15 A.1.2 Inhalation Dose (Committed Effective Dose Equivalent) 15A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) . . . . 15A-2 15A.2 Main Control Room Dose Models . .. . . . .. ... 15A-2 15A.2.1 Immersion Dose Models . . ... . . . . 15A-2 15A.2.2 Inhalation Dose . . . . . . . . . . 15A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) . 15A-4 15A.3 General Analysis Parameters . . .. .... . . . 15A-4 l 15A.3.1 Source Terms . . . . . . . . . .. . . 15A-4 15A.3.2 Nuclide Parameters . . . . .. . . . . 15A-6 l 15A.3.3 Atmospheric Dispersion Factors . . . 15A-6 !
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| 15A.4 References . . ... . . . . 15A-6 Ol Revision: 10 December 20,1996 xxiy 3 W85tiligh00Se l
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page Volume 10 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS . ......... ....... ..... . 16.1-1 16.1.1 Introduction to Technical Specifications .. .... ...... . . 16.1-1 1.0 Use and Application ... .... . ....... ...... . . 1.1-1 1.1 Definitions . . ...... . . ... . .. . 1.1-1 1.2 Logical Connectors ... . .... . .. .. . 1.2-1 1.3 Completion Times . .... . . .. . .... . .. 1.3-1 1.4 Frequency .. .. .... .. ..... ........ 1.4-1 2.0 Safety Limits (SLs) .... . ... . ... . .. ..... . 2.0-1 2.1 SLs .................. . .... ... . .. . 2.0-1 2.2 SL Violations . ......... . ..... ... .... 2.0-1 3.0 Limiting Conditions for Operation (LCO) Applicability . . . . .. 3.0-1 3.0 Surveillance Requirement (SR) Applicability .. . .... . . 3.0-4 3.1 Reactivity Control Systems . . . . . . . . . . .. . . 3.1-1 3.1.1 Shutdown Margin (SDM) . . . . .... .. . . . . 3.1-1 3.1.2 Core Reactivity . ... .... . ... .. ..... . . 3.1-2
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| (~) 3.1.3 Moderator Temperature Coefficient (MTC) .. . . .... 3.1-4 V 3.1.4 Rod Group Alignment Limits . . . . . ... . . ... .. 3.1-6 3.1.5 Shutdown Bank Insertion Limits .. .. ..... . . . . 3.1-11 3.1.6 Control Bank Insertion Limits ...... .. ......... 3.1-13 3.1.7 Rod Position Indication . . . ... .. . . ...... . . 3.1-16 3.1.8 Physics Tests Exceptions - Mode 2 . .. ........... 3.1-18 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves . . . . . . . . . 3.1-20 1 3.2 Power Distribution Limits . ...... ...... 3.2-1 l
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| 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) l (FoMethodology) . . . ... .. . . ... ... 3.2-1 !
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| 3.2.2 Nuclear Enthalpy Rise Hot Channel I Factor (F%) ... . ... ..... .. .. 3.2-5 l 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) ... ... ... 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QPTR) ... . ... . . 3.2-10 3.2.5 OPDMS-Monitored Power Distribution Parameters . . . . . . . . . . . . .. . .. . . . ... 3.2-14 3.3 Instrumentation . . . . . .. ...... ... . .. . . .. .. 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation .. ..... 3.3-1 3.3.2 Engineered Safety Feature Actuation i System (ESFAS) Instrumentation ... ........ . 3.3-17 3.3.3 Post Accident Monitoring (PAM) Instrumentation . 3.3-45
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| <s s
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| 3.3.4 Remote Shutdown Workstation . . . . 3.3-48 v
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| Revision: 10
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| [ W85tingh0USS xxy December 20,1996
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| l Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age 3.4 Reactor Coolant System (RCS) . . . . ... . ........ . . 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . .. 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . 3.4-3 3.4.3 RCS Pressure and Temperature (P/F) Limits . .. 3.4-4 3.4.4 RCS Loops - Modes 1 and 2 . .. .... .... . 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . .. .... .. .. 3.4-7 3.4.6 Pressurizer . .. ...... ... . ..... . . 3.4-9 3.4.7 Pressurizer Safety Valves ..... . . . . .. 3.4-10 3.4.8 RCS Operational Leakage .. .. .... . . . . . 3.4-12 3.4.9 Minimum RCS Flow . . . ..... . .... . 3.4-14 3.4.10 RCS Leakage Detection Instrumentation . . . 3.4-15 3.4.11 RCS Specific Activity . . . . . .. .. ... .... . 3.4-18 3.4.12 Automatic Depressurization System (ADS) - Operating . 3.4-20 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Intact .. . ... . . ........ .. . 3.4-22 3.4.14 Automatic Depressurization System (ADS) - Shutdown, RCS Open . . . . . ..... . . . . 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . . . . . . . ... . . . . . 3.4-26 3.5 Passive Core Cooling System (PXS) .... . . . .. 3.5-1 3.5.1 Accumulators .. . .. . ... ... ... . .. 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating .... . .. .. 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating ... ........ . . . 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . . . . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST)-
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| Operating . ..... . ..... . . .... . . 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST)-
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| Shutdown. RCS Inventory High . .. ... . . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low . . . ... . 3.5-18 3.6 Containment Systems . .. ... .. ... . . . 3.6-1 3.6.1 Containment . . . . . . .. .. . . . . 3.6-1 3.6.2 Containment Air Locks ..... ..... ....... .. 3.6-3 3.6.3 Containment Isolation Valves ...... . .. 3.6-7 3.6.4 Containment Pressure . . . . ... . . 3.6-12 3.6.5 Containment Air Temperature . .. .. . . 3.6-1 't O
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| Revision: 10 December 20,1996 xxvi [ W85tingh0USe
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| Section Title _P_ age i l
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| 3.6.6 Passive Containment Cooling System (PCS)- Operation . 3.6-14 l 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . 3.6-17 3.6.8 Containment Penetrations ......... . . . . . . . 3.6-19 1 3.6.9 pH Adjustment . .. .. .. . .. . . . 3.6-22 I 3.7 Plant Systems . . . . . ... ...... ... . .. . .. . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . ... . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVsi . . ..... ...... 3.7-5 l 3.7.3 Main Feedwater Isolation and Contro'; Valves (MFIV and MFCV) . . . . . .... .... . .. .... 3.7-7 )
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| 3.7.4 Secondary Specific Activity . ..... .. ..... . . .. 3.7-9 )
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| 3.7.5 Spent Fuel Pool Water Level . . .. .. .. .... . . 3.7-10 l 3.7.6 Main Contrcl Room Habitability System (VES) ... .. 3.7-11 I 3.7.7 Startup Feedwater Isolation and Control Valves . ... 3.7-15 1 3.8 Electrical Power Systems ... ... .. . 3.8-1 3.8.1 DC Sources - Operating . . . . . . . . .. .. 3.8-1 3.8.2 DC Sources - Shutdown . ..... .. .. . .... .. 3.8 5 3.8.3 Inverters - Operating . .. . . .. .. .... 3.8-7 ,
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| 3.8.4 Inverters - Shutdown ..... ... ... ..... . 3.8-9 I
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| (~]
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| (s 3.8.5 Distribution Systems - Operating 3.8.6 Distribution Systems - Shutdown ...........
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| 3.8-11 3.8-13 3.8.7 Battery Cell Parameters . . .... . . . .. ... . 3.8-15 3.9 Refueling Operations . .... ...... . ... ...... 3.9-1 3.9.1 Boron Concentration . . ... .. . .. .. .. .. 3.9-1 3.9.2 Unborated Water Source Flow Paths . . . .. ... 3.9-2 3.9.3 Nuclear Instmmentation ..... . ....... .. 3.9-4 3.9.4 Refueling Cavity Water Level . . . . . . . .. .. . .. 3.9-6 4.0 Design Features . . . . . . . . . . ... .. ... . . . 4.0-1 ,
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| 4.1 Site . . . . . ... .. .. ... . . . ... ... 4.0-1 !
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| 4.1.1 Site and Exclusion Boundaries .... . .... 4.0-1 4.1.2 Iow Population Zone (LPZ) . . ... .. .. 4.0-1 4.2 Reactor Core ... .... .. . ... ...... . 4.0-1 4.2.1 Fuel Assemblies . .... .. .... ... 4.0-1 4.2.2 Control Rod and Gray Rod Assemblies .... 4.0-1 4.3 Fuel Storage . . . .. .... ..... . . . 4.0-2 4.3.1 Criticality . .. . .... . ... . .. . 4.0-2 4.3.2 Drainage .. ... . . . ... . . ... 4.0-2 4.3.3 Capacity . . ... . .. . .. 4.0-2 4.4 Hydrogen Control . ... . . . . . 4.0-3 4.4.1 Passive Autocatalytic Recombiners (PARS) . . 4.0-3 5.0 Administrative Controls .. . ... .. . . 5.0-1 5.1 Responsibility . ... . . .. . . .. . 5.0-1
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| ,m 5.2 Organization . . . . ... . .. . . . . 5.0-2 (v)
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| Revision: 10 3 W85tingh00S6 xxvii December 20,1996
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| j Master Table of Contents MASTER TABLF OF CONTENTS (Cont.)
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| Section Title Eage, a
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| 5.3 Unit Staff Qualifications . . . ... .. . . 5.0-5 5.4 Procedures . . . . . .. . . .. .. .. . .. . . 5.0-6 5.5 Programs and Manuals . . . . ... . . ... 5.0-7 5.6 Reporting Requirements . ... .. . . 5.0-15 B 2.0 Safety Limits (SLs) . . ....... ... .... . .. . B 2.0-1 B 2.1.1 Reactor Core Safety Limits (SLs) . . ... B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability . ..... B 3.0-1 B 3.0 Surveillance Requirement (SR) Applicability ........ . . . B 3.0-12 B 3.1 Reactivity Control Systems .... .... . . . . . . . . B 3.1 - 1 B 3.1.1 Shutdown Margin (SDM) . . . . . . . . . . . .. B 3.1-1 B 3.1.2 Core Reactivity . . .. . ........ . B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . . .... ... B 3.1-19 B 3.1.5 Shutdown Bank Insertion Limits . . . . . . . . . B 3.1-29 ,
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| B 3.1.6 Control Bank Insenion Limits . . .... B 3.1-34 B 3.1.7 Rod Position Indication . .. . . ... B 3.1-40 B 3.1.8 Physics Tests Exceptions - Mode 2 . . . . . . B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves . . . . . B 3.1-53 B 3.2 Power Distribution Limits .... ..... . .. . B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (Fq (Z))
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| (FqMethodology) ... .. .. . . B 3.2-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) .... . . .. . . .. . B 3.2-10 B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) ... B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . . B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters . . ......... .. . . B 3.2-28 B 3.3 Instrumentation ... .. . .. ... .. .. . . B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation . B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation ....... . . . . . B 3.3-53 I B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation . .. .. .. .. . . B 3.3-115 B 3.3.4 Remote Shutdown Workstation . .... . B 3.3-125 ,
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| B 3.4 Reactor Coolant System (RCS) . . .. . . B 3.4-1 :
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| B 3.4.1 RCS Pressure, Temperature, and Flow Departure I from Nucleate Boiling (DNB) Limits . . B 3.4-1 O
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| Resision: 10 December 20,1996 xxviii 3 Westirighouse
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| Master Tc ble of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title ,P,_ age B 3.4.2 RCS Minimum Temperature for Criticality . . B 3.4-6 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . B 3.4-9 i B 3.4.4 RCS Loops - Modes 1 and 2 . . . . . .. . . B 3.4-17 '
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| B 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . . . . .. B 3.4-21 B 3.4.6 Pressurizer . . . . ..... .. ... . . . B 3.4-25 B 3.4.7 Pressurizer Safety Valves . ... ... . . B 3.4-28 i B 3.4.8 RCS Operational Leakage . . ..... B 3.4-32 B 3.4.9 Minimum RCS Flow . .. ... . .. . B 3.4-38 B 3.4.10 RCS Leakage Detection Instrumentation . . B 3.4-41 B 3.4.11 RCS Specific Activity . . . . . .......... B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)-
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| Operating . . . . .... ...... ..... B 3.4-50 B 3.4.13 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Intact ... .... .... B 3.4-54 B 3.4.14 Automatic Depressurization System (ADS)-
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| Sl'utdown, RCS Open . . . . . ...... . . B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . ...... .. . B 3.4-60 A B 3.5 Passive Core Cooling System (PXS) . .. .... B 3.5-1 V B 3.5.1 Accumulators . .... . . .. . . . . . B 3.5- 1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . . . . B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . ........ . .... . B 3.5-15 !
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| B 3.5.4 Passive Residual Heat Removal Heat :
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| Exchanger (PRHR HX) - Operating .. . . B 3.5-18 ;
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| B 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . . . . B 3.5-24 j B 3.5.6 In-containment Refueling Water Storage i Tank (IRWST) - Operating .. . ... . B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory High . . B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low .. ... .. ... ....... B 3.5-38 B 3.6 Containment Systems . .. . . . . . . . B 3.6-1 B 3.6.1 Containment . .. ....... ...... .... B 3.6-1 B 3.6.2 Containment Air Locks . . . .. . . B 3.6-6 B 3.6.3 Containment Isolation Valves .. ... B 3.6-13 B 3.6.4 Containment Pressure ... .. .. . ... B 3.6-23 B 3.6.5 Containment Air Temperature . . B 3.6-26 B 3.6.6 Passive Containment Cooling System (PCS) - Operating . . .. B 3.6-30 b
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| Revision: 10 3 W85tingt100S6 xxix December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title h B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . ....... .. ..... B 3.6-37 B 3.6.8 Containment Penetrations . . . .. . ..... B 3.6-40 B 3.6.9 pH Adjustment . .......... . . . B 3.6-47 B 3.7 Plant Systems . . . . .. ... . ... . . . . . . . B 3.7- 1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) ..... B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) . ............ B 3.7-13 B 3.7.4 Secondary Specific Activity . ....... B 3.7-18 B 3.7.5 Spent Fuel Pool Water Level . . .. ... B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability System . . . ... ... .. .. . . . . . . . . B 3.7-24 B 3.7.7 Startup Feedwater Isolation and Control Valves B 3.7-30 B 3.8 Electrical Power Systems . .. ..... .. .. B 3.8-1 B 3.8.1 DC Sources - Operating . .. .... ... . B 3.8-1 B 3.8.2 DC Sources - Shutdown . . .. . .. .. B 3.8-11 B 3.8.3 Inverters - Operating . . . .. . .. . B 3.8-15 l B 3.8.4 Inverters - Shutdown . . . . . . ... . .. . B 3.8-20 B 3.8.5 Distribution Systems - Operating .. . .. B 3.8-24 B 3.8.6 Distribution Systems - Shutdown . .. . B 3.8.33 l B 3.8.7 Battery Cell Parameters . . . . . . . .. B 3.8-37 l B 3.9 Refueling Operations . . . . ....... . .. . B 3.9-1 l B 3.9.1 Boron Concentration ... .......... B 3.9-1 B 3.9.2 Unborated Water Source Flow Paths ... . B 3.9-5 B 3.9.3 Nuclear Instrumentation . . . .. . .... B 3.9-8 B 3.9.4 Refueling Cavity Water Level .. . ... B 3.9-11 Volume 11 i 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM . ... . . . 16.2-1 16.2.1 Introduction . . .. . .. . . .. ..... . . 16.2-1 16.2.2 Scope .. .... . ... .. . .. . . ...... . 16.2-1 16.2.3 Design Considerations . .. ... .. . . . .. ... 16.2-1 16.2.4 Relationship to Other Administrative Programs . .. ... . . . 16.2-2 16.2.5 The AP600 Design Organization . . . ..... 16.2-2 16.2.6 Objective . . ........ ...... .... . .. .. . . 16.2-3 16.2.7 D-RAP, Phase I .... . ... .. .... . 16.2-4 16.2.8 Combined License Activities - O-RAP . .... ... . . 16.2-9 16.2.9 Glossary of Terms .. . . . . . ....... 16.2-10 0
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| Revision: 10 December 20,1996 xxx T Westirighouse
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| Master Tchte of Contents j m
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| MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_agte 16.2.10 References . .. . . .... .. .. . .. . . 16.2-11 CHAPTER 17 QUALITY ASSURANCE ... .. .. .. ....... ... .... . 17.1-1 17.1 Quality Assurance During the Design and Construction Phases . ... . . 17.1 17.2 Quality Assurance During the Operations Phase . .. . .... . . . . 17.1 - 1 17.3 Quality Assurance During Design, Procurement, Fabrication, Inspection and/or Testing of Nuclear Power Plant Items and Services ....... .. . 17.1-1 17.4 Combined License Information Items ... . .. . .. ....... . . 17.1-2 17.5 References . . ....... ... ... .. .. . . ..... ... 17.1-2 CHAPTER 18 HUMAN FACTORS ENGINEERING . . . . .. . .... .. .... I8.1-1 18.1 Oveniew . . . ....... .... ... ..... . .... 18.1-1 18.1.1 References . . ...... .. .. .... ... . . . . .... 18.1-4 18.2 Human Factors Engineering Program Management .. . . ... 18.2-1 18.2.1 Human Factors Engineering Program Goals, Scope, Assumptions, and Constraints . . . ... . . ... ...... . I8.2-1 18.2.2 Human System Interfaces Design Team and Organization . .. 18.2-4 18.2.3 Human Factors Engineering Processes and Procedures . . . 18.2-11
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| : p. I8.2.4 Human Factors Engineering Issues Tracking . .. .... ..... I8.2-17 U 18.2.5 Human Factors Engineering Technical Programs and Milestones . . .......... .. . ..... .. .. 18.2.18 18.2.6 Combined License Information . .. ..... .. .. . . . 18.2-19 18.2.7 References ... ..... ... . . ...... .. .. . . 18.2-19 18.3 Operating Experience Review . . . . .. . .. 18.3-1 18.3.1 Combined License Information . . . . . .... ... . . I8.3-1 18.3.2 References . . . ..... ... . . .. ...... . 18.3-1 18.4 Functional Requirements Analysis and Allocation . . . . ... . 18.4-1 18.4.1 Combined License Information . ... .. . . . . 18.4-2 18.4.2 References .. ..... .... ... . . ... .. 18.4-2 18.5 AP600 Task Analysis Implementation Plan . .. . .. . 18.5-1 18.5.1 Task Analysis Scope ...... . . . ... .. . . .. 18.5-1 18.5.2 Task Analysis Implementation Plan ... . . ... . 18.5-2 18.5.3 Job Design Factors ... ... . . ... .. ... ... . 18.5-5 18.5.4 Combined License Information Item . . ... . . .... . I8.5-5 18.5.5 References . , . . .. . .. . . ... . . . 18.5-5 18.6 Staffing .. . . .. .......... . . . . . . . 18.6-1 18.6.1 Combined License Information Item . . . . . 18.6-1 18.6.2 References . ... .... . ..... . .. .. ... 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering 18.7-1 18.7.1 Combined License Information . . . . . ..... ..... 18.7-1 18.7.2 References . . .. . . . . .. . .. . . . . . . 18.7-1 l 18.8 Human System Interface Design . .... . . . . . . . 18.8-1
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| w l Revision: 10
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| [ W85tingh0USB xxxi December 20,1996
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| Master Tcble of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 18.8.1 Implementation Plan for the Human System Interface Design ..... 18.8-3 18.8.2 Safety Parameter Display System (SPDS) . . . ... .. I8.8-11 j 18.8.3 Operation and Control Centers . . . . . . ..... . ... . . .. I8.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Portion of the Plant . ... . .. ... . .. . . 18.8-20 18.8.5 Combined License Information . .. . .... . .... .... . I8.8-23 18.8.6 References . . . . .... . . . . . .. .... I8.8-23 18.9 Procedure Development ...... .. ...... ...... .. ..... . . I8.9-1 18.9.1 Combined License Information . . ........ . .... .. . 18.9-1 18.9.2 References . ...... ... .. .... . . .. . . .. I8.9-1 18.10 Training Program Development .. .... . . . . . .... ..... I8.10-1 18.10.1 Combined License Information . . .. ..... ..... 18.10-1 18.10.2 References .. . . . .. . . ... ... .. .. I8.10-1 18.11 Human System Interface Design Test Program . . . ... 18.11-1 18.11.1 Combined License Information . . . . . ... ....... 18.11-2 18.11.2 References . . .. . .. . .. .. . ... . 18.11-2 18.12 Displays, Alarms, and Controls ... .. . ... .. .. . .. . 18.12-1 18.12.1 Inventory of Displays, Alarms, and Controls . .... . . I8.12-1 18.12.2 Minimum Inventory of Main Control Room Fixed Displays, Alarms, and Controls . . . . . . ........ . ........... . 18.12-1 18.12.3 Remote Shutdown Workstation Displays. Alarms, and Controls . . . 18.12-7 18.12.4 Combined License Information . . ... .......... 18.12-7 18.12.5 References .... . . . . . . . 18.12-8 9
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| Resision: 10 December 20,1996 xxx;; [ W85tingh0LISO
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| Mastero Table s f Content O
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| Section MASTER TABLE OF Volume 1 CONTENTS v Title CHAPTER 1
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| ==1.1 INTRODUCTION==
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| Introduction AND 1.1.1 . Pajte 1.1.2 1.1.3 Plant Location GENERAL DESCRIPTI ON Containment T .
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| OFPLANT 1.1.4 Reactor Type .ype . . .
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| 1.1.5 Power Out .. . ....
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| 1.1-1 1.1.6 Schedule .put . . . . . .. .
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| 1.1-1 1.2 1.1.7 Format and Content
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| .. 1.1-1 1.1-1 General Plant DescriCombined License Info 1.2.1
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| . 1.1-1 1.2.2 ption . . . rmation . .. .
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| 1.1-1 1.2.3 Site DescriptionDesign .
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| Criteria, .....
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| ... . Oper i 1.1-1 1.2.4 1.1-2 NuclearIsland escription . Plant Arrangement D at ng Char 1.2.5 . 1.1-3 1.2.6 Annex Building . . .
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| , and Safety Considerations 1.2-1 1.2.7 . .. .
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| 1.2-1 1.2.8 Radw te BuildingDiesel as ng
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| .. Generator 1.2-15 Buildi 1.2-16 1.3 1.2.9 Turbine Building .
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| 1.2-17 ComparisonsCombined.... License Inf ... ..
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| 1.4 . . .
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| . 1.2-24 Identification 1.4.1 owith Agents fSimilar Facility Desiormation ..
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| 1.2-25 gns .
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| 1.2-26 1.4.2 ...
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| Other ContractorsApplicant . . -. .Program Mand Contracto 1.5 1.4.3 anager . ..... . . . . . .. . .
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| 1.2-26 1.2-27 Requirements for FurthCombined License InfandParticipants .
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| 1.3-1 1.5.1 ... ..
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| 1.5.2 ormation . .
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| 1.4-1 AP600 Component DAP600 Safety-Related Ter Tec 1.5.3 n .
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| 1.4-1 ests 1.6 1.5.4 Combined L .
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| .. 1.4-1 1.4-3 Material ReferencedReferences .icense Information .esign Tes 1
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| 1.7 .
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| \ Drawings 1.5-1
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| \ 1.7.1 .... . 1.5-1 1.5-7 Electrical and Instrumand Other Detailed Info
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| \ 1.7.2 . .. .
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| \ rmation 1.5-8 1.8 1.7.3 Piping andInstru ..
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| 1.5-8
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| \ 1.9 mentation Diagramsentation . .
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| and ControlD
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| \
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| \
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| Interfaces for Compliance with Reg lr Design ormation . .
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| 1.9.1 Standa dCombined rawings . . .
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| .. License Inf 1.6-1 1.7-1
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| \ a .
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| 1.7-1 1.9.2 Regulatory Guidesu tory Criteria .
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| 1.9.3 . . . 1. 7-1
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| \
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| Three Mile Island IssuCompliance With Sta d n
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| 1.7-1 1.8 1 es .
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| ard Review Plan . .
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| (NUREG 1.9-1 D . -0800) .
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| . 1.9-1
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| ) Westinghouse .
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| 1.9-3 1.9-3 Y' -7 y- /X
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| o Master Table f Contents t)
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| Pm MASTER TABLE OF CONTENTS (Con .
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| Title
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| . . . 1.9-28 Generic Safety Issues . . . . . . 1.9 . 1.9-74 107 Section ...... 1.9-108 Unresolved Safety Issues .....
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| andWater
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| ..... Reactor Certification 1.9.4 .....
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| . . . . 1 A-1 1.9.5 Advanced...LightCombined ...
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| License Information IA-79 ...
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| 1.9.6 . S .
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| References ...
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| 1B-1 1.9.7 WITH REGULATORY . ..
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| ATIVES . .
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| GUIDE ..
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| . . . . IB-1 CONFORMANCE . ...
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| . . . IB-1 APPENDIX 1 A References .
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| 1 A.1 GATION DESIGN ALTERN.
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| . . IB-2
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| . ... . . 1B-2 SEVERE..... ACCIDENT MITI 1B-2 APPENDIX IB Introduction ... ..
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| IB.I Summary
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| . . . . . . .1B-3 IB-3 o
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| Selection Methodologyf SAMDAS ..
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| IB.2 .. ...
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| . . IB-3 /
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| IB.3 1B.4 Risk Reduction ...
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| IB 4 1B.4.1 Capital Cost Estimates ... .
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| 1B 4 1B.4.2 CostBenefit Analysis. .. ... .. .... . . .. .
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| 1B-5 1B.4.3 .. 1B-5 PRA Release ReleaseCategories Category OK .........
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| 1B.5 1B.5.1 Release Category OKP ..... .
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| . . . . . . . IB-5 1B.5.2 Release Category CC... .... ..
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| . . . . .. .1B-6 1B-6 1B.5.3 Release Category ... .. CI . .. . .
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| IB 6 1B.5.4 ... ..
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| IB-7 fit . . . LOCAs .. .
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| 1B.6 1B.7 Total PopulationContainment .
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| Dose. . . . .SAMDA
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| . . . IB-7 Desc
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| . 1B 7 iB.7.1 FilteredVent .
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| IB-7 l tion Valves ..
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| IB.7.3 Locate Normal RHRInsideSelf-Actuat 1B.7.2 .... .
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| 1B-8 I jection System . . . ..
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| 1B-8 1B.7.4 Passive Containment Sprays . . .
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| 1B-8 1B.7.5 Active High Pressure HeatSafety Removal n ... Systemf .
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| IB-8Flow to IB.7.6 IB.7.7 Steam Generator d Ventilation Shell-SideDirect St 1B-9 1B-9 IB.7.8 Increased SteamValves Generator ..
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| 1B-9 1B.7.9 1B.7.10 Secondary Containment .
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| in
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| ..,. FiltereDive 1B-9
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| . IB-9 IB.7.11 Ex Vessel Core Containment Catcher .
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| IB-11 1B.7.12 High Pressure ..
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| Des g . Actuation .
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| iB.7.13 Increase Reliability of Diverse 1B.7.14 .
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| Results . . ....
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| 1B.8 References .
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| IB.9 W Westinghow ame 11 nm
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| l
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| :-- a ,
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| Master Table of Contents i
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| MASTER TABLE OF CONTENTS l
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| Section Title Page Volume 1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT .. . . 1.1-1 1.1 Introduction . . . . . . .. ... ... . . .... . . ... . . 1.1-1 1.1.1 Plant Location . . . . ..... .... . . ... .. . 1.1-1 (
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| l.1.2 Containment Type ...... .. .. . .... . . . 1.1-1 1.1.3 Reactor Type . . .. .. ..... . . . ........ . .. 1.1-1 l 1.1.4 Power Output . ...: ... ...... ... ..... .... . . 1.1-1 l 1.1.5 Schedule . . . . . . . . . ..... . . .. ....... . . . . 1.1-1 !
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| 1.1.6 Fermat and Content . ... . . ..... .... .. .... 1.1-2 i 1.1.7 Combined License lnformation . . . . .. 1.1-3 l
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| 1.2 General Plant Description . . . . . . . . . . . . . . ...... 1.2-1 1.2.1 Design Criteria, Operating Characteristics, and Safety Considerations . 1.2-1 !
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| 1.2.2 Site Description . . .......... . ..... .. .. . ... 1.2-15 l 1.2.3 Plant Arrangement Description .. . . ... . . . 1.2-16 l 1.2.4 Nuclear Island . . . . . . .. ... .. . 1.2-17 1.2.5 Annex Building . ....... ..
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| 1.2.6 Diesel Generator Building .
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| . ...... . . . 1.2-24 l g i
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| .. . . . ...... ......... 1.2-25 ;
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| : 1.2.7 Radwaste Building . . . . . . . .. . . ... ...... .... . 1.2-26 l 1.2.8 Turbine Building . . .. . ... ....... . .. 1.2-26 1.2.9 Combined License Information . . . . . . . .......... ...... . 1.2-27 1.3 Comparisons with Similar Facility Designs . ... . .. ... .. . 1.3-1 1.4 Identification of Agents and Contractors ..... . ..... .... ... 1.4-1 1.4.1 Applicant - Program Manager . .. ... . ... . 1.4-1 1.4.2 Other Contractors and Participants . .. . ........ 1.4-1 1.4.3 Combined License Information . .. . ........ . . 1.4-3 1.5 Requirements for Further Technical Information . . .. .... . . .... . 1.5-1 1.5.1 AP600 Safety-Related Tests . .. . ...... . . 1.5-1 1.5.2 AP600 Component Design Tests ... .. .. ... . . 1.5-7 1.5.3 Combined License Information . ... .... ...... . 1.5-8 1.5.4 References . . . . . ....... ... .. ....... . . 1.5-8 1.6 Material Referenced . . . ....... .. . . ........... .. . 1.6-1 1.7 Drawings and Other Detailed Information .. . . ... ... .. . . . 1.7-1 1.7.1 Electrical and Instrumentation and Control Drawings . . . .... . . 1.7-1 1.7.2 Piping and Instmmentation Diagrams . .. .. ...... . .. 1.7-1 1.7.3 Combined License Information . . . . .. .. . . 1.7-1 1.8 Interfaces for Standard Design . . ... . . . .. ..... .... . 1.8-1 1.9 Compliance with Regulatory Criteria ... .. . . . ... . 1.9-:
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| 1.9.1 Regulatory Guides . . . . . . . ... .... . . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG-0800) . . . 1.9-3 1.9.3 Three Mile Island Issues . . .. . . . . . 1 9-3 f)
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| G/
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| Revision: 10 W Westinghouse December 20,1996
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| - 1 Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 1.9.4 Unresolved Safety Issues and Generic Safety Issues . . ... ... . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues .. .. . . . . 1.9-74 I 1.9.6 Combined License Information . . . . . . . . . . . .. . . . . . . . 1.9-107 l 1.9.7 References . ....... .. ... .. ...... . ... . 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES . . . . . . . l A-1 1 A.1 References . .. .......... ... ... .. . .. ..... IA-79 APPENDIX 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES . . . . . . 1 B-1 IB.! Introduction . .. ..... .. .... ...... ...... 1B-1 IB.2 Summary . .... ... .. .... ..... . . . . ... . . 1B-1 IB.3 Selection of SAMDAS . . . . . . .......... ... .. . . . . IB-2 IB.4 Methodology . . . ... .. . .. . ...... .. . .. .. . IB-2 IB.4.1 Risk Reduction .. .. . . . .. .... . . . IB-2 i 1B.4.2 Capital Cost Estimates ... ... . .... . . . . 1 B-3 1B.4.3 Cost Benefit Analysis . . ... .. . . . . .... . . IB-3 IB.5 PRA Release Categories . . .... .. . .. . . . ..... .... IB-3 IB.5.1 Release Category OK . . . . . .. . .. . . 1 B-4 ,
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| 1B.5.2 Release Category OKP . . . . . ... . .. .... 1B-4 1B.5.3 Release Category CC . . . ..... . .. ... . 1B-5 IB.5.4 Release Category CI . ... . . .. .. . . . . . . I B-5 IB.6 Total Population Dose . . . . . . ....... . . ...... ... . . . . . . I B-5 1B.7 SAMDA Description and Benefit . . . . .... ... .. .. 1B-6 1B.7.1 Upgrade the CVCS for Small LOCAs . . . .. .. .... 1B-6 1B.7.2 Filtered Vent . . ..... .. ..... .... . .... . 1B-6 1B.7.3 Locate Normal RHR Inside Containment .. .. . ... .. IB-7 IB.7.4 Self-Actuating Containment Isolation Valves . . . . . . .... IB-7 1B.7.5 Passive Containment Sprays . .... .. . . . 1 B-7 IB.7.6 Active High Pressure Safety Injection System . .. . . . . I B-7 IB.7.7 Steam Generator Shell-Side Heat Removal System . . . . 1B-8 IB.7.8 Direct Steam Generator Relief Flow to the IRWST . .. . . IB-8 1B.7.9 Increased Steam Generator Pressure Capability .. .. . .. 1B-8 1B.7.10 Secondary Containment Filtered Ventilation . .... ..... 1B-8 I B.7.11 Diversify the IRWST Discharge Valves . . . . IB-9 1B.7.12 Ex-Vessel Core Catcher . . .. .. .. . .. .. . 1B-9 1B.7.13 High Pressure Containment Design . ..... . . . 1B-9 IB.7.14 Increase Reliability of Diverse Actuation System . .. . . . 1 B-9 IB.8 Results . . . .... . ... .. . . . . .. . . . IB-9 IB.9 References .. ........ . . . . .. . . . . IB-ll O
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| Revision: 10 December 20,1996 ii 3 W85tingt10Use
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| 1 u-Master Table of Contents y
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| o U MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page CHAPTER 2 SITE CHARACTERISTICS .. ... ... ...... ... ... ...... 2-1 2.1 Geography and Demography . . . . . . .. .. .. . . 2-1 l 2.1.1 Combined License Information for Geography and Demography . . . 2-1 2.2 Nearby Industrial, Transportation, and Military Facilities ... . . 2-1 1 2.2.1 Combined License Information for Identification of Site-specific Potential Hazards ... ... .. .. . .. . .. .. .. 2-2 2.3 Meteorology . ... . . .... .. .. .. .. ... .. 2-2 2.3.1 Regional Climatology . . .. . . ... . ..... .. . 2-3 ;
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| 2.3.2 Local Meteorology . .. . ... .. . . . 2-3 i 2.3.3 Onsite Meteorological Measurement Programs . . . . . 2-3 2.3.4 Short-Term Diffusion Estimates . . . ... ... ... . .. .. 2-3 2.3.5 Long-Term Diffusion Estimates . . .. .... . .. . 2-4 l 2.3.6 Combined Licensed Information . .. .. . .. ..... . . 2-4 l 2.4 Hydrologic Engineering . .. . . . . ... . . .. ... . . 2-5 I 2.4.1 Combined License Information ... . . .. .. . .... 2-5 2.5 Geology, Seismology, and Geotechnical Engineering . ...... ..... .. 2-6 l 2.5.1 Basic Geological and Seismic Combined License Information . . 2-6 I 2.5.2 Vibratory Ground Motion . . . . . ..... ..... . . . .. 2-7 )
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| 2.5.3 Surface Faulting Combined License Information . . .. ... . 2-7
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| ()N
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| ( 2.5.4 Stability of Subsurface Materials and Foundations . . ... 2-8 2.5.5 Combined License Information for Stability of Slopes ... . 2-12 2.5.6 Combined License Information for Embankments and Dams . 2-13 2.5.7 References ... ..... .. . .... 2-13 APPENDIX 2A DESIGN SOIL PROFILES ....... . . . ... .... . . 2A-1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. . . 2A-1 2A.2 Generic Soil Profiles . ... . ........ . . . .. . . 2A-2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . .. . 2A-4 2A.4 Free-Field Site Response Analysis . . . . . . . . . .. . 2A-5 2A.5 2D Soil-Stmeture Interaction Analysis . . . ... .. . 2A-7 2A.6 AP600 Design Soil Profiles .. ... 2A-12 2A.7 References . .. . .... ... . . ... . .. . . 2A-14 1
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| APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL PROFILES . . . .... . .... .. . . . . . 2B-1 2B.1 2D SSI Analysis Parameters and Procedures . . . . 2B-2 2B.l .1 Structural Models . . . . . . . . 2B-2 1 2B.I .2 SASSI Foundation Models .. ... ... .. . 2B-2 l 2B. I .3 Soil Properties for SSI Analysis . .. .... . . . 2B-2 l 2B.I .4 Input Motion . . . . . . .. . . . . . 2B-3 j 2B.I .5 Two-Dimensional Enveloped SSI Results . .. . . 2B-3 ,
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| 2D;2 Design Soil Profiles 2B-3 g . . . . l b
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| Revision: 10
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| [ Westinghouse jii December 20,1996
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| F-?
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| n- Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page I l
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| 1 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . . . . . . . 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) ..... .. .... .. . . 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . . . 2B-5 2B.2.4 Variation of Soil Properties and 60 Percent Requirement of Free-Field Spectra at Foundation Level . ...... . . 2B-5 2B.2.5 AP600 Design Soil Profiles . ..... . .. . . .. . . 2B-6 2B.3 Soil Profile Parametric Studies: ... .. .. .... ..... . .. . 2B-6 2B.3.1 Depth-to-Base Rock . . . . . . . .. .... ... . . ... . 2B-7 2B.3.2 Soil Curves for Clay Material . . . . ... ..... . ...... . 2B-7 ,
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| 2B.3.3 Poisson's Ratio for Soil above Water Table ........ ..... . 2B-8 !
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| 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site ... . . . 2B-8 ;
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| 2B.3.5 Idriss 1990 Soil Curves . . . . ... .. ... .. . . . . . 2B-9 l 2B.3.5 Soil Densitys ...... . . .... ... ... .. . . . 2B-9 i 2B.4 References . .. .. ... . . .. . . ..... . ... . . 2B-9A Volume 2 APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES . .
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| 2C.1 2D SASSI Analysis for Seismic Lateral Earth Pressure 2C.I .1 Analysis Method ...... .. .
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| . 2C-1 2C- 1 2C-1 G'
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| 2C.I .2 Structural Models . . . . . . . ....... ...... ... . 2C-1 2C. I .3 SASSI Foundation Models ... .... . .. . .. . . 2C-1 2C.I .4 Representation of Adjacent Structures .. .. . .... .. . . 2C-2 2C.I.5 Input Motion . . . . . . . .. . ... . .... .. . 2C-2 2C.I .6 Soil Properties . . . . . .... . . .. ...... .... . 2C-2 2C.I .7 2D SASSI Analyses Results .. ..... . . ... . . .. 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island .... . 2C-2 2C.3 Local Distribution of Lateral Earth Pressure . .... ... .... . 2C-3 2C.4 References . .... ... .... .. ..... . . . . . 2C-4 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT.
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| AND SYSTEMS ............ .. . ...... .. . . 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria 3.1-1 3.1.1 Overall Requirements . . ... . . ... . 3.1-1 3.1.2 Protection by Multiple Fission Product Barriers .. .. . 3.1-4 3.1.3 Protection and Reactivity Control Systems . . . . 3.1-12 3.1.4 Fluid Systems ..... .. ... . ... . . 3.1-18 3.1.5 Reactor Containment . .... ... .... . . 3.1-30 3.1.6 Fuel and Reactivity Control . . . . ... . 3.1-34 3.1.7 Combined License Information .. . . ... ... 3.1-37 3.1.8 References ... . . . . . .. .. . . . 3.1-37 Revision: 10 December 20,1996 iv [ Westillghouse
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| Master Table of Contents
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| (~)
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| V MASTER TABLE OF CONTENTS (Cont.)
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| 1 Section Title P_ age, 3.2 Classification of Structures, Components, and Systems .... . ... .. . 3.2-1 .
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| 3.2.1 Seismic Classification ....... ...... . .. ... 3.2-1 3.2.2 l
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| AP600 Classification System . . . . . . . . . .... .... .. ... 3.2-3 3.2.3 Inspection Requirements ...... . . ...... . . . 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System . . .......... ........ . . 3.2-13 3.2.5 Combined License Information . .. . . . . ... . 3.2-16 3.2.6 References . . ... .. .. . .... ... ... . 3.2-17 3.3 Wind and Tornado Loadings . ........ . . ... . .. .. .. .. 3.3-1 I 3.3.1 Wind Loadings . . . . . . . . . . . . . . . . .. .. ... . ... . 3.3-1 3.3.2 Tornado Loadings . . ..... . .. ... .. ... . . . .. ... 3.3-2 3.3.3 Combined License Information .... ........ .. . . . 3.3-4 ;
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| 3.3.4 References . . .. . ..... . ... .. . ... .. 3.3-4 3.4 Water Level (Flood) Design .. . .. . . .. .......... . . 3.4-1 3.4.1 Flood Protection .. . . ... ... . .. . 3.4-1 3.4.2 Analytical and Test Procedures ...... . . . . . . 3.4-24 3.4.3 Combined License Information .. . . . . .. . . 3.4-24 3.4.4 References . . . . . . . .. . .. . . . ........... 3.4-24 1 3.5 Missile Protection . . ... . ... ....... . . ... .. . 3.5-1
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| {
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| 3.5.1 Missile Selection and Description . .... . .. . . .... . 3.5-4
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| (\s) 3.5.2 Protection from Externally Generated Missiles . . . . . . . .. .
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| 3.5-13 3.5.3 Barrier Design Procedures . . . . . . .. ........ . . . 3.5-13 3.5.4 Combined License Information ......... .......... . . 3.5-16 3.5.5 References . . ...... ....... . . . .... . . . . 3.5-16 3.6 Protection Against the Dynamic Effects Associated with the l Postulated Rupture of Piping . . . ... ...... ... . . ..... . 3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment ...... .. ..... . . .... ...... ... 3.6-2 3.6.2 Determination of Break Location: and Dynamic Effects Associated with the Postulated Ruptare of Piping . . .. ... . 3.6-12 3.6.3 Leak-before-Break Evaluation Proced: res .... .. . 3.6-31 3.6.4 Combined License Information . . .......... .. 3.6-38 3.6.5 References . . .. .. .. ... .. . .... ...... . 3.6-38 3.7 Seismic Design ........... ... . ........ .. . ... 3.7-1 3.7.1 Seismic Input . . ..... . . .. .... .. .. . . 3.7-1 3.7.2 Seismic System Analysis .. . . . ... . .... 3.7-6 3.7.3 Seismic Subsystem Analysis . . . . . .. . ..... . . 3.7-20 3.7.4 Seismic Instrumentation ..... .. .. . .. . . . . 3.7-46 3.7.5 Combined License Information . . . ..... .. 3.7-48 3.7.6 References . ... . .... . .. . .. . . 3.7-49 3.8 Design of Category I Structures ... .. .. .. .... 3.8-1 3.8.1 Concrete Containment ....... . . .. . . 3.8-1 3.8.2 Steel Containment .. .. . .... .. . . 3.8-1 o
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| Revision: 10
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| [ W85tingh00S8 y December 20,1996
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| m-Master Table of Contents l
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| l MASTER TABLE OF CONTENTS (Cont.) ei l
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| Section Title Page l
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| l l
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| 1 3.8.3 Concrete and SteelInternal Structures of Steel Containment . 3.8-16 3.8.4 Other Category I Structures . ... ....... .. . 3.8-39 3.8.5 Foundations . ... . . . . ..... .. . 3.8-53 3.8.6 Combined License Information ... .... . . . ... 3.8-60 3.8.7 References . . . . . .. . . .. . ..... ... . . 3.8-60 Volume 3 3.9 Mechanical Systems and Components . . .. ........ .. . ... 3.9-1 l 3.9.1 Special Topics for Mechanical Components . . . . . . . .. . ... 3.9-1 !
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| 3.9.2 Dynamic Testing and Analysis . . ...... . ...... . 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Components, Component l Supports, and Core Support Structures . .. .... . . 3.9-45 3.9.4 Control Rod Drive System (CRDS) .. . .. . 3.9-71 3.9.5 Reactor Pressure Vessel Intemals . . .. ... . 3.9-82 !
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| 3.9.6 Inservice Testing of Pumps and Valves ... .. .. . 3.9-89 3.9.7 Integrated Head Package . .. . . .. . . . 3.9-97 3.9.8 Combined License Information .. . ... ..... . 3.9-102 j 3.9.9 References
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| .. .. .. . .... .... ...... . 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and l Electrical Equipment . . . . ........ . ..... ...... ... . 3.10-1 1 3.10.1 Seismic and Dynamic Qualification Criteria ... . . .. . . . . 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment,
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| , Instrumentation, and Mechanical Components . . . . .. . . . 3.10-3 l 3.10.3 Method and Procedures for Qualifying Supports of Electrical Equipment, Instrumentation, and Mechanical Components . .. . 3.10-7 3.10.4 Documentation .. .... .. .. .......... . .. . 3.10-7 3.10.5 Standard Review Plan Evaluation . . ..... .... .. . 3.10-7 l 3.10.6 Combined License Information Item on Experienced-Based Qualification ... . .... . . 3.10-8 3.10.7 References ... ...... . . . . . . .. . .. 3.10-8 3.11 Environmental Qualification of Mechanical and Electrical Equip' ment . 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . . 3.11-1 3.11.2 Qualification Tests and Analysis . . . . .. . 3.11-3 3.11.3 Loss of Ventilation . . . . . . . . . .. 3.11-4 3.11.4 Estimated Radiation and Chemical Environment .. ..... .. 3.11-5 3.11.5 Combined License Information Item for Equipment Qualification File . . . . . ... .. .. . . .. ... . 3.11-5 3.11.6 References . . . . ..... . . . . .... . 3.11-6 l
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| 9 Revision: 10 December 20,1996 vi [ W85tingh0USB
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| Master Tchla of Contents f
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| n C'% MASTER TABLE OF CONTENTS (Cont.) i l
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| l Section Title Pm APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS . . . .. .. . .. . 3A-1 ;
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| 3A.1 Codes and Standards . .. .. . .. ... ........... . . .. . 3A-1 3A.2 Loads and Load Combinations ... . .. . ... .... ..... . 3A-1
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| , 3A.2.1 Loads ....... ..... ........ . ... . . . ..... 3A-1 3A.2.2 Load Combinations .. .... . . . .. . . ... . . . 3 A-3 3A.3 Analysis and Design . . . . . . . . . . .. .... . . . .. . . 3A-3 3 A.3.1 Response Due to Seismic Loads . . . . . . .. 3A-3 3A.3.2 Deflection Criteria . . . .... . .. .. ... .... 3A-3 3A.3.3 Relative Movement . . . . .. . . .. . . ... . . . 3A-3 3A.3.4 Allowable Stresses . ..... .. . .... .. .. . . . . . . 3 A-4 3A.3.5 Connections .... .. . . ... .... ... . . .. . . 3A-4 APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . . . . . 3B-1 3B.1 Leak-Before-Break Criteria for AP600 Piping . . . .. . .. . ...... . 3B-2 1 3B.2 Potential Failure Mechanisms for AP600 Piping . . . . . ... .. ......... 3B-2 3B.2.1 Erosion-Corrosion Induced Wall Thinning . . ........ 3B-2 3B.2.2 Stress Corrosion Cracking . . . ... . .... .... 3B-3 3B.2.3 Water Hammer .. ... .... . . . .. . . . . . . . 3B-5
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| ,. 3B.2.4 Fatigue . ..... ... . .. . . .. .. .... 3B-9
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| ( ) 3B.2.5 Thermal Aging . . ... .. .... .... . . 3B-9 V 3B.2.6 Thermal Stratification . . .. . . . .. . .... 3B-10 3B.2.7 Other Mechanisms . . . . . . . . . . . . ... .. . . 3B-13 l 3B.3 Leak-Before-Break Bounding Analysis .. . ... ... .... . .. 3B-13 1 3B.3.1 Procedure for Stainless Steel Piping . . . . . . . .. .. .... . . 3B-13 3B.3.2 Procedure for Non-Stainless Steel Piping . . . . . ... 3B-16 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . . 3B-17 3B.3.4 Bounding Analysis Results ... .. . . .... ...... . 3B-21 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe . . . . .... ... . .. . ... .. . . .. 3B-21 3B.5 Differences in Inspection Criteria for Class 1,2, and 3 Systems . . . . . . . . 3 B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping . .. . .. ...... . .. . . . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Emds in the Feedwater Lines . . 3B-21 A 3B.8 Augmented In-Service Inspection o' .nt Main Feedwater Nozzles Connected to the Steam Generato-- . . . .... ... .. 3B-21 A 3B.9 References .... ... ... . .. . . . 3B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS .. . . .. 3C-1 3C.1 Reactor Coolant Loop Model Description . .. .. ...... ... . . 3C-1 3C.l .1 Steam Generator Model . . . .... . . .. . . 3C-1 3C.I .2 Reactor Coolant Pump Model .. . . ... . . .. . 3C-2 3C.1.3 Reactor Pressure Vessel Model .. . . . . . . 3C-2
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| .f '
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| Revision: 10 3 Westingh0tise vii December 20,1996
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| E=-p Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age 3C.I .4 Containment Interior Building Structure Model .. .. . ... . 3C-3 3C.I.5 Reactor Coolant Loop Piping Model . . . . ........ . .. . 3C-3 3C.2 Design Requirements .. . . . . .. .... . . . . .... 3C-3 3C.3 Static Analyses . . . .... .. . . .. . .. ...... .. . 3C-4 3C.3.1 Deadweight Analysis . . .. ..... .. ........ . . . . 3C-4 3C.3.2 Internal Pressure Analysis . . . . ... . ...... .. . . 3C-4 3C.3.3 Thermal Expansion Analysis . .... . .... . ... ..... 3C-4 ;
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| 3C.4 Seismic Analyses . ........ .. .. 3C-4 l
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| 3C.5 Reactor Coolant Loop Piping Stresses ... . . . .. ......... 3C-5 3C.6 Description of Computer Programs . . . . . . . . .... .... ... 3C-5 ;
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| APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT .... . . ..... 3D-1 3D.1 Purpose .. . .. .. . .. . .... . . . . ..... . .. . 3D-2 3D.2 Scope. ...... . . . .. . ... ..... .... 3D-2 3D.3 Introduction . . . . .. .. ..... .. . .. . . .. . . .. 3D-3 1 3D.4 Qualification Criteria . . . . . .... 3D-3 l
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| 3D.4.1 Qualification Guides . ... .. . . . .... . 3D-3 3 D.4.2 Definitions ... ... . .. ....... ... . 3D-7 3D.4.3 Mild versus Harsh Environments . ...... . . ... . .... 3D-7 l 3D.4.4 Test Sequence . . ..... . .. . ........ . . 3D-8 j 3D.4.5 Aging .. .. . . ... .. . .. . .. . .. . 3D-9 l 3D.4.6 Operability Time . ... . . . . .. .... . 3D-12 !
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| 3D.4.7 Performance Criterion . . . .... . 3D-12 3D.4.8 Margin . . ... . . . .. . ..... . 3D-12 3D.4.9 Treatment of Failures . . . .. .. .... . 3D-15 3D.4.10 Traceability ..... ... ... . . ... .... . 3D-16 3D.5 Design Specifications . . . . . ... . . . 3D-17 3D.5.1 Normal Operating Conditions . . .. . . .. .. 3D-18 3D.5.2 Abnormal Operating Conditions . . . . . .. 3D-19 3D.5.3 Seismic Events . . . ..... . . ... . . . 3D-20 3D.5.4 Containment Test Environment .. . . .. . . . . 3D-20 3D.5.5 Design Basis Event Conditions . . .. ... . .. . . ... 3D-20 3D.6 Qualification Methods ......... . .. . ....... .. . . 3D-24 3D.6.1 Type Test . .... ..... ... .......... 3D-25 3D.6.2 Analysis . . ... . . ...... . .. .. . . .. 3D-25 3D.6.3 Operating Experience .. . . .. . 3D-30 3D.6.4 On-Going Qualification . . . . . . .. . .. . . 3D-30 3D.6.5 Combinations of Methods . .. . . . . . 3D-30 0
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| Revision: 10 December 20,1996 viii WB5tingh0USS
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| w Master Tabli of Contents p
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| g
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| \ i V'
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| MASTER TABLE OF CONTENTS (Cont.)
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| t'ection Title Page a
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| 3D.7 Documentation . . . . . . . . . . . . . . .... ... . . . .. .. . .. . . 3D-31 3D.7.1 Equipment Qualification Data Package . . .. .. ... . 3D-32 3D.7.2 Specifications .. ........ . . ... .. . . .. . . 3D-32 3D.7.3 Qualification Program . . .. ... ...... . . ... . . 3D-34 3D.7.4 Qualification by Test . . . .... . . ..... 3D-34 3D.7.5 Qualification by Analysis ... . ...... .. . .. 'L37 3D.7.6 Qualification by Experience . .. ..... ... . ... . 2 37 3D.7.7 Qualification Program Conclusions . . .... .. .... . . . 3D-37 3D.7.8 Combined License Information . . . .. .... . . .. .. . 3D-38 3D.8 References .... .. .. .. .... ... .. .. .. .. . ... . 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package .. .. . . 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program . . ... ... .. . . . 3D-87 B.1 Introduction . . .. ... . .. .. . . . . 3D-87 B.2 Objectives . . ........ . . . . .... . . . . 3D-87 B.3 Basic Approach .. .. ... . . ... .. . . . . . 3D-87 B.4 Subprogram A ..... .. ..... .. . . . . . . . 3D-88
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| /^\ B.4.1 Scope . .. .... ... ... .. . . .. .. . .. . 3D-88 V B.4.2 Aging Mechanisms . . .. . . . ........ . 3D-88 B.4.3 Time . . .. . .. .. . . . . .. .. . . .. ... 3D-88 B.4.4 Operational Stresses . . . . .. . .......... .... . . 3D-89 B.4.5 External Stresses . .. ..... .. .. . ...... ... . 3D-89 B.4.6 Synergism . . . . . . .... .. ........ . . . 3D-91 B.4.7 Design Basis Event Testing . . . .. .. .. .. . . 3D-91 B.4.8 Aging Sequence .. .. . . . . . . .... .. . 3D-91 B.4.9 Performance Criterion . . .. . . . . .. 3D-91 B.4.10 Failure Treatment . . . . . . . . .. ......... . 3D-91 B.5 Subprogram B .. . . . .. . . . .. . . 3D-92 B.5.1 Scope . ... .... . . . ... ... . . . 3D-93 B.5.2 Performance Criteria . . . . . . . 3D-93 B.5.3 Failure Treatment . . . .. . . . . . ... . . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials ... . 3D-96 C.1 Introduction . .. .... ... .. . ... . . .. ... . . 3D-96 C.2 Scope. .. . .. . ... ... . . .. . . .. . . . 3D-97 C.3 Discussion . .. . .... .... . .. . . . 3D-97 l C.4 Conclusions .. . ... . .. . . . 3D-98 C.5 References . , . . . 3D-98 L./
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| Revision: 10 l 3 WB5tiligh00SO ix December 20,1996
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| -E Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| i Section Title Pm i
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| Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . . ... . . 3D-103 D.1 Introduction ...... . . ... ...... .. .. .. .. . . 3D-103 D.2 Arrhenius Model .. ..... ....... .. ...... ... . . . 3D-103 D.3 Activation Energy . ..... .... .. .. . . ... .... . 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) .. ... . 3D-106 D.4.1 Normal Operation Temperature .. . ... .. .... . 3D-1%
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| D.4.2 Accelerated Aging Temperature .. . .. ... . 3D-107 D.4.3 Examples of Arrhenius Calculations . . ... ..... . . 3D-107 D.5 Post-Accident Thermal Aging . . ....... . .. . .... . . 3D-108 D.5.1 Post-Accident Operating Temperatures . . ... ..... . .. . 3D-108 D.5.2 Accelerated Thermal Aging Parameters for Post. Accident Conditions ... ... .. ........ .. .. ..... ..... . 3D-109 D.6 References ... ........ . . . .. ... . . ...... .. . 3D-109 Appendix 3D-Attachment E - Seismic Qualification Techniques .. . .. . . 3D-115 E.1 Purpose . ..... ...... . . .. . . . .. ...... 3D-Il5 E.2 Definitions .... . .... .. ... . . ..... . . . . 3D-115 E.2.1 1/2 Safe Shutdown Earthquake . . . . .. ... .. . 3D-115 E.2.2 Seismic Category I Equipment . . .. .. . . ... . . 3D-115 E.2.3 Active Equipment . . . .... .. . .. ..... . . 3D-115 E.2.4 Passive Equipment .. .. .. .. .. . . .. . . . 3D-115 E.3 Qualification Methods ..... ..... ..... . .... .. .. . 3D-116 E.3.1 Use of Qualification by Testing .. . . ... .... . . . 3D-Il6 E.3.2 Use of Qualification by Analysis . . . .. .. . . .. 3D-116 E.4 Requirements . . . . . . ..... .. .. . ... . . . . . . 3D-117 E.4.1 Damping . . . ...... . .... . . ........ 3D-Il7 E.4.2 Interface Requirements . ... . . . .. . ... . 3D-117 i E.4.3 Mounting Simulation . . ..... . .. . . .... . . 3D-118 E.4.4 1/2 Safe Shutdown Earthquake . .. 3D-Il8 E.4.5 Safe Shutdown Earthquake . .. . .. . . ... 3D-118 E.4.6 Other Dynamic Loads . . ....... .. . . . .... . 3D-Il8 E.5 Qualification by Test . . . . ....... . ...... . .. 3D-Il8 E.5.1 Qualification of Hard-Mounted Equipment . . . .. . . 3D-119 l E.5.2 Qualification of Line-Mounted Equipment .. . .. . . 3D-120 E.5.3 Operational Conditions . . .. . ... . . .. ... 3D-122 E.5.4 Resonant Search Testing . . . . . . ...... 3D-123 ,
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| E.6 Qualification by Analysis . . . . . . . .. . ... ... .. .. . 3D-123 !
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| E.6.1 Modeling ....... . . . . . .. .. .. . 3D-124 E.6.2 Qualification by Static Analysis . . . .. 3D-124 E.6.3 Qualification by Dynamic Analysis . ... .. . .. . 3D-124 O
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| Revision: 10 December 20,1996 x 3 Westiligh00S8
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| Master Tcble of Contents (yV)
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| MASTER TABLE OF CONTENTS (Cont.)
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| Section Title a P_agte E.7 Performance Criteria . . . ... .. . . ..... . . 3D-126 E.7.1 Equipment Qualification by Test . .. . . . ...... ... . 3D-126 E.7.2 Equipment Qualification by Analysis . ....... . . . . . 3D-126 APPENDIX 3'E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND .. . . 3E-1 APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS .. .. . . . . 3F-1 3F.1 Codes and Standards . ... ... . ... .... . . ... . . 3F-1 3F.2 Loads and Load Combinations . . . ... ... ....... .... 3F-1 3F.2.1 Loads ... . ...... ... .. . .. .. . . . 3F-1 3F.2.2 Load Combinations ...... .... .. .. . . .... . 3F-2 3F.3 Analysis and Design . ... ..... .. ..... . ... .... ... 3F-2 3F.3.1 Damping . ..... . . . . . . ... . . 3F-2 3F.3.2 Seismic Analysis . .. . . . . .. . . . .... 3F-3 3F.3.3 Allowable Stresses . .. .... .. . . . . . . 3F-3 3F.3.4 Connections . . ... ... . . . . . ...... ... . 3F-3 CHAITER 4 REACTOR ..... . ... . .. . . . . ... . . 4.1-1
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| (~~S 4.1 Summary Description .. . . . .... .. .. .. . . 4.1-1
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| () 4.1.1 Combined License Information . . . . ... .. . 4.1-4 4.1.2 References ... .. .. .... .. . . . . 4.1-4 4.2 Fuel System Design .. . . ... .. . . . . ... 4.2-1 4.2.1 Design Basis . . .. .. . .. .... . . . . 4.2-2 4.2.2 Description and Design Drawings . .. . .. ..... . . . 4.2-9 4.2.3 Design Evaluation . . . . .. . . .. ... . 4.2-20 4.2.4 Testing and Inspection Plan . . ... . . ... .. . 4.2-32 4.2.5 Combined License Information . . . . . ... .. . .. 4.2-37 4.2.6 References . ... . .... . . . . 4.2-37 4.3 Nuclear Design . . . . .. . . . . . . 4.3-1 4.3.2 Description . .. ... ... . . . 4.3-7 4.3.3 Analytical Methods .. . . .. ... . ... 4.3-39 4.3.4 Combined License Information . . . . . . .. . . 4.3-42 4.3.5 References . . .. ... .. . . . . .. 4.3-42 4.4 Thermal and Hydraulic Design . . . .... . .. . ... . . .. 4.4-1 4.4.1 Design Basis . .... . .. . . .. . 4.4-1 4.4.2 Description of Thermal and Hydraulic Design of the Reactor Core . 4.4-4 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System .. ..... . . . .. . 4.4-201 4.4.4 Evaluation ... . . . . . . .... . . 4.4-21 4.43 Testing and Verification ... . . . . 4.4-30 4.4.6 Instrumentation Requirements . . 4.4-31 4.4.7 Combined License Information . . .. . 4.4-35
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| U Revision: 10
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| [ Westirigh01.tSe xi December 20,1996
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| 1 l
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| a w- Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) G!1 Section Title Page.
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| l 4.4.8 References . . . . . .. ....... ..... .... ... .. . . 4.4-35 4.5 Reactor Materials . . . . . . . . . . .... .. .... .. ........ ... 4.5-1 4.5.1 Control Rod and Drive System Structural Materials . . .... 4.5-1 4.5.2 Reactor Intemal and Core Support Materials . . ... .. .. . 4.5-3 4.5.3 Combined License Information . . . . . . ... . ... . 4.5-4 4.5.4 References ..... . . .. .. .... . .. .... .. .. . 4.5-4 4.6 Functional Design of Reactivity Control Systems .... ... ..... .. 4.6-1 4.6.1 Information for Control Rod Drive System ......... ... . 4.6-1 4.6.2 Evaluations of the Control Rod Drive System . ... ....... . 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System . . . . . . . 4.6-2 4.6.4 Information for Combined Performance of Reactivity Systems . ... 4.6-2 4.6.5 Evaluation of Combined Performance . . ... . ... . ... . 4.6-3 4.6.6 Combined License Information . . . . . . . .. .. ... 4.6-4 Volume 4 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS . . .. .. 5.1-1 5.1 Summary Description . . ...... .. .. . . . .. .. . 5.1-1 5.1.1 Design Bases . .... . .. . .. . ... . . 5.1-1 5.1.2 Design Description . . . .... .... ... .. .. .... . 5.1-2 5.1.3 System Components . . . . . . ... ... . . .. .... 5.1-4 5.1.4 System Performance Characteristics . ... . . . . .. 5.1-7 5.1.5 Combined License Information . . .. .. . . . ... 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary . . ... .. .. 5.2-1 :
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| 5.2.1 Compliance with Codes and Code Cases . . . . . . . . 5.2-1 5.2.2 Overpressure Protection . . . .. .. . . . . 5.2-2 ;
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| 5.2.3 Reactor Coolant Pressure Boundary Materials . ......... .. 5.2-7 l 5.2.4 Inservice Inspection and Testing of Class 1 Components . . ... .. 5.2-17 i 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary . 5.2-20 I 5.2.6 Combined License Information items . .. .. ... . .. 5.2-29 5.2.7 References ..... .. .. . . ... .... . 5.2-29 5.3 Reactor Vessel . ... ....... . . .. ... ........ . .. 5.3-1 5.3.1 Reactor Vessel Design ... .. . .. .. ...... .. 5.3-1 5.3.2 Reactor Vessel Materials . .. . .. . . .. . 5.3-4 5.3.3 Pressure-Temperature Limits . . .. . . .. 5.3-13 5.3.4 Reactor Vessel Integrity . . .... .... .. 5.3-14 5.3.5 Combined License Information . . . 5.3-19 5.3.6 References .. . . .. . . . .. .... .. 5.3-20 l 5.4 Component and Subsystem Design . . . . . . .... .. 5.4-1 I 5.4.1 Reactor Coolant Pump Assembly . .. . .. . .. 5.4-1 )
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| Section Title Eage 5.4.2 Steam Generators . ........ .. . . . .. . . ... . . 5.4-10 5.4.3 Reactor Coolant System Pipinr; .. .. ... ..... ... ... .. 5.4 23 5.4.4 Main Steam Line Flow Restriction . . . . ................ 5.4-28 5.4.5 Pressurizer . ................................ .... . 5.4-29 5.4.6 Automatic Depressurization System Valves . .... ......... 5.4-36 5.4.7 Normal Residual Heat Removal System . . . . . . . . . . . . . . . . . 5.4-3 8 5.4.8 Val ve s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........ .. 5.4-51 5.4.9 Reactor Coolant System Pressure Relief Devices . . . . . . . . . . . . 5.4-57 5.4.10 Component Supports . . . . . . . . . . . . . . . ... . . . . . . . . . 5.4-60 5.4.11 Pressurizer Relief Discharge .... .... . . ............ . 5.4-63 5.4.12 Reactor Coolant System High Point Vents . . . . . . . . . . . . . 5.4-65 5.4.13 Core Makeup Tank . . . . . . .... ... ..... ... . . . . . . . 5.4-68 5.4.14 Passive Residual Heat Removal Heat Exchanger . . . . . ...... . 5.4-71 5.4.15 Combined License Information . . . .......... ... . . . . . . . . 5.4-74 5.4.16 References ............... .............. ....... . 5.4-74 CHAPTER 6 ENGINEERED SAFETY FEATURES . . . . . . . . . . . . .......... .. .. 6.0-1 6.1 Engineered Safety Features Materials . . .... .. ..... ... ..... 6.1-1 p 6.1.1 Metallic Materials . . . ........ .. . . ......... . .. . 6.1-1 g 6.1.2 Organic Materials . . . . . . . ............. . . . . . . .. . . . .. .. 6.1-5 6.1.3 Combined License Information Items . ... . ........... . . 6.1-11 6.1.4 References . . . .... ...... .. .... . .. ..... . . . 6.1-12 6.2 Containment Systems . . . . . . . . ..... . .. . . .. . ... .. ... 6.2-1 6.2.1 Containment Functional Design . . ...... .. . ... . . .. .. 6.2-1 6.2.2 Passive Containment Cooling System . . . . . ........ .. 6.2-20 6.2.3 Containment Isolation System ...... . ............ . . 6.2-28 6.2.4 Containment Hydrogen Control System . . .. ..... ..... . 6.2-378 6.2.5 Containment Leak Rate Test System . . ... ...... ... . . . 6.2-48 6.2.6 References ..... ..... ...... .. ....... .... . 6.2-55 6.3 Passive Core Cooling System . . . .... . .. . .. ... . ..... . 6.3-1 6.3.1 Design Basis . . .. ..... .... . . . .. .... .. 6.3-2 6.3.2 System Design . . . . ..... ....... . . .. .. . . . . 6.3-6 6.3.3 Performance Evaluation . . . ... . . ...... .. .. . 6.3-28 l 6.3.4 Post-72 Hour Actions ....... .. ... ....... ....... . 6.3-41 6.3.5 Limits on System Parameters . . . . .. ... . . . . . . 6.3-41 6.3.6 Inspection and Testing Requirements . . . . . . ..... .... . 6.3-42 6.3.7 Instrumentation Requirements .. ...... .... . ... . 6.3-43 6.3.8 Combined License Information . . ...... .. .. . . . . . 6.3-48 6.3.9 References . . . . . . . . . . . . . . . . . .... .... . .. . . 6.3-48 6.4 Habitability Systems .... ............. ..... ... . . . 6.4-1 6.4.1 Safety Design Basis . . . . . . . . . . .. .......... . . . . 6.4-1
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| '6.4.2 System Description . . . . . . . . . . . . . ..... . . . 6.4-2 6.4.3 System Operation . . ...... .. . . . .. . . . 6.4-6
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| Section Title Pm 6.4.4 System Safety Evaluation . . . .. . . .... . .... 6.4-8 6.4.5 Inservice Inspection / Inservice Testing . . . . ... ... . 6.4-10 6.4.6 Instrumentation Requirements . . . .... 6.4-10 6.4.7 Combined License Information . . .. . .. . . . ... . 6.4-11 6.4.8 References . . . .... .. . .. ..... . . . .. . 6.4-11 6.5 Fission Product Removal and Control Systems ... .... . . . . . . 6.5-1 6.5.1 Engineered Safety Feature (ESF) Filter Systems . . . . . . . . . . 6.5-1 6.5.2 Containment Spray System . . . .. .. ... .. ... . 6.5-1 6.5.3 Fission Product Control Systems .. . .. .. ... .. . 6.5-1 6.5.4 Combined License Information . ... . .. ....... . 6.5-2 6.6 Inservice Inspection of Class 2 and 3 Components . . . . .. 6.6-1 6.6.1 Components Subject to Examination . . . . . . . . ... . .... . 6.6-1 6.6.2 Accessibility ... . . . .. ...... ... . . ... 6.6-1 6.6.3 Examination Techniques and Procedures . ... . . . . .. . 6.6-2 6.6.4 Inspection Intervals . . . . ... . .. .. . . . . .. .. 6.6-3 6.6.5 Examination Categories and Requirements . .. .. . ... 6.6-3 6.6.6 Evaluation of Examination Results ........ .. .. . . . 6.6-3 6.6.7 System Pressure Tests . . . . .. . . .... .. .. . . 6.6-3 6.6.8 Augmented Inservice Inspection to Protect against Postulated Piping Failures . . . .... . .... ... . . . 6.6-3 6.6.9 Combined License Information Items . ..... . . .. . 6.6-4 CHAPTER 7 INSTRUMENTATION AND CONTROLS .. . ... .. . ... . . 7.1-1 7.1 Introduction . . . .... ... . . . . .. . .. . 7.1-1 1 7.1.1 The AP600 Instrumentation and Control Architecture . . . . 7.1-2 )
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| 7.1.2 General Protection Subsystem Configuration . .. . .. . . 7.1-6 I 7.1.3 Plant Control System .. .. .. .... ..... . . 7.1-27 7.1.4 Identification of Safety Criteria . . . . . ..... ....... 7.1-32 7.1.5 AP600 Protective Functions . . . . .. 7.1-48 7.1.6 Combined License Information . .. . .. . . . .. 7.1-48 7.1.7 References . .. . ... ...... . . . . . 7.1-49 7.2 Reactor Trip .. . . .... . . . ... . . . 7.2-1 7.2.1 Description . ........ .. .. . . . . . . 7.2-14 7.2.2 Analyses .. .. ..... . . ... ... . . . 7.2-14 7.2.3 Combined License Information . . . . .... . . . 7.2-17 7.2.4 References . . . . . .. ... .. ... . . .. 7.2-17 7.3 Engineered Safety Features . .. ... . .. .. . . . . ... 7.3-1 7.3.1 Description ..... . . . .. . ... .... . . 7.3-1 7.3.2 Analysis for Engineered Safety Features Actuation . . . 7.3-19 7.3.3 Combined License Information . . . . .. . . . . 7.3-22 7.4 Systems Required for Safe Snutdown ... . . . . .. 7.4-1 Revision: 10 December 20,1996 xiy [ W85tingh00S8
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| Section Title Page 7.4.1 Safe Shutdown . . . . . . . ........ . . . ....... ... 7.4-3 7.4.2 Safe Shutdown Systems . . . . . . . . . . . . . ..... ..... . . 7.4-10 ,
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| 7.4.3 Safe Shutdown from Outside the Main Control Room . . . . . . . . . 7.4-11 1 7.4.4 Combined License Information . . . . ... . ... ... 7.4 14 i 7.4.5 References . . ... ..... ... . . . ... . 7.4-14 I 7.5 Safety-Related Display Information ..... . . .. . .. . . . 7.5-1 l 7.5.1 Introduction . . . . .. ... . ... ... .... .. . . 7.5-1 i 7.5.2 Variable Classifications and Requirements . ... . .. . 7.5-1 l 7.5.3 Description of Variables . .. ... ... . . . . . . . . 7.5-9 7.5.4 Processing and Display Equipment . . . .. . . ... .. . 7.5-11 7.5.5 Combined License Information . . . . . . . .. . . ........ 7.5-13 !
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| 7.6 Interlock Systems Important to Safety . . ... ......... ...... . 7.6-1 7.6.1 Prevention of Overpressurization of Low-Pressure Systems .. . . . 7.6-1 7.6.2 Availability of Engineered Safety Features ... . . ..... . . ... 7.6-2 7.6.3 Combined License Information . . . . .. .. . ... . . . 7.6-5 7.7 Control and Instrumentation Systems . . . . . . ..... . ... .... 7.7-1 7.7.1 Description ........ ...... . .. . .. . 7.7-2 7.7.2 Analysis .... . ..... .... .... . . . ....... 7.7-20 A 7.7.3 Combined License Information . .. 7.7-21 v)
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| Volume 5 CHAPTER 8 ELECTRIC POWER . . . . . . . .. .. .. . .. ... .. .. 8.1-1 8.1 Introduction ...... . ................. .... .. ...... . 8.1-1 ;
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| 8.1.1 Utility Grid Description . . .. . .. .. .... . . . 8.1-1 8.1.2 Onsite Power System Description . . . ......... ... . 8.1-1 8.1.3 Safety-Related Loads . .... . . . .. .. 8.1-2 8.1.4 Design Basis . . .. ... .. .. . ...... .. ...... . . 8.1-2 8.1.5 Combined License Information . . . .. .. . . . . . 8.1-5 8.2 Offsite Power System ....... . . . . . . . .. . 8.2-1 8.2.1 System Description . . . . . .. . ... . .. .. . . 8.2-1 8.2.2 Conformance to Criteria . . . . . . ... . . . 8.2-2 8.2.3 Standards and Guides . . . . .. . . .. ..... .. . 8.2-2 8.2.4 Combined License Information for Offsite Electrical Power . . ... . 8.2-2 8.2.5 References . . . .. . .. ... . ... ... . 8.2-2 8.3 Onsite Power Systems . . . . . . .. . . . . . . 8.3-1 8.3.1 AC Power Systems . . . . . . . . ... . 8.3-11 8.3.2 DC Power Systems . .. .. . . . .. . . . . 8.3-13
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| , 8.3.3 Combined License Information for Onsite Electrical Power .. 8.3-21 8.3.4 References . . ... .. .. . . ... .... 8.3-22 O.
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| Section Title Page CHAPTER 9 AUXILIARY SYSTEMS . ....... ...... .. ........ ... .9.11 9.1 Fuel Storage and Handling . . . . . . . .. .
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| .. .. . ..... ... . 9.1-1 9.1.1 New Fuel Storage . . . . . . .. .. .. .......... ...... 9.1-1 9.1.2 Spent Fuel Storage . . . . . .... ... . . ... .... .. 9.1-5 9.1.3 Spent Fuel Pool Cooling System . . ...... . .. .. ... . 9.1 10 9.1.4 Light Load Handling System (Related to Refueling) . . . 9.1 21 9.1.5 Overhead . Heavy Load Handling Systems .... ...... . . 9.1-34 9.1.6 Combined License Information for Fuel Storage Handling .. . 9.1-40 9.1.7 References ... . . ....... ... . .. .. . . . . . . 9.1 -40 9.2 Water Systems .. ..... ... . .... . . . .. ... 9.2-1 9.2.1 Service Water System . ..... . . .... .. . . ... 9.2-1 9.2.2 Component Cooling Water System . . . ... .. ... .. .. . 9.2-7 9.2.3 Demineralized Water Treatment System . . . . . . . .... .. . 9.2-16 9.2.4 Demineralized Water Transfer and Storage System . . ... . 9.2-20 9.2.5 Potable Water System ... . .. .... ... .. .... . 9.2-25 9.2.6 Sanitary Drainage System ... . ..... . . . . 9.2-28 9.2.7 Central Chilled Water System . . . .. . .... . . .. . . . . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . ... . . 9.2-36 9.2.9 Waste Water System . ..... . ........... .. .. . 9.2-40 9.2.10 Hot Water Heating System .. ..... . ....... ... ... . 9.2-44 9.2.11 Combined License Information . . . ..... .. . ...... . 9.2-47 9.2.12 References . . . . ... ........ .... . ....... . 9.2-48 9.3 Process Auxiliaries . . . . . . . . . . . . . . . ....... .. ..... . .. 9.3-1 9.3.1 Compressed and Instrument Air System ...... . .. .... 9.3-1 9.3.2 Plant Gas System ..... .... .. ...... .. . ... 9.3-7 9.3.3 Primary Sampling System .. .. .. ..... ... ... . . 9.3-10 9.3.4 Secondary Sampling System . .... .. .. . .. .. 9.3-15 .
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| 9.3.5 Equipment and Floor Drainage Systems . . .. . . . 9.3-17 !
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| 9.3.6 Chemical and Volume Control System .. .... 9.3-22 l
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| 9.3.7 Combined License Information . . . . . .. . 9.3-43 i 9.3.8 References ... .. .... . . . .. 9.3-43 Volume 6 l 9.4 Air-Conditioning, Heating, Cooling, and Ventilation System ... . . . 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System . .. . . 9.4-1 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System . 9.4-15 9.4.3 Radiologically Controllea Area Ventilation System ...... 9.4-26 I 9.4.4 Balance-of-Plant Interface . . . . ... . . 9.4-36 l 9.4.5 Engineered Safety Features Ventilation System . .. . .. 9.4-36 l 9
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| Section Title Page 9.4.6 Containment Recirculation Cooling System . . . .. ... ..... . 9.4-36 9.4.7 Containment Air Filtration System . . ................. . 9.4-41 9.4.8 Radwaste Building HVAC System . .... ...... . . . . . . 9.4-49 9.4.9 Turbine Building Ventilation System .. .... .. .. 9.4-54 9.4.10 Diesel Generator Building Heating and Ventilation System .... . 9.4-59 9.4.11 Health Physics and Hot Machine Shop HVAC System .. ..... . 9.4-65 9.4.12 Combined License Information . . . . .. . . ... . 9.4-70 9.4.13 References . . . . . . .. .. ... .. .. ...... . . 9.4-70 9.5 Other Auxiliary Systems .. . .. .. . . . . . . . . 9.5-1 s 9.5.1 Fire Protection System ......... ... ......... 9.5-1 9.5.2 Communication System ..
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| . ... ..... .... . ... 9.5-14 j 9.5.3 Plant Lighting System . .... . . ... .. .. . . 9.5-18 i 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System . ..... .. 9.5-21 9.5.5 References . . ........ . . .... ... . . . . . 9.5-27 APPENDIX 9A FIRE PROTECTION ANALYSIS .. . . .. . . . . 9A-1 9A.1 Introduction . .. ....... ... . ...... ... .. . 9A-1 9A.2 Fire Protection Analysis Methodology . . ... ........... ... . 9A-1 (3 9A.2.1 Fire Area Description . . . . .. . . .. ........ . . 9A-1
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| x ) 9A.2.2 Combustible Material Survey . . . . ............. . 9A-2 9A.2.3 Fire Severity Categorization . . . . . . . . ......... ..... . . . 9A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration Calculations . ....... .......... .......... . . . . 9A-2 9A.2.5 Fire Protection Adequacy . .. .... . . .... . ...... . 9A-3 9A.2.6 Fire Protection System Integrity . . . ...... . ......... . 9A-4 9A.2.7 Safe Shutdown Evaluation . . . . ... . .. ........ . . . . . 9 A-4 9A.3 Fire Protection Analysis Results ... . . ....... . . . . . . 9A-8 9A.3.1 Nuclear Island ... . ... . . ... ...... . . . . 9A-9 9A.3.2 Turbine Building . . .... . ... .. . . .. . 9A-61 9A.3.3 Yard Area And Outlying Buildings .. ..... ... 9A-72 9A.3.4 Annex I and II Buildings . . . . . . . . .... . . . 9A-72 9A.3.5 Radwaste Building . ...... . . . .. . . 9A-88 9A.3.6 Diesel Generator Building . . . . . ..... . 9A-90 9A.3.7 Special Topics . . . .. ... . . .. . . . ... . 9A-94 9A.4 References . . .. .. . .. ..... .. . . 9A-97 Volume 7 CHAIrrER 10 STEAM AND POWER CONVERSION SYSTEM . .. . . 10.1-1 10.1 Summary Description . ... .... . . . .. . . 10.1-1 10.1.1 General Descriptionn . ...... . . . . . .. . 10.1-1 10.1.2 Protective Features . . .. .. . . ... ... . 10.1-2 (v)
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| 1 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . . 10.1-4 l 10.2 Turbine-Generator ..... ... . ... . . ... .... .... . 10.2-1 !
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| 10.2.1 Design Basis ..... . .... ....... . .... .. . 10.2-1 10.2.2 System Description . .. . ...... .. ....... .. . 10.2-1 10.2.3 Turbine Rotor Integrity . . .... ... ..... ... . 10.2-11 10.2.4 Evaluation ............. . ...... ..... . 10.2-17 10.2.5 Instrumentation Applications . ...... .. . ..... . . . 10.2-17 l 10.2.6 Combined License Information on Turbine Maintenance and inspection ..... .. .. .. . . ........ .. 10.2-19 10.2.7 References . . . . . . . . . . . . ... . . . .... . 10.2-19 10.3 Main Steam Supply System . . .. .... ... .. .. . . 10.3-1 10.3.1 Design Basis . . . .. .. . . . .. .. . 10.3-1 l 10.3.2 System Description . . . . .. . ... . . .. ... . 10.3-4 l
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| 10.3.3 Safety Evaluation . . ... ... . . .... . .... 10.3-10 10.3.4 Inspection and Testing Requirements . . .. . ...... . 10.3-12 10.3.5 Water Chemistry ........ . . . ... . ... ... .. 10.3-12 i 10.3.6 Steam and Feedwater System Materials . . . . . . . . . 10.3-16 10.3.7 Combined License Information . . . . . . . ... . ... .... 10.3-17 10.3.8 References . . ... . . .. ... . .. .. ... . 10.3-17 j 10.4 Other Features of Steam and Power Conversion System . .. . ... . . . . 10.4-1 10.4.1 Main Condensers . . . . . . . .. . .... . . 10.4 1 10.4.2 Main Condenser Evacuation System . . .. ....... . . 10.4-4 10.4.3 Gland Seal System . .. . .. .... .. . ......... . 10.4-6 10.4.4 Turbine Bypass System . .. .... .. ... . . . . 10.4-8 )
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| 10.4.5 Circulating Water System . . . ... . . ,.. . . 10.4-12 10.4.6 Condensate Polishing System .. .. ... . . .. .. 10.4-17 10.4.7 Condensate and Feedwater Systems . . . . . .... ... 10.4-20 10.4.8 Steam Generator Blowdown System . . . .. . . . 10.4-35 10.4.9 Startup Feedwater System . ..... . . . 10.4-44 10.4.10 Auxiliary Steam System .... ... .. . 10.4-53 ,
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| i 10.4.11 Turbine Island Chemical Feed ... . . . 10.4-56 l 10.4.12 Combined License Information . . . . ... . . . 10.4-59 10.4.13 References . . .. . ... . .... .. . 10.4-59 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT . . . .. . . .. .. .... . I1.1-1 11.1 Source Terms . .. .... . . . .... .. I1.1-1 11.1.1 Design Basis Reactor Coolant Activity . ... ..... . . I1.1-1 11.1.2 Design Basis Secondary Coolant Activity . . . . . . 11.1 -3 11.1.3 Realistic Reactor Coolant and Secondary Coolant Activity ... 11.1-4 11.1.4 Core Source Term ... . .. .. . .. . .. 11.1-4 O
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| Section Title Page 11.1.5 Process Leakage Sources ... . . ..... ...... .... . I1.1-4 11.1.6 Combined License Information . .... ... ..... .. ... . .. I1.1-4 11.1.7 References . ........ . .... .. ...... . . 11.1-5 11.2 Liquid Waste Management Systems .. . ..... .... . . .. . . I1.2-1 11.2.1 Design Basis . . . .. .... .. . . ... ........ .. . 11.2-1 11.2.2 System Description .... .......... .. .... ....... .. 11.2-6 11.2.3 Radioactive Releases . . . . .. . . .... . . ....... . 11.2-18 11.2.4 Combined License Information . . . . . . .... . .. .... . I1.2-20 11.2.5 References . . . . .. ........ . . .... ........ .. 11.2-20 11.3 Gaseous Waste Management System . . . . . . . .... . . .. . . . . . I1.3-1 11.3.1 Design Basis . . . . . . . . . . ...... .. . .. ..... . . . 11.3-1 11.3.2 System Description . . . . . . . . . . .. . . .. ... ... . . 11.3-4 11.3.3 Radioactive Releases . ... ... . .. . .... . I1.3-9 11.3.4 Combined License Information . . . . . .. ...... . . I1.3-11 11.3.5 References . . . .... ..... . . .... ... ... 11.3 11 11.4 Solid Waste Management . ...... .. .... . . .. ... . . . 11.4-1 11.4.1 Design Basis ..... . . .. ........ .... . . , 11.4-1 11.4.2 System Description . . . . ....... ..... ............ . 11.4-3 (7 11.4.3 System Safety Evaluation .......... ....... ... ... . 11.4-13
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| () 11.4.4 Tests and Inspections . .... .... ..... ...... .. .. 11.4-13 11.4.5 Quality Assurance . . . . ... ........ ..... ..... .. .. 11.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program .. . . ..... .. .. I1.4-13 11.4.7 References . . . . . . . ...... ...... . ......... 11.4-14 11.5 Radiation Monitoring . . .. .... .. . ..... . .. ... . . 11.5-1 11.5.1 Design Basis . ..... ... . ..... . ...... ..... 11.5-1 11.5.2 System Description . . ..... . . ... .... .. .. .... 11.5-2 11.5.3 Effluent Monitoring and Sampling . . . . . .... ... . . . . I 1.5-13 11.5.4 Process and Airborne Monitoring and Sampling . .. .. . I1.5-13 11.5.5 Post-Accident Radiation Monitoring . .. . .. . 11.5-14 11.5.6 Area Radiation Monitors . . . . . . . . . .. .. . . 11.5-14 11.5.7 Combined License Information . . . . .. . 11.5-17 CHAPTER 12 RADIATION PROTECTION . . .. .. .. .. . . . . . . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As-Low-As-Reasonably Achievable (ALARA) . . ... .. .. . 12.1-1 12.1.1 Policy Considerations .... .. . . . .. 12.1-1 12.1.2 Design Considerations . ....... .. . .. . . 12.1-2 12.1.3 Combined License Information . . . . .. .. . . 12.1-6 12.2 Radiation Sources . ..... ... . . ... . . . 12.2-1 12.2.1 Contained Sources . . ...... ...... . .. . . 12.2-1 12.2.2 Airborne Radioactive Material Sources .. . .. .. .. . . 12.2-6 i 4 Q
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| Fection .Ti Le Page 12.2.3 Combined License Information . . . .. .. .. .. . .. . .. 12.2-8 12.2.4 References . . .. .... .. ... .. ... ........ . . 12.2-8 12.3 . Radiation Protection Design Features . . . . ... ..... ..... . . . 12.3-1 12.3.1 Facility Design Features .. .. .. . . . . . . . . 12.3-1 12.3.2 Shielding . . . . . . . . . . . . . . .. . . . .. .. . .. . . .. 12.3-9 12.3.3 Ventilation . . . ... .. . .. ......... ... . . . 12.3-15 12.3.4 Area Radiation and Airbome Radioactivity Monitoring Instmmentation . . . . . .... . . .. . .. .. . .. 12.3-19 12.3.5 Combined License Information . .. ... . . ... . 12.3-19 12.3.6 References .. . . .... . ..... 12.3-19 12.4 Dose Assessment ........ ... . .. .... .. .. . . . 12.4 1 12.4.1 Occupational Radiation Exposure . . .. . . ... . . 12.4-1 12.4.2 Radiation Exposure at the Site Boundary .... .. .. . 12.4-4 12.4.3 Combined License Information . . . ... ... . ... . . 12.4-4 12.5 Health Physics Facilities Design . . . ...... .. .. . . 12.5-1 12.5.1 Objectives . .... ...... .. . . .. .... . . . 12.5-1 12.5.2 Equipment, Instmmentation, and Facilities . . .... . . . . . 12.5-1 12.5.3 Other Design Features . . ..... .. .. .. . .... . . . 12.5-3 12.5.4 Controlling Access and Stay Time . ..... .. . . 12.5-4 12.5.5 Combined License Information . . . .... .. . . . . 12.5-5 Volume 8 CHAIYTER 13 CONDUCT OF OPERATION . . . . . .... . . . . . ... 13-1 13.1 Organizational Stmeture of Applicant ... .. ... . . ... ...... . 13-1 ]
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| 13.1.1 Combined License Information Item ......... ... ... ..... 13-1 {
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| 13.2 Training . . ........ ... ...... .. . . .. . ... 13-1 l 13.2.1 Combined License Information Item .. . . ... ... 13-1 13.3 Emergency Planning . . . . . . .. .. . . . . 13-1 13.3.1 Combined License Information Item . . . . . . 13-2 ,
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| 13.4 Operational Review . . . . . . . . .. . .... . .. 13-2 i 13.4.1 Combined License Information Item . .... .... 13-2 I 13.5 Plant Procedures . . ..... . .. . . .. . . ... 13-2 13.5.1 Administrative Procedures . . . . .. 13-2 13.6 Industrial Security . ,... . .. .. . . . . 13-3 13.6.1 Preliminary Planning . .. . . . . 13-3 13.6.2 Security Plan . . . ... . . . ....... .. . 13-3 i 13.6.3 Plant Protection System . . .. . . . . 13-3 l 13.6.4 Physical Security Organization . ..... . . 13-5 13.6.5 Physical Barriers . . . . . . . . 13-5 l .
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| 13.6.6 Access Requirements .. . ... . . . . ..... . 13-6 13.6.7 Detection Aids . . . . . . . . . .. .. .. .. ... . ...... 13-7 13.6.8 Security Lighting . . .. .. ... ... .. . . ... . .. 13-7 13.6.9 Security Power Supply System . . . . . . ..... . . .. 13-7 13.6.10 Communications . . . ... . . .. . . . . 13-7 13.6.11 Testing and Maintenance . .. ..... . .. . . . 13-8 13.6.12 Response Requirements .. .. . ... . ....... . . 13-8 13.6.13 Combined License Information Item ... . . .. ... . 13-8 13.7 References . .... ... ... .... . .. . .... 13-8 CHAPTER 14 INITIAL TEST PROGRAM . . ........ ... ...... ... . . 14.1-1 i 14.1 Specific Information to be Included in Preliminary / Final Safety Analysis Reports . . . . . ... ... ..... . ... . .. . . . 14.1 - 1 14.2 Specific Information to be Included in Standard Safety Analysis Reports . 14.2-1 14.2.1 Summary of Test Program and Objectives . . ...... 14.2-1 14.2.2 Organization, Staffing, and Responsibilities . ....... . . 14.2-4 14.2.3 Test Specifications and Test Procedures ... .. . .... 14.2-4 14.2.4 Compliance of Test Program with Regulatory Guides . ... . 14.2-6 77 (j
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| 14.2.5 Utilization of Reactor Operating and Testing Experience in the Development of Test Program . . . . . ........ . 14.2-6 14.2.6 Use of Plant Operating and Emergency Procedures . . . . . . 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality . ... .. .... . . 14.2-7 14.2.8 Test Program Schedule . ... ... .. . ... ... . . . 14.2-10 14.2.9 Preoperational Test Descriptions . . . . . .. .. .. ... . 14.2-10 14.2.10 Stanup Test Procedures . . .. .. . .... . ... . . 14.2-80 14.3 Certified Design Material . . . . . . . . . . . . . . . .......... . 14.3-1 i 14.3.1 CDM Section 1.0, Introduction . . . . . . . .. . ....... . 14.3 2 14.3.2 CDM Section 2.0, System Based Design Descriptions i and ITAAC .. .. ... . . . .. ... . ...... . 14.3-3 j 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions j and ITAAC .... . .. . ... . . ... .. . 14.3-9 i 1
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| 14.3.4 Certified Design Material Section, 4.0 Interface Requirements . 14.3-10
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| . 14.3.5 CDM Section 5.0, Site Parameters .. .. .. .. .... ... 14.3-10 14.3.6 Initial Test Program . . .. . 14.3-10 l 14.3.7 Summary . .. .. . .. ... . ... . 14.3-11 l 14.3.8 References . . ... . . . .. . .. . 14.3-11 l 14.4 Combined License Applicant Responsibilities . . . . . .. . 14.4-1 14.4.1 Organization and Staffing . ... .. . 14.4-1 )
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| 14.4.2 Test Specifications and Procedures . . .. . . . . 14.4-1 i 14.4.3 Conduct of Test Program . . . .. .. . .. . . 14.4 1 14.4.4 Review and Evaluation of Test Results . . .. . 14.4-1 1
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) O1 Section Title Page CHAPTER 15 ACCIDENT ANALYSES .. . . .... .. .... .... . . . 15.0-1 15.0.1 Classification of Plant Condit'Ons ... .
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| . .. ........... ... . 15.0-1 15.0.2 Optimization of Control Systems . . . . . . . . . ......... . . . . . 15.0-5 15.0.3 Plant Characteristics and Initial Conditions Assumed in the Accident Analyses . . . . . . .. . ... . . .. . .... . 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysis . . . . . . . .. . . 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics . . . . .. .. 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses . . 15.0-8 15.0.7 Instmmentation Drift and Calorimetric Errors, Power Range Neutron Flux . . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . . .... . . . ... .. . .. 15.0-10 15.0.10 Residual Decay Heat . . .. .... . . , . . . ... . 15.0-10 15.0.11 Computer Codes Utilized .. ...... .. .... . ... .. . 15.0-11 15.0.12 Component Failures . . .. . ..... .. . ..... .. .... 15.0-13 15.0.13 Operator Actions . . . . . . .... .... .. .. .. . ..... ... . 15.0-14 15.0.14 Combined License Information . . . . ... . .. . .... .. 15.0-14 15.0.15 References . .. ..... ............. . ..... ... . 15.0 14 15.1 Increase in Heat Removal from the Primary System . . .. . . . . 15.1-1 15.1.1 Feedwater System Malfunctions that Result in a Decrease in Feedwater Temperature . . . . . .. . .. ..... . 15.1-1 15.1.2 Feedwater System Malfunctions that Result in an increase in Feedwater Flow . . . . . . . ...... . .. . ..... .. . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow . ..... .. .. . 15.1-5 15.1.4 Inadvenent Opening of a Steam Generator Relief or Safety Valve . . 15.1-8 15.1.5 Steam System Piping Failure ... .. ... . . ... . 15.1-11 15.1.6 Inadvertent Operation of the Passive Residual Heat Removal l Heat Exchanger .... ... . .. . .. ... .. 15.1-20 15.1.7 Combined License Information .. ... . ... . ... 15.1-24 15.1.8 References . . . ..... . .. . .. 15.1-24 ;
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| 15.2 Decrease in Heat Removal by the Secondary System . . . . .. . 15.2-1 l 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . . . .... . . . . . .. 15.2-1 15.2.2 Loss of External Electrical Load . . . . . 15.2-1 15.2.3 Turbine Trip ..... .. . .. . . . ... . 15.2-3 15.2.4 Inadvenent Closure of Main Steam Isolation Valves . . . .. 15.2-7 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries . . . 15.2-8 15.2.7 Loss of Normal Feedwater Flow . .. .. . . . . 15.2-12 15.2.8 Feedwater System Pipe Break . . ... . . 15.2-16 15.2.9 Combined License Information . . .. . 15.2-21 O
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| 15.2.10 References . . ....... . . . ...... . . . . 15.2-21 15.3 Decrease in Reactor Coolant System Flow Rate ........ ... ... .. 15.3-1 15.3.1 Panial Loss of Forced Reactor Coolant Flow . . . . . . ... .... . 15.3-1 l 15.3.2 Complete Loss of Forced Reactor Coolant Flow . . . . .
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| . . . . 15.3-3 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) ......... 15.3 .5 )
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| 15.3.4 Reactor Coolant Pump Shaft Break ... ......... ... . . 15.3-10 15.3.5 Combined License Information . ..... . .. . ... ... 15.3-10 l 15.3.6 References . . . . .......... . .. ......... ...... 15.3-11 I 15.4 Reactivity and Power Distribution Anomalies . . . .. . .... . . . 15.4-1 -
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| 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Suberitical or Low-Power Startup Condition .. . ..... . 15.4-1 l 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power . ........ . ..... .. . . . . 15.4-5 15.4.3 Rod Cluster Control Assembly Misalignment (System Malfunction or Operator Error) ........ .... ........... 15.4-11 15.4.4 Stanup of an Inactive Reactor Coolant Pump at an Incorrect Temperature . . ....... .. .. . . . ...... .... . 15.4-17 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling q Water Reactor Loop tha' Results in an Increased Reactor
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| ( ,/ Coolant Flow Rate . . . . . ........... ..... . ..... 15.4-19 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant . . . . . .. ... ... . . ... ...... . 15.4-19 15.4.7 Inadvenent Loading and Operation of a Fuel Assembly in an Improper Position . . . . . . . .. ............ ........... 15.4-25 15.4.8 Spectrum of Rod Cluster Control Assembly Ejection Accidents . . 15.4-28 15.4.9 Combined License Infomiation . .. . ... . . .. 15.4-39 15.4.10 References ...... . . . . ... . ... 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory . .. . . 15.5-1 15.5.1 Inadvenent Operation of the Core Makeup Tanks (CMT) During Power Operation .. ... . . .. .. .. 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory .... . . . 15.5-4 15.5.3 Boiiing Water Reactor Transients . . .. . . 15.5-8 15.5.4 Combined License Information . . . . .. . . . . 15.5-8 15.5.5 References ..... . .. . .. .. . . 15.5-8 15.6 Decrea.se in Reactor Coolant Inventory . ... . . .. .... 15.6-1 15.6.1 Inadvenent Opening of a Pressurizer Safety Valve or Inadvenent Operation of the ADS . . . . . . 15.6-1
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| l Section Title Page 15.6.2 Failure of Small Lines Carrying Primary Coo! ant Outside Containment . . . ....... . . .... ..... .... ...... 15.6-4 15.6.3 Steam Generator Tube Rupture .... - . . . .. .... . .... . . 15.6-5 15.6.4 Spectrum of BWR Steam System Piping Failures Outside of Containment . . .. . .... . .... . . 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . . ... . . ... ... 15.6-15 15.6.6 References . . . . . . ... .. . . . ... . . . . 15.6-64 15.7 Radioactive Release From a Subsystem or Component . .... ... 15.7-1 15.7.1 Gas Waste Management System Leak or Failure ...... . . . 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ..... ..... ... ..... . . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure ... ....... . ... ....... ... . 15.7-1 15.7.4 Fuel Handling Accident . . . . . . .. . . ..... . ... . 15.7-1 15.7.5 Spent Fuel Cask Drop Accident .. . .... ...... . ... . 15.7-6 15.7.6 Combined License Information . . .. . .... 15.7-6 15.7.7 References . . . .... . .. .... .......... . 15.7-7 15.8 Anticipated Transients without Scram . . .... .. .. . . . .. 15.8-1 15.8.1 Gen. ral Background . ...... . .. .. ... .. . .. 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . . . . . ....... 15.8-1 15.8.3 Conclusion . . ... ... ... .... .... . ... . .. 15.8-1 15.8.4 Combined License Information ..... .. ...... ..... . . 15.8-1 15.8.5 References . . . . . . ...... ..... .... ..... ... .. . 15.8-1 )
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| APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS !
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| OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS .. .. . 15A-1 I 1 SA.1 Offsite Dose Calculation Models . . . . .. .. 15A-1 l 15 A.I .1 Immersion Dose Models . . . . . . . . 15A-1 15A.I.2 Inhalation Dose (Committed Effective Dose Equivalent) .. . 15 A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) .. . . 15A-2 15A.2 Main Control Room Dose Models . .. ... .... . 15A-2 j 15A.2.1 Immersion Dose Models . ... . . ...... . 15A-2 15 A.2.2 Inhalation Dose . . ... . . . 15A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) . . .. .. . 15A-4 15A.3 General Analysis Parameters .... . . ... 15A-4 15A.3.1 Source Terms . . . . . .. . . . 15A-4 1 15 A.3.2 Nuclide Parameters . .. . . . . . . 15A-6 15A.3.3 Atmospheric Dispersion Factors ... . .. 15A-6 15A.4 References ..... . .. . .... 15A-6 O
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| Section Title h Volume 10 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS . . .... . . . .... 16.1-1 16.1.1 Introduction to Technical Specifications . . . . . .. . ... . 16.1-1 1.0 Use and Application ...... ....... .... . . . ... . 1.1-1 1.1 Definitions ...... . . . . . .. . . . 1.1-1 1.2 Logical Connectors . ... . . . . .. .. 1.2-1 1.3 Completion Times . . . .... .... .. .... . 1.3-1 1.4 Frequency . . . .. . .. .. .. . . . . 1.4-1 2.0 Safety Limits (SLs) . . . . . . ... . . . .... . . 2.0-1 2.1 SLs . . .. .. .. . .............. ... .. .. 2.0-1 2.2 SL Violations . . . . .. ... .. ...... ...... . 2.0-1 3.0 Limiting Conditions for Operation (LCO) Applicability . . . . . . . 3.0-1 3.0 Surveillance Requirement (SR) Applicability ...... . .. . 3.0-4 l 3.1 Reactivity Control Systems . . . . .. . . .. .. . . . 3.1-1 3.1.1 Shutdown Margin (SDM) . .... . ... .... 3.1-1 3.1.2 Core Reactivity .. . . . . . . . ... . . 3.1-2
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| /3 3.1.3 Moderator Temperature Coefficient (MTC) .. . . . .. 3.1-4
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| () 3.1.4 Rod Group Aligument Limits . . . . . ... .. ...... . 3.1-6 3.1.5 Shutdown Bank Insertion Limits . .. . ........ . 3.1-11 3.1.6 Control Bank Insertion Limits ....... .... .... 3.1-13 3.1.7 Rod Position Indication . . . . .. .. ... . . . 3.1-16 l 3.1.8 Physics Tests Exceptions - Mode 2 . .. .. .. .... 3.1-18 I 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves .. . 3.1-20 3.2 Power Distribution Limits . . . . . . .. .. . .. 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fn (Z)) ,
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| (FqMethodology) .... . . .. . . . . 3.2-1 1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) ... .. . . .. . . ... 3.2-5 3.2.3 Axial Flux Difference (AFD)(Relaxed Axial Offset Control (RAOC) Methodology) .. .. . . . 3.2-8 l 3.2.4 Quadrant Power Tilt Ratio (QPTR) . 3.2-10 3.2.5 OPDMS-Monitored Power Distribution Parameters . . ... .. .. . .. . 3.2-14 3.3 Instmmentation . . . . .. .. 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation . . 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation . ...... . . 3.3-17 3.3.3 Post Accident Monitoring (PAM) Instmmentation 3.3-45
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| ,, 3.3.4 Remote Shutdown Workstation . . . .. . . 3.3-48
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| Section Title Page 3.4 Reactor Coolant System (RCS) .... . ..... .... . .. 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . . . .. 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . .. . . . 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits ....... . 3.4-4 3.4.4 RCS Loops - Modes 1 and 2 ..... ... ... 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . . . 3.4-7 3.4.6 Pressurizer ... ... . . . .. . . . . 3.4-9 3.4.7 Pressurizer Safety Valves . . ... .. .. . . 3.4-10 3.4.8 RCS Operational Leakage ... . .. . 3.4-12 3.4.9 Minimum RCS Flow . . .. .. . . . . 3.4-14 3.4.10 RCS Leakage Detection Instrumentation .. . .. 3.4-15 3.4.11 RCS Specific Activity .... . ..... . .. 3.4-18 3.4.12 Automatic Depressurization System (ADS)- Operating . 3.4-20 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Intact ...... . .. . .. . . . . . . . . . . . 3.4-22 3.4.14 Automatic Depressurization System (ADS) - Shutdown, RCS Open . . . . . . . . . . .... . ....... . . 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . .. . ..... . ..... . 3.4-26 3.5 Passive Core Cooling System (PXS) ... ... . .. . . 3.5-1 3.5.1 Accumulators . . . ... . .. . ... 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating . .... . .. .. 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . .. . 3.5-9 l
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| 3.5.5 Passive Residual Heat Removal Heat Exchanger !
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| (PRHR HX) - Shutdown, RCS Intact . . .. .. . . 3.5-11 l 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - l Operating . .. ... .. .. .. . 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory High . . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low . . . 3.5-18 3.6 Containment Systems ... . . . .. .. . .. 3.6-1 3.6.1 Containment . . . .. . . ... . . 3.6-1 3.6.2 Containment Air Locks . ...... . 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . 3.6-7 3.6.4 Containment Pressure .. .. . . 3.6-12 3.6.5 Containment Air Temperature . .. .. . . 3.6-13 O
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| Section Title Pag.e 3.6.6 Passive Containment Cooling System (PCS)- Operation . 3.6-14 3.6.7 Passive Containment Cooling System (PCS)- Shutdown . 3.6-17 3.6.8 Containment Penetrations . . . ..... . . .. . 3.6-19
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| . 3.6.9 pH Adjustment . . . .. .. .. .. . .. ..... 3.6-22 3.7 Plant Systems . . . . . . . . . . .... . ..... ... . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) .. .... ....... 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . .... ...... 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves (MFIV and MFCV) . .. ... ....... ..... . ... 3.7-7 3.7.4 Secondary Specific Activity . . ..... .... ... . 3.7-9 3.7.5 Spent Fuel Pool Water Level . ... . .. . 3.7-10 3.7.6 Main Control Room Habitability System (VES) . . . 3.7-11 3.7.7 Stanup Feedwater Isolation and Control Valves . . .. . 3.7-15 3.8 Electrical Power Systems . . . .. .. . .. ... 3.8-1 3.8.1 DC Sources - Operating . . . .. .. ... .. 3.8-1 3.8.2 DC Sources - Shutdown . ... . . ....... .. . 3.8-5 3.8.3 Inverters - Operating . . . . . . ... ...... 3.8-7 3.8.4 Inveners - Shutdown . . ...... .. .. . 3.8-9 (3 3.8.5 Distribution Systems - Operating ... .. .. . ... . 3.8-11 Cl 3.8.6 Distribution Systems - Shutdown ... ....... . . . 3.8-13 3.8.7 Battery Cell Parameters . . . . . . .. . .. . . . . . . . 3.8- 15 3.9 Refueling Operations .. . .. ..... ..... ... . . 3.9-1 3.9.1 Boron Concentration . . . . ..... .. . . 3.9-1 3.9.2 Unborated Water Source Flow Paths . . .. . . .. 3.9-2 3.9.3 Nuclear Instmmentation . . . ..... . .. . .. 3.9-4 3.9.4 Refueling Cavity Water Level . . ... . . .. .... 3.9-6 4.0 Design Features . . . ....... . .. .......... .. 4.0-1 4.1 Site . . . .... ..... . . .. .. ....... ... . 4.0 1 4.1.1 Site and Exclusion Boundaries . .. . .. . .. 4.0-1 4.1.2 Low Population Zone (LPZ) . . . . . 4.0-1 4.2 Reactor Core ..... . ........ .... . . 4.0-1 4.2.1 Fuel Assemblies . . . .. .. . .. .. 4.0-1 4.2.2 Control Rod and Gray Rod Assemblies . .. 4.0-1 4.3 Fuel Storage . . . . .. ..... . . . . . . . 4.0-2 4.3.1 Criticality . . . .. . .. . .. .. . 4.0-2 4.3.2 Drainage . . . .. . .... 4.0-2 4.3.3 Capacity . . . .. . ... . . . . 4.0-2 4.4 Hydrogen Control . . . ... .... ... . . 4.0-3 4.4.1 Passive Autocatalytic Recombiners (PARS) .. 4.0-3 5.0 Administrative Controls . . . . .. . . 5.0-1 5.1 Responsibility . . . . . . . .. .. ... . 5.0-1 5.2 Organization . .. ... .. . .. ... . 5.0-2
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pane 5.3 Unit Staff Qualifications .. .... . ... .... .. 5.0-5 5.4 Procedures . . . . .
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| ..... . .... ... . 5.0-6 5.5 Programs and Manuals . . . . . .. . .. 5.0-7 5.6 Reporting Requirements . ... . . . . 5.0-15 B 2.0 Safety Limits (SLs) . . ... . . . ... ... B 2.0-1 B ?.1.1 Reactor Core Safety Limits (SLs) . ... ... B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability ... .. B 3.0-1 B 3.0 Surveillance Requirement (SR) Applicability . ...... B 3.0-12 B 3.1 Reactivity Control Systems ... .. ..... .. . . B 3.1-1 B 3.1.1 Shutdown Margin (SDM) . ... .... . B 3.1-1 B 3.1.2 Core Reactivity . . .
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| ... .... ... B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . . . ... .. . B 3.1-19 B 3.1.5 Shutdown Bank Insertion Limits . ... . . B 3.1-29 B 3.1.6 Control Bank Insertion Limits . ....... . B 3.1-34 B 3.1.7 Rod Position Indication ... .... B 3.1-40 B 3.1.8 Physics Tests Exceptions - Mode 2 .. .... B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves . . . . . B 3.1-53 B 3.2 Power Distribution Limits . . . . ... . ... . B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (F (Z))
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| n (FqMethodology) . . . ...... .. ....... B 3.2-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) . ... ...... .. . . . . . B 3.2-10 B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . . . . B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QFTR) .. . . B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters .. . . . B 3.2-28 B 3.3 Instrumentation . . . .. ... .... . B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instmmentation B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instmmentation . B 3.3-53 B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation . .. .. . . . B 3.3115 B 3.3.4 Remote Shutdown Workstation . . . . . . B 3.3-125 B 3.4 Reactor Coolant System (RCS) . ... ... B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . B 3.4-1 O
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| Section Title Page B 3.4.2 RCS Minimum Temperature for Criticality . . . . B 3.4-6 I B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . B 3.4-9 4 B 3.4.4 RCS Loops - Modes 1 and 2 . . . . . . . . . B 3.4-17 )
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| B 3.4.5 RCS Loops - Modes 3,4, and 5 . . . . . . . B 3.4-21 j B 3.4.6 Pressurizer . . . . . ... .. .. ... .. B 3.4-25 I B 3.4.7 Pressurizer Safety Valves . . . . . .... . . . . B 3.4-28 I B 3.4.8 RCS Operational Leakage . ... .. .. B 3.4-32 !
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| B 3.4.9 Minimum RCS Flow . . .... . . . B 3.4-38 I B 3.4.10 RCS Leakage Detection Instrumentation . .. B 3.4-41 B 3.4.11 RCS Specific Activity . . . . . .. ... . B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)- ;
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| Operating . . ... ... .... ..... . . B 3.4-50 B 3.4.13 Automatic Depressurization System (ADS)- ,
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| Shutdown, RCS Intact . . .... ... B 3.4-54 B 3.4.14 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Open . . . . .. . . . . . . B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection j (LTOP) System . . ... .. .. . . . . . B 3.4-60 l n B 3.5 Passive Core Cooling System (PXS) . . .. .. B 3.5-1 '
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| () B 3.5.1 Accumulators . . . . . . . . . . ... . . . . B 3.5- 1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . . . . . B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . ... ........ ... . . . B 3.5-15 B 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . . . . B 3.5-18 B 3.5.5 Passive Residual Heat Removal Heat Exchanger !
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| (PRHR HX) - Shutdown, RCS Intact . . . . B 3.5-24 B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating .. .... . . . B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory High . B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low ... .. . .... . . B 3.5-38 B 3.6 Containment Systems . ........ . . . B 3.6-1 i B 3.6.1 Containment . . . . . . B 3.6-1 )
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| B 3.6.2 Containment Air Locks .... . .. . . B 3.6-6 B 3.6.3 Containment Isolation Valves . . .. . . B 3.6-13 B 3.6.4 Containment Pressure .. ... ... . .. B 3.6-23 B 3.6.5 Containment Air Temperature . . . B 3.6-26 B 3.6.6 Passive Containment Cooling System
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| , (PCS) - Operating . .. . B 3.6-30
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| ( i N)
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| i Section Title Page !
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| B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown . . . . . .... ... . . . B 3.6-37 B 3.6.8 Containment Penetrations . . . . . . .. . B 3.6-40 B 3.6.9 pH Adjustment . . ........ ..... . . . B 3.6-47 B 3.7 Plant Systems . . . . . ... ...... .... .. . . . . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) .............. . . B 3.7-13 B 3.7.4 Secondary Specific Activity . .. . . . . B 3.7-18 B 3.7.5 Spent Fuel Pool Water Level . . .. . . . . B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability System . ..... . ... .. . . . . . . B 3.7-24 B 3.7.7 Startup Feedwater Isolation and Control Valves B 3.7-30 B 3.8 Electrical Power Systems ..... . .. . . . . B 3.8-1 B 3.8.1 DC Sources - Operating . . . . . . . . . . . ... B 3.8-1 B 3.8.2 DC Sources - Shutdown . . . . . . . . ....... B 3.8-11 B 3.8.3 Inveners - Operating . . . ... ... ...... B 3.8-15 B 3.8.4 Inveners - Shutdown . . . ..... ..... B 3.8-20 B 3.8.5 Distribution Systems - Operating . ..... B 3.8-24 B 3.8.6 Distribution Systems - Shutdown . .. . . . B 3.8.33 B 3.8.7 Battery Cell Parameters . .. ..... . . . . B 3.8-37 B 3.9 Refueling Operations . . . . . . . . . .. . ..... . . B 3.9-1 B 3.9.1 Boron Concentration . . . . . ... .. ... B 3.9-1 B 3.9.2 Unborated Water Source Flow Paths . . . . . B 3.9-5 B 3.9.3 Nuclear Instmmentation . . . . . . . . . . . . . B 3.9-8 B 3.9.4 Refueling Cavity Water Level . .. . . B 3.9-11 Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM .. . 16.2-1 16.2.1 Introduction .. . . ... . . . 16.2-1 16.2.2 Scope . ... . . . .. ... . 16.2-1 16.2.3 Design Considerations . .. ... . . . .... . . . . 16.2-1 16.2.4 Relationship to Other Administrative Programs . . . . . 16.2-2 16.2.5 The AP600 Design Organization . ... . . .. . .. . 16.2-2 16.2.6 Objective . . .... .. ... . . . . .. . 16.2-3 16.2.7 D-RAP, Phase I . . ...... . . .. .. .. .. 16.2-4 16.2.8 Combined License Activities - O-RAP .. . .. . .. 16.2-9 16.2.9 Glossary of Terms . . . .. . ... .. . .. . ... . 16.2-10 0
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| Revision: 10 December 20,1996 xxx 3 Westinghouse
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| 16.2.10 References . . . .... . . ....... ... . .... . . 16.2-11 I CHAPTER 17 QUALITY ASSURANCE . . . . . ......... .. . . ...... . . . . 17.1-1 17.1 Quality Assurance During the Design and Construction Phases . . . . . . . . . 17.1-1 17.2 Quality Assurance During the Operations Phase . . . . . ............. 17.1-1 17.3 Quality Assurance During Design, Procurement, Fabrication. Inspection :
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| and/or Testing of Nuclear Power Plant Items and Services . . . .... . . . . 17.1-1 !
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| 17.4 Combined License Information Items ..... .... .... ...... ... 17.1-2 17.5 References . .. .... ........ .. .. . .. ..... . . . 17.1-2 CHAPTER 18 HUMAN FACTORS ENGINEERING . . . . . . . .. . ........ ..... 18.1-1 18.1 Overview . . . .... .. ... .... . . . . . .... .. . 18.1-1 18.1.1 References . ........ .. .. . .. .. ... .. . . . . 18.1-4 18.2 Human Factors Engineering Program Management . .... .. ...... . 18.2-1 18.2.1 Human Factors Engineering Program Goals, Scope, j Assumptions, and Constraints . . . ....... ..... ....... . 18.2-1 18.2.2 Human System Interfaces Design Team and Organization ..... . 18.2-4 18.2.3 Human Factors Engineering Processes and Procedures . . .. 18.2-11 )
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| , 18.2.4 Human Fac: ors Engineering Issues Tracking . ............ . I8.2-17
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| ) 18.2.5 Human Factors Engineering Technical Programs and l Milestones . ......... .......... .. . ...... 18.2.18 l 18.2.6 Combined License Information . . . . .. .. ..... ... .... 18.2-19 18.2.7 References . . . . . . . . . . . . ..... ............ .. . . . 18.2-19 18.3 Operating Experience Review . . . . . ... . . . ...... . . 18.3-1 18.3.1 Combined License Information . . .. . . . ..... . . . 18.3-1 18.3.2 References . . ... .. ..... ... .. . .... .. . 18.3-1 18.4 Functional Requirements Analysis and Allocation . . .... ..... .. 18.4-1 18.4.1 Combined License Information . . . . . .. . ... .. . 18.4-2 18.4.2 References . . .. . ........ ...... .... . . . 18.4-2 18.5 AP600 Task Analysis Implementation Plan . . ... .. .. . 18.5-1 18.5.1 Task Analysis Scope . . ... . . ... . . .. . . I 8.5- I 18.5.2 Task Analysis Implementation Plan . .. . . 18.5-2 18.5.3 Job Design Factors . ... .. .. . ......... 18.5-5 18.5.4 Combined License Information Item . .. .. 18.5-5 18.5.5 References . .. . .... . ..... 18.5-5 18.6 Staffing . .. .. . .. . . . . . .. . I8.6-1 18.6.1 Combined License Information Item .. .. . . .. 18.6-1 l 18.6.2 References . . . ......... . .. . .. .. .. . 18.6-1 18.7 Integration of Human Reliability Analysis with Human Factors Engineering . 18.7-1 18.7.1 Combined License Information . . . . .. . .. .... . . 18.7-1 18.7.2 References . .. . ........ . . . .. .. . 18.7-1 18.8 Human System Interface Design . . . . . .. . .. 18.8-1 i
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| Section Title g 18.8.1 Implementation Plan for the Human System Interface Design . . 18.8-3 18.8.2 Safety Parameter Display System (SPDS) . ..... . . . 18.8-11 18.8.3 Operation and Control Centers . . ....... .. .. .. 18.8-16 18.8.4 Human Factors Design for the Non-Human-System Interface Portion of the Plant . . ..... .. .. . . . . 18.8-20 18.8.5 Combined License Information . . .. .. . . ... 18.8-23 18.8.6 References . ........... . . . ... . . ... . . . 18.8-23 18.9 Procedure Development . . . . . . .. . . . .. . . .. I8.9-1 18.9.1 Combined License Information . . . . . ..... ... 18.9-1 18.9.2 References . . . . . .. .. . . . . . ... . 18.9-1 18.10 Training Program Development . . . . . .. .. 18.10-1 18.10.1 Combined License Information . .. . . .. . 18.10-1 18.10.2 References . ...... .. . .. . .. . ... . . . 18.10-1 18.11 Haman System Interface Design Test Program . .. . .. . 18.11-1 18.11.1 Combined License Information . . . . ... .... .... . 18.11-2 18.11.2 References . ...... ... . . . . . . ..... 18.11-2 18.12 Displays, Alarms, and Controls . . ..... . . . . . .. I8.12-1 18.12.1 Inventory of Displays, Alarms, and Controls . . . . ... ... 18.12-1 18.12.2 Minimum Inventory of Main Control Room Fixed Displays, Alanns, and Controls .... .. . ... ..... .... 18.12-1 18.12.3 Remote Shutdown Workstation Displays, Alarms, and Controls . . . 18.12-7 18.12.4 Combined License Information .. . . ... ... . . .. I8.12-7 18.12.5 References . ......... . . . . . . . .. . .... . 18.12-8 O
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| Revision: 10 December 20,1996 xxxii W85tingh00S8
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| MASTER TABLE OF CONTENTS l
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| Section Title Pm J Volume 1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIFFION OF PLANT . . .. 1.1-1 1.1 Introduction . . . . . ....... . ... . . ... .. . ...... 1.1-1 1.1.1 Plant Location . . . . .. ...... ...... ... .. . ... .... 1.1-1 1.1.2 Containment Type ...... ... .... . .. .. .. . . . 1.1-1 1.1.3 Reactor Type . . . . . . . . . . . . . . . . .. . .... . . 1.1-1 1.1.4 Power Output . . . ..... . . ........ ... . .. . . . 1.1-1 1.1.5 Schedule . ......... ...... . .. ...... ...... . . 1.1-1 1.1.6 Format and Content ................. . ... . . . . .. . . .. . 1.1-2 1.1.7 Combined License Information . . ... . . .............. .. 1.1-3 1.2 General Plant Description . . . . ... .... ..... . . . .. ... . . . 1.2-1 1.2.1 Design Criteria, Opeating Characteristics, and Safety Considerations . 1.2-1 1.2.2 Site Description . . . . . .. . .... ........ . 1.2-15 1.2.3 Plant Arrangement Description . . . . . ... ...... . ... 1.2-16 1.2.4 Nuclear Island . . . ... ... ... .. ................ . 1.2-17 1.2.5 Annex Building . . . . ...... ... .. .. .. . ... .. . l.2-24 (q
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| 1.2.6 1.2.7 Diesel Generator Building . . . . . . .
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| Radwaste Building . . . . ..
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| ......... 1.2-25 1.2-26 1.2.8 Turbine Building . ... .......... .. . . . .... 1.2-26 1.2.9 Combined License Information . . . ... . .. ..... .... 1.2-27 7.3 Comparisons with Similar Facility Designs . . ......... .... . .. 1.3-1 1.4 Identification of Agents and Contractors .......... . ....... . . .. 1.4-1 1.4.1 Applicant - Program Manager ... ..... .. . .. ... . 1.4-1 1.4.2 Other Contractors and Participants . . . . . . . .............. . 1.4-1 1.4.3 Combined License Information . . . . . ... . .... ... .. 1.4-3 1.5 Requirements for Further Technical Information ... .. .. ... . 1.5-1 1.5.1 AP600 Safety-Related Tests ....... . . . . . .. . 1.5-1 1.5.2 AP600 Component Design Tests . .. . . . ...... .. . 1.5-7 1.5.3 Combined License Information . ... . ... . . . . . . 1.5 8 1.5.4 References . . . . . . . . . .... . .. .. ........ .. 1.5-8 1.6 Material Referenced . ... . ... . .. . . .... . . . 1.6-1 1.7 Drawings and Other Detailed Information .... ... .. .. . .... . . . 1.7-1 1.7.1 Electrical and Instrumentation and Control Drawings ..... . .. 1.7-1 1.7.2 Piping and Instrumentation Diagrams . . . ... . . . 1.7-1 1.7.3 Combined License Information . . . . .. . 1.7-1 1.8 Interfaces for Standard Design .... . . . .. . . . ..... . . . 1.8-1 1.9 Compliance with Regulatory Criteria ... . .. . .... . 1.9-1 1.9.1 Regulatory Guides . . . .. . .. .. ..... .. . 1.9-1 1.9.2 Compliance With Standard Review Plan (NUREG.0800) ..... . . 1.9-3 1.9.3 Three Mile Island Issues . . . . . . . . ... ... 1.9-3 A
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| b Revision: 10
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| Section Title Page 1.9.4 Unresolved Safety Issues and Generic Safety Issues . . . ... . 1.9-28 1.9.5 Advanced Light Water Reactor Certification Issues . . .. . . . 1.9-74 1.9.6 Combined License Information . ... .. ... ... ..... .. 1.9-107 1.9.7 References . . ..... . . . .... .. .. 1.9-108 APPENDIX 1 A CONFORMANCE WITH REGULATORY GUIDES . . . . .. . . 1 A-1 1 A.1 References . . . .. ....... . .. ... . . .... ...... I A-79 APPENDIX IB SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES . .. . 1B-1 1B.1 Introduction . . .... ... . . . .. ... .. . . . IB-1
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| ; IB.2 Summary .. .......... ... . .... . . .. . IB-1 IB.3 Selection of SAMDAS ... ..... . . . . . .. . 1B-2 l IB.4 Methodology . . . ..... ....... .. . . .. .. .. . ... . IB-2 IB.4.1 Risk Reduction .... . . . . ...... . .. . . . 1 B-2 1B.4.2 Capital Cost Estimates . . . . ........ . .. . . . IB-3 1B.4.3 Cost Benefit Analysis ... .. . . . . ... . . . 1B-3 1B.5 PRA Release Categories . . . . . . ... . ....... ..... . . . . 1 B-3 IB.5.1 Release Category OK . . . . . ..... . .... .. . . . 1B-4 IB.5.2 Release Category OKP . .. . ... ............ . .. . 1B-4 1B.5.3 Release Category CC .. .. .. .... ... . . . . . 1 B-5 1B.5.4 Release Category CI . . . . . . . .. .. . . . . 1B-5 1B.6 Total Population Dose . . . . . . ... . . . . . ................ 1B-5 1B.7 SAMDA Description and Benefit . .. . . .. .. . . .. . . . . . . I B-6 IB.7.1 Upgrade the CVCS for Small LOCAs . . . . . . 1B-6 IB.7.2 Filtered Vent . . . . . . ....... . ... . . . . . . I B-6 1B.7.3 Locate Normal RHR Inside Containment .... . . . . I B-7 1B.7.4 Self-Actuating Containment Isolation Valves . . . . . . .. . 1B-7 1B.7.5 Passive Containment Sprays .... .. .. . .. . . 1B-7 IB.7.6 Active High Pressure Safety Injection System . . . . 1B-7 ,
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| 1B.7.7 Steam Generator Shell-Side Heat Removal System . . . . . 1B-8 j IB.7.8 Direct Steam Generator Relief Flow to the IRWST . 1B-8 IB.7.9 Increased Steam Generator Pressure Capability . . . . IB-8 IB.7.10 Secondary Containment Filtered Ventilation . . . 1B-8 IB.7.11 Diversify the IRWST Discharge Valves . .. .. 1 B.9 1B.7.12 Ex-Vessel Core Catcher . . . . . . . . I B-9 ,
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| l 1B.7.13 High Pressure Containment Design . . ... . . . . IB-9 I i 1B.7.14 Increase Reliability of Diverse Actuation System ... . . 1B-9 l 1B.8 Results .. . .. .... ..... . .. . .. . . . . I B-9 1B.9 References . . . . . . . . .... . ... ... .... . . IB-11 )
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| Section Title Page CHAPTER 2 SITE CHARACTERISTICS ... ... ......... . .. . ..... .. 2-1 l 2.1 Geography and Demography ...... .. ...... . .. . . . . 2-1 !
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| 2.1.1 Combined License Information for Geography and Demography . 2-1 2.2 Nearby Industrial, Transportation and Military Facilities . . . .... . 2-1 2.2.1 Combined License Information for Identification of Site-specific Potential Hazards . .. ... . ... . ...... . 2-2 !
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| 2.3 Meteorology .. . .. ...... . . .. .. . . .. . 2-2 2.3.1 Regional Climatology . . . . . . . .. . .... 2-3 i
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| . 2.3.2 Local Meteorology . . . ... .... . .. . . . 2-3 2.3.3 Onsite Meteorological Measurement Programs . . . ...... . 2-3 2.3.4 Short-Term Diffusion Estimates .......... ... ... . 2-3 2.3.5 Long-Term Diffusion Estimates . . . ......... . .. . . 2-4 2.3.6 Combined Licensed Information . . . . ... .. . .... .. 2-4 2.4 Hydrologic Engineering . .. ... . . .. . .... .. 2-5 2.4.1 Combined License Information ... .... . ..... ... 2-5 2.5 Geology, Seismology, and Geotechnical Engineering . . . . ... . . 2-6 2.5.1 Basic Geological and Seismic Combined License Information . . .. 2-6 2.5.2 Vibratory Ground Motion . . ... ..... .. ........... 2-7 ,
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| /O 2.5.3 Surface Faulting Combined License Information . .. . . .. 2-7
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| () 2.5.4 Stability of Subsurface Materials and Foundations ... ... . 28 2.5.5 Combined License Information for Stability of Slopes .. .... . 2-12 2.5.6 Combined License Information for Embankments and Dams . . . . 2-13 2.5.7 References . . . . ... .. ... .. ..... .... ...... . 2-13 APPENDIX 2A DESIGN SOIL PROFILES .. . ... ... ....... . . . . . 2 A- 1 2A.1 Survey of a Selection of Existing Nuclear Power Plant Sites in the U.S. . . . 2A-1 2A.2 Generic Soil Profiles . . . .......... . . . . .. ... 2A-2 2A.3 Applicability of Design Ground Motion to Generic Soil Profiles . . . . .. . 2A-4 2A.4 Free-Field Site Response Analysis . . . . .... . . 2A-5 2A.5 2D Soil-Stmeture Interaction Analysis .. . .. . 2A-7 2A.6 AP600 Design Soil Profiles . . . . . .. 2A-12 2A.7 References ..... .. . . . . 2A-14 APPENDIX 2B PARAMETRIC STUDIES RELATED TO AP600 DESIGN SOIL PROFILES ... .. . ... . . 2B-1 2B.1 2D SSI Analysis Parameters and Procedures . . . . . . 2B-2 2B.I .1 Structural Models . .. . .. . .. 2B-2 2B.1.2 SASSI Foundation Models . ... ... . 2B-2 2B. l .3 Soil Properties for SSI Analysis ... . . .. . 2B-2 2B.I .4 Input Motion . ... . . . . . 2B-3 2B.I .5 Two-Dimensional Enveloped SSI Results .. .... . . . 2B-3
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| -, 2B.2 Design Soil Profiles .. . . . . 2B-3
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| : _- u Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page 2B.2.1 Lower Bound of Soft Soil Profile (V,=707 fps) . . . . . . . 2B-4 2B.2.2 Firm Rock Profiles (V,=3500 fps) . . ...... . .. .. 2B-4 2B.2.3 Parabolic Distribution of Soil Profile with Sandy Soil Material . 2B-5 2B.2.4 Variation of Soil Properties and 60 Percent Requirement of Free-Field Spectra at Foundation Level . ... . .. . 2B-5 2B.2.5 AP600 Design Soil Profiles . . .. . .. . . . . 2B-6 2B.3 Soil Profile Parametric Studies: . . . ... .. ....... . . . 2B-6 2B.3.1 Depth-to-Base Rock ..... .. . . .. . . . . . 2B-7 2B.3.2 Soil Curves for Clay Material . .. .. . .. . . . . 2B-7 2B.3.3 Poisson's Ratio for Soil above Water Table . . .. .. . . 2B-8 2B.3.4 Fixed-Base vs. SSI Analysis for the Hard Rock Site . . . . .. . 2B-8 2B.3.5 Idriss 1990 Soil Curves . . . . . . . .. . 2B-9 2B.3.5 Soil Densitys .. .. .. . . . . 2B-9 2B.4 References . .. . . . . ....... .. . .. . . .. 2B-9A Volume 2 APPENDIX 2C SEISMIC LATERAL EARTH PRESSURES .. .. . ..... .. . 2C-1 2C.1 2D SASSI Analysis for Seismic Lateral Earth Pressure ..... .. .. . 2C-1 2C.l .1 Analysis Method ... .. . . . . . .... . . 2C-1 2C.I.2 Stmetural Models . .. ....... . . .. .... ... . 2C-1 2C.I.3 SASSI Foundation Models . . . . . .... . .. .. . . 2C-1 2C. I .4 Representation of Adjacent Structures .. . ....... .. . . . 2C-2 2C.I .5 Input Motion . . . .. . .. . . .. ... . 2C-2 2C.I.6 Soil Properties . ....... . . ... . .. .... 2C-2 2C.I.7 2D SASSI Analyses Results . . . .. . . . . 2C-2 2C.2 Effect from Torsional Motion of the Nuclear Island . . .. .. . 2C-2 2C.3 Local Distribution of Lateral Earth Pressure . .. .. . . . 2C-3 2C.4 References . .. . . .. ... ... .. . 2C-4 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS .. . ...... . . .... ..... . . 3.1-1 3.1 Conformance With Nuclear Regulatory Commission General Design Criteria 3.1-1 3.1.1 Overall Requirements . .... . ... . . . 3.1-1 3.1.2 Protection by Multiple Fission Product BarTiers . . . 3.1-4 3.1.3 Protection and Reactivity Control Systems . 3.1-12 3.1.4 Fluid Systems . . ... .. . .... .... . 3.1-18 3.1.5 Reactor Containment . . . .. . . . 3.1-30 3.1.6 Fuel and Reactivity Control . . . . . . 3.1-34 3.1.7 Combined License Information . .. . . 3.1-37 3.1.8 References . . . . .. ... . . .. ... . . . 3.1-37 Revision: 10 December 20,1996 iv [ Westirigh00S8
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| Section Title Page 3.2 Classification of Structures, Components, and Systems . ..... . . . . 3.2-1 3.2.1 Seismic Classification . . . . . . . . . . .. ..... . .. . .. 3.2-1 3.2.2 AP600 Classification System . . . . . ... ... . . . . 3.2-3 3.2.3 Inspection Requirements . . .... . . . . ... .. 3.2-12 3.2.4 Application of AP600 Safety-Related Equipment and Seismic Classification System ...... . ... . . ..... . 3.2-13 3.2.5 Combined License Information . .. . . .. . 3.2-16 3.2.6 References . ... . . . .. . . . . . . . 3.2-17 3.3 Wind and Tornado Loadings . ... . .. .. . .. ..... . 3.3-1 3.3.1 Wind Loadings . .. .. .. . . . .. ... . . . ... 3.3-1 3.3.2 Tornado Loadings . . .. . . ... .. . . . .. . . 3.3-2 3.3.3 Combined License Information . . .... . . ... . . 3.3-4 3.3.4 Reference; . .. .... . . .. . . . . . .... 3.3-4 3.4 Water Level (Flood) Design .. ... .... . .. . . 3.4-1 3.4.1 Flood Protection .. . . . . . .... .. . . . 3.4-1 3.4.2 Analytical and Test Procedures . . . ... .. ..... . 3.4-24 3.4.3 Combined License Information . . .. . . . ... . 3.4-24 3.4.4 References . . .. . .... ...... ... . 3.4-24 3.5 Missile Protection . .... .... ..... . ... . . .. ... . 3.5-1 3.5.1 Missile Selection and Description . .... 3.5-4 (L') 3.5.2 Protection from Extemally Generated Missiles
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| .. . 3.5-13 3.5.3 Barrier Design Procedures . . . . . . .. ..... . . . . . 3.5-13 3.5.4 Combined License Information . . . .... . .... . 3.5-16 3.5.5 References ..... ....... . ........ . ... . 3.5-16 3.6 Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping . . . . . . . ..... . .. .. ... 3.6-1 3.6.1 Postulated Piping Failures in Fluid Systems Inside and Outside Containment .. .. .. ...... . . . ... . 3.6-2 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postula:ed Rupture of Piping . . 3.6-12 3.6.3 Leak-before-Break Evaluation Procedures . . .. . 3.6-31 3.6.4 Combined License Information . . .. . . . ... 3.6-38 3.6.5 References . . . . . .. . . . . . ... 3.6-38 3.7 Seismic Design . .. . . . ... ... 3.7-1 3.7.1 Seismic Input . .. .. . . . . . 3.7-1 3.7.2 Seismic System Analysis . . .. . . . .... . 3.7-6 3.7.3 Seismic Subsystem Analysis . . . .. . . . . . 3.7-20 3.7.4 Seismic Instrumentation .. .... . 3.7-46 l 3.7.5 Combined License Information . .. ... . 3.7-48 l 3.7.6 References . ... . .. . .. . 3.7-49 3.8 Design of Category I Structures . .. . ... ... . . 3.8-1 3.8.1 Concrete Containment .. . . .. . 3.8-1 3.8.2 Steel Containment . . . .. .. 3.8-1
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| 3.8.3 Concrete and Steel Internal Structures of Steel Containment ... . 3.8-16 3.8.4 Other Category I Structures .. . . . ... . 3.8-39 3.8.5 Foundations . . . . . ..... . . . .. .. . 3.8-53 i 3.8.6 Combined License Information . ... . .. 3.8-60 3.8.7 References ... .. ..... . .. ... ....... .. 3.8 60 Volume 3 3.9 Mechanical Systems and Components . . . . . . . . . . 3.9-1 3.9.1 Special Topics for Mechanical Components . . ... . ., . 3.9-1 3.9.2 Dynamic Testing and Analysis . . . ... .. .... . . 3.9-30 3.9.3 ASME Code Classes 1,2, and 3 Components, Component Supports, and Core Support Stmetures . . ... . . 3.9-45 3.9.4 Control Rod Drive System (CRDS) . ... .. . . . . . 3.9-71 3.9.5 Reactor Pressure Vessel Internals . . ... . . 3.9-82 3.9.6 Inservice Testing of Pumps and Valves . . . .. ... 3.9-89 3.9.7 Integrated Head Package . . . ... .. .... . ..... 3.9-97 3.9.8 Combined License Information . . . ... ..... .. . 3.9-102 3.9.9 References . . . . . . . . . . . . . . . .. .. .... ... . .. 3.9-103 3.10 Seismic and Dynamic Qualification of Seismic Category I Mechanical and Electrical Equipment .. . . ....... . ... ........ . . . . 3.10-1 3.10.1 Seismic and Dynamic Qualification Criteria ....... . . . 3.10-2 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Instmmentation, and Mechanical Components . .... ... 3.10-3 ;
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| 3.10.3 Method and Procedures for Qualifying Supports of Electrical l Equipment, Instrumentation, and Mechanical Components . . . 3.10-7 l 3.10.4 Documentation . ........... . ... ..... . . . 3.10-7 ;
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| 3.10.5 Standard Review Plan Evaluation . . . 3.10-7 l
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| 3.10.6 Combined License Information Item on Experienced-Based Qualification . . . . . .. .. .. . .. . . 3.10-8 ;
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| 3.10.7 References .. .. .. .... . . ... . . 3.10-8 l 3.11 Environmental Qualification of Mechanical and Electrical Equip' ment . . 3.11-1 3.11.1 Equipment Identification and Environmental Conditions . . . 3.11-1 3.11.2 Qualification Tests and Analysis . . . . .. 3.11-3 I 3.11.3 Loss of Ventilation . .... . . . .. . .. 3.11-4 3.11.4 Estimated Radiation and Chemical Environment . . . . 3.11-5 i 3.11.5 Combined License Information Item for Equipment Qualification File . . . . . . . . . . . . . . . . . . . . . . 3.11-5 3.11.6 References . ...... . . ... ... . ... . . 3.11-6 O
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| Section Title Pm APPENDIX 3A HVAC DUCTS AND DUCT SUPPORTS . . . ... . ... . . . . 3A-1 3A.1 Codes and Standards . . . ..... ...... .... ...... ... . . 3A-1 3A.2 Loads and Load Combinations .. ..... . .......... . . . . . 3A-1 3A.2.1 Loads . . ..... ......... . .... . ... .. . 3A-1 3A.2.2 Load Combinations .. ... . . ........ . .... . 3A-3 3A.3 Analysis and Design . . .. ...... . .. ......... . . . 3 A-3 3 A.3.1 Response Due to Seismic Loads . . . ..... .. . .. .. . . 3A-3 3A.3.2 Deflection Criteria . .. ... .. ... ..... .... .. 3A-3 l 3A.3.3 Relative Movement . . .. . ... .. ... ... . . . . 3A-3 {
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| 3A.3.4 Allowable Stresses . . . . .. .. . . . . . 3 A-4 3 A.3.5 Connections . ........ ... ...... .... ... . 3A-4 )
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| i APPENDIX 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP600 PIPING . 3B-1 3B.1 Leak-Before-Break Criteria for AP600 Piping . . ..... .. . . . 3B-2 3B.2 Potential Failure Mechanisms for AP600 Piping ........ ..... . 3B-2 3B.2.1 Erosion-Corrosion Induced Wall Thinning .. .... .. ..... . 3B-2 3B.2.2 Stress Corrosion Cracking .. ... . ... . ..... .. . 3B-3 3B.2.3 Water Hammer ....... .. ... .... . .... . . . . 3B-5 3B.2.4 Fatigue . .. ........ . .. . .... .. ..... . . . 3B-9 i
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| U 3B.2.5 Thermal Aging ..... . ...
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| 3B.2.6 Thermal Stratification . .. . ...
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| . 3B-9 3B-10 3B.2.7 Other Mechanisms . . . . . . . . .. . . . .... .. . 3B-13 3B.3 Leak-Before-Break Bounding Analysis . ... .... ...... ....... 3B-13 3B.3.1 Procedure for Stainless Steel Piping . ... .. ..... .. . . 3B-13 3B.3.2 Procedure for Non-Stainless Steel Piping .. ... ..... ..... 3B-16 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves . . . . 3B-17 3B.3.4 Bounding Analysis Results ....... . .. . .. ... . . 3B-21 3B.4 Differences in Leak-Before-Break Analysis for Stainless Steel and Ferritic Steel Pipe .. ...... .... . .. .... . . 3B-21 3B.5 Differences in Inspection Criteria for Class 1,2, and 3 Systems . . . ..... 3B-21 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping . . . . . . . . . .. . . 3B-21 3B.7 Monitoring of Unanticipated Dynamic Loads in the Feedwater Lines .. . 3B-21 A 3B.8 Augmented In. Service Inspection of the Main Feedwater Nozzles Connected to the Steam Generators . ... . . . 3B-21 A 3B.9 References . . . . . . . . . .. . . 3B-21 A APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS . . .. . 3C-1 3C.1 Reactor Coolant Loop Model Description . . . . . . . 3C-1 3C.I .1 Steam Generator Model . . . . . . ... . . . 3C-1 3C.I .2 Reactor Coolant Pump Model . . . . 3C-2 3C. I .3 Reactor Pressure Vessel Model . .. . .. .. . 3C-2
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| Section Title Page 3C.1.4 Containment Interior Building Structure Model . . . . . .. . . . 3C-3 3C.I.5 Reactor Coolant Loop Piping Model .. .. . .. ... ..... . 3C-3 l 3C.2 Design Requirements . ....... ..... .. . . ..... .. . 3C-3 l 3C.? Static Analyses . . . .. . . .... ... ... .. . . . 3C-4 3C.3.1 Deadweight Analysis . . . ..... . ... .. . . . . 3C-4 1
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| 3C.3.2 Intemal Pressure Analysis .. . . . ......... 3C-4 3C.3.3 Thermal Expansion Analysis . . . . . ... . . .. 3C-4 3C.4 Seismic Analyses .. ........ .. .. ...... . . . .. .. . 3C-4 3C.5 Reactor Coolant Loop Piping Stresses . . . . . . . . ... . . . . .... 3C-5 3C.6 Description of Computer Programs . . . . . . . .. . . . . . . . . 3 C-5 APPENDIX 3D METHODOLOGY FOR QUALIFYING AP600 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT . . ..... .... 3D-1 3D.1 Purpose .... .. . .. . .. . .... . . . .. ...... .. . 3D-2 3D.2 Scope. ..... .... . . ... .. .... . ... . . . . . . . 3D-2 I 3D.3 Introduction . . . . . . . . . . ..... .. . . ... ... .. . . . 3D-3 3D.4 Qualification Criteria . . . . .... . ... . . . . ....... ... ... 3D-3 3D.4.1 Qualification Guides . ... .... . . ... .. .... . . . . 3D-3 '
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| 3D.4.2 Definitions . . .. . ...... .. . .. . . ........ . 3D-7 1 3D.4.3 Mild versus Harsh Environments . . . . . . ........ . . . 3D-7 3D.4.4 Test Sequence .. .... .... ... . . ... . . . 3D-8 3D.4.5 Aging . . . . . . . .. . ... .. ......... . . . 3D-9 i 3D.4.6 Operability Time .... . ..... . . . . . . .... . . 3D-12 I
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| 3D.4.7 Performance Criterion . . . . ... . . . . . . . 3D-12 l 3D.4.8 Margin .. .. . . .... . . . .. 3D-12 3D.4.9 Treatment of Failures . . . . . . . . . . . . . 3D-15 3D.4.10 Traceability . . ... . . . .. . ... .. . 3D-16 3D.5 Design Specifications . . . . . . . .. .. 3D-17 3D.5.1 Normal Operating Conditions .. . .... ... 3D-18 3D.5.2 Abnormal Operating Conditions . . .. ... . . . 3D-19 3D.5.3 Seismic Events . . . ... . . .... . . 3D-20 3D.5.4 Containment Test Environment .. .. .. . . . . .. . 3D-20 3D.5.5 Design Basis Event Conditions . . . .. .. . . 3D-20 3D.6 Qualification Methods . . . . . . .. . .. . . 3D-24 3D.6.1 Type Test . . .. .. . . .. . . . . 3D-25 3D.6.2 Analysis .... . . . . . . . ... ... 3D-25 3D.6.3 Operating Experience . . . .. 3D-30 3D.6.4 On. Going Qualification . . . . . . . 3D-30 3D.6.5 Combinations of Methods . . .. . . .. .. . . 3D-30 0
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| 3D.7 Documentation . ................ . .. . ... ..... . . . . 3D-31 1
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| 3D.7.1 Equipment Qualification Data Package . .. ......... . . 3D-32 3D.7.2 Specifications . . .... .... ...... . . .. .. .. 3D-32 3D.7.3 Qualification Program .. . .. . ...... ...... . 3D-34 3D.7.4 Qualification by Test . . ..... . . ..... ..... . 3D-34 3D.7.5 Qualification by Analysis . .. . ... . ...... . . 3D-37 I 3D.7.6 Qualification by Experience . . . .. . .. . .. . . . 3D-37 l 3D.7.7 Qualification Program Conclusions . .. ..... ... ....... 3D-37 l 3D.7.8 Combined License Information . . . ... .......... . 3D-38 3D.8 References . . ... . ..... . .. . . . .. . .. 3D-38 Appendix 3D-Attachment A - Sample Equipment Qualification Data Package . . . . 3D-69 Appendix 3D-Attachment B - Aging Evaluation Program . . ..... .. . . 3D-87 B.1 Introduction ..... ... .. ......... . . ... . . 3D-87 i B.2 Objectives . .... . . . . . . . .... . .. .. 3D-87 l B.3 Basic Approach . .... ..... .. ...... ..... . 3D-87 l B.4 Subprogram A . ...... . ... . .. .. . .. .. .. . . . 3D-88 l
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| (] B.4.1 Scope ....... ... .... . . . ... .. . . . . . . . . . 3D-88 {
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| C/ B.4.2 Aging Mechanisms . ..... .. ... . .... .... ... . 3D-88 l B.4.3 Time ......... .. ... . .. ... . . .. . . 3D-88 l B.4.4 Operational Stresses . . ...... ... . ............ . . . . 3D-89 B.4.5 External stresses . ...... .. .... . ....... . . . 3D-89 l B.4.6 Synergism . ... . .... ..... ... .... .... . 3D-91 B.4.7 Design Basis Event Testing .. . . ..... . .. .. . . 3D-91 B.4.8 Aging Sequence . . ........ . ... .. . .... .. . 3D-91 B.4.9 Performance Criterion . . . .. . . . . 3D-91 B.4.10 Failure Treatment .... . .... . . . 3D-91 B.5 Subprogram B . .... .. .. ... .. .... . . . 3D-92 B.5.1 Scope . .... . .. . .. .. .. . . . 3D-93 B.S.2 Performance Criteria .. ... ... . .. . . 3D-93 B.5.3 Failure Treatment . .. . . . . . . . 3D-93 Appendix 3D-Attachment C - Effects of Gamma Radiation Doses Below 10' Rads on the Mechanical Properties of Materials . . . . 3D-96 C.1 Introduction . . . . .... . . . 3D-96 C.2 Scope. .. . . . . . . . . 3D-97 C.3 Discussion . . . . . . 3D-97 C.4 Conclusions . ...... .. .. 3D-98 C.5 References . ... ... ... . . . 3D-98 73
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| Appendix 3D-Attachment D - Accelerated Thermal Aging Parameters . . .... .... .. 3D-103 D.1 Introduction . ... .. ..... .. . ... ... . ... . . . . . 3D-103 D.2 - Arrhenius Model . ... ...... .. .. . ... . . . 3D-103 D.3 Activation Energy . . . . . . .. . . . . .. .. ... . 3D-105 D.4 Thermal Aging (Normal / Abnormal Operating Conditions) . .. . . 3D-106 D.4.1 Normal Operation Temperature . .. . . .. . .. . 3D-106 D.4.2 Accelerated Aging Temperature . . . . . . . . 3D-107 D.4.3 Examples of Arrhenius Calculations . . . .. .. . 3D-107 D.5 Post-Accident Thermal Aging . . . . . . . . . .. .. ... . . . . . 3D-108 D.5.1 Post-Accident Operating Temperatures . . . ..... .. ... . 3D-108 D.5.2 Accelerated Thermal Aging Parameters for Post-Accident Conditions . .. ... . . .. . .. .... . 3D-109 D.6 References .. .. .... . ... . . . ... 3D-109 Appendix 3D-Attachment E - Seismic Qualification Techniques ... . 3D-115 E.1 Purpose . .... ..... .... ....... . .. . . ... ... 3D-Il5 E.2 Definitions .. ...... . . .... .. . . . .. .. ... . . 3D-Il5 E.2.1 1/2 Safe Shutdown Eanhquake . . . . .. ........ . 3D-115 E.2.2 Seismic Category I Equipment . .. . . .. .. . 3D-115 E.2.3 Active Equipment . . . . . ... ... . ... ... ... . 3D-Il5 E.2.4 Passive Equipment . . .. . ... . ..... . . . 3D-115 E.3 Qualification Methods .. ....... ... .. .. . .. . . . 3D-Il6 E.3.1 Use of Qualification by Testing . . . .. . . ... . . .. . 3D-116 E.3.2 Use of Qualification by Analysis .. .. .. . ... . . . 3D-116 E.4 Requirements . . ... .. .......... ... . . .... 3D-Il7 E.4.1 Damping .... ... . .. . . . ... .. .. .. 3D-Il7 E.4.2 Intenace Requirements . . . .. . .. ... 3D-117 E.4.3 Mounting Simulation . . . . . . .. ... . . 3D-Il8 E.4.4 1/2 Safe Shutdown Earthquake .. . . . .. 3D-118 E.4.5 Safe Shutdown Earthquake . . .... . .. . . ... 3D-118 E.4.6 Other Dynamic Loads . . . .. . .. .. . . 3D-118 E.5 Qualification by Test . .. . .. . .. . .. .... 3D-118 E.5.1 Qualification of Hard-Mounted Equipment .. . .. . . 3D-119 E.5.2 Qualification of Line-Mounted Equipment .. ... .. 3D-120 E.5.3 Operational Conditions .. .... .. . . .. . . 3D-122 E.5.4 Resonant Search Testing . . . . .. . . . . .. 3D-123 E.6 Qualification by Analysis . . . . . .... . .. . ....... . .... 3D-123 E.6.1 Modeling . . .. .... ... . ... ... . . 3D-124 E.6.2 Qualification by Static Analysis . . . . . . 3D-124 E.6.3 Qualification by Dynamic Analysis . . .. . . . . . 3D-124 O
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| E.7 Performance Criteria . . . . . . ... . .. . . ... . ... . 3D-126 E.7.1 Equipment Qualification by Test . . ... ....... . . . . . 3D-126 E.7.2 Equipmot Qualification by Analysis ... ............. . 3D-126 APPENDIX 3'E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND .. ... .. . 3E-1 APPENDIX 3F CABLE TRAYS AND CABLE TRAY SUPPORTS . . .. . . . 3F-1 3F.1 Codes and Standards .. . .. ... ... . .. ..... . 3F-1 3F.2 Loads and Load Combinations .. .. . . .. ... .... . . 3F-1 3F.2.1 Loads ... ....... . ...... . . ..... .... . .. 3F-1 3F.2.2 Load Combinations .. ....... . . . . . .. . 3F-2 3F.3 Analysis and Design . . . . . .......... . .. . . .. . 3F-2 3F.3.1 Damping ... .... ... . . .. .. ... 3F-2 3F.3.2 Seismic Analysis . .... .. .. . . . .. .. . 3F-3 3F.3.3 Allowable Stresses .. .. ... . . . ..... . . 3F-3 3F.3.4 Connections . . . .. .. . ... . . .... . . 3F-3 CHAPTER 4 REACTOR.. .. . ... .. ... . .. .. . 4.1-1 73 4.1 Summary Description . .. . .... . ... . .. ...... 4.1-1 Q
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| 4.1.1 Combined License Information ... ... . . ... 4.1-4 4.1.2 References . . . . ..... .. ..... . ... . . 4.1-4 4.2 Fuel System Design . ...... ......... . .. .... .. . 4.2-1 4.2.; Design Basis . . . . ... ... . .... . .. . ... . 4.2-2 4.2.2 Description and Design Drawings . . . ... . .... . 4.2-9 4.2.3 Design Evaluation . . .. ...... . .. ..... .... 4.2-20 4.2.4 Testing and Inspection Plan . . . . . . .. .. .... . . .. . 4.2-32 4.2.5 Combined License Information . . ... . .. . ... . 4.2-37 4.2.6 References . . . . ... ..... .... ....... 4.2-37 4.3 Nuclear Design .. ... . .... . ... .. ......... ... 4.3-1 4.3.2 Description .. . . .. .. .. . . .... . .. . 4.3-7 4.3.3 Analytical Methods . .. . . . ... .. . . 4.3-39 4.3.4 Combined License Information . . . . ....... ... . 4.3-42 4.3.5 References . . . . . .... .. . .... . . . . 4.3-42 4.4 Thermal and Hydraulic Design . ....... . . . .. . . . . .. . 4.4-1 4.4.1 Design Basis . . . .... .. .. . . .. . . 4.4-1 i 4.4.2 Description of'Itermal and Hydraulic Design of the Reactor Core . . . 4.4-4 4.4.3 Descrijai::n .-f av Thermal and Hydraulic Design of the Reactor Coolant Sysw.a ..... .... .. .. .. . . . 4.4-201 4.4.4 Evaluation ..... .. . .. .. .... . .. . .. 4.4-21 4.4.5 Testing and Verification .... .. .. . . . 4.4-30 4.4.6 Instrumentation Requirements ... . . .. . . . 4.4-31 4.4.7 Combined License Information . . ... . .. . . .. .. . 4.4-35 i
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| 4.4.8 References . . ... . ... .. .. .. . . . . . . 4.4-35 4.5 Reactor Materials ..... . .. .. ... . . . . .. 4.5-1 4.5.1 Control Rod and Drive System Structural Materials .. .. . 4.5-1 4.5.2 Reactor Internal and Core Support Materials .. . 4.5-3 4.5.3 Combined License Information . . ...... . . .. ... 4.5-4 4.5.4 References . . .. ... .. .. .. . . ... .. 4.5-4 4.6 Functional Design of Reactivity Control Systems .... . ... .. . 4.6-1 4.6.1 Information for Control Rod Drive System . . .... .. . . 4.6-1 4.6.2 Evaluations of the Control Rod Drive System . .. .... ..... 4.6-1 4.6.3 Testing and Verification of the Control Rod Drive System . . ..... 4.6-2 4.6.4 Information for Combined Performance of Reactivity Systems .. 4.6-2 4.6.5 Evaluation of Combined Performance .. .. . . 4.6-3 4.6.6 Combined License Information . . .. . . .. . 4.6-4 Volume 4 CHAI'I'ER 5 PEACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS .. 5.1-1 5.1 Summary Description ..... . .. .. . ... . ...... . 5.1-1 5.1.1 Design Bases . . . . . . .. . .. . . .. . . ... . . 5.1-1 5.1.2 Design Description ..... . . . .. . .. . .. 5.1-2 5.1.3 System Components . . . . . .. .... ... . .... .. 5.1-4 5.1.4 System Performance Characteristics . ... . . . . f.1-7 5.1.5 Combined License Information . . . . . . . . .. . .. 5.1-9 5.2 Integrity of Reactor Coolant Pressure Boundary .. . .. . 5.2-1 5.2.1 Compliance with Codes and Code Cases . ..... .. . 5.2-1 5.2.2 Overpressure Protection . ...... . . . . . 5.2-2 5.2.3 Reactor Coolant Pressure Boundary Materials ... ... 5.2-7 ,
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| 5.2.4 Inservice Inspection and Testing of Class 1 Components . . . 5.2-17 j 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary . 5.2-20 l 5.2.6 Combined License Information Items . .... .. . . 5.2-29 5.2.7 References . . .... . .. .... . . ... . . 5.2-29 5.3 Reactor Vessel . .... . ......... .... ... .. . 5.3-1 ,
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| l 5.3.1 Reactor Vessel Design .. .. ...... . ... 5.3-1 :
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| 5.3.2 Reactor Vessel Materials . . . .. . . .. .. 5.3-4 !
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| 5.3.3 Pressure-Temperature Limits ... .. ... .. 5.3-13 I 5.3.4 Reactor Vessel Integrity .... . . .. . .. . 5.3-14 l 5.3.5 Combined License Information . . ... ...... . . 5.3-19 ;
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| 5.3.6 References . . ..... . ... ... . .. .. . . 5.3-20 l 5.4 Component and Subsystem Design . . . . . .. .. 5.4-1 l 5.4.1 Reactor Coolant Pump Assembly . .. . . . . . 5.4-1 0
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| ' Revision: 10 l December 20,1996 xij [ W85tkigh00Se .
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| Section Title P_a.ge 5.4.2 Steam Generators ... . . .. .. ... .... 5.4-10 5.4.3 Reactor Coolant System Piping .. . . .. . . . . 5.4-23 5.4.4 Main Steam Line Flow Restriction . . . .. . . 5.4-28 5.4.5 Pressurizer ... . . . .. . . . . .. . . 5.4-29 5.4.6 Automatic Depressurization System Valves .. . . .. . . 5.4-36 5.4.7 Normal Residual Heat Removal System . . .. . . .. . 5.4-38 5.4.8 Valves . ........ . . .. . ... .... . 5.4-51 5.4.9 Reactor Coolant System Pressure Relief Devices ...... . . . 5.4-57 5.4.10 Component Supports . . ..... . . . .. .. . 5.4-60 5.4.11 Pressurizer Relief Discharge . .. .... .. . .. . 5.4-63 5.4.12 Reactor Coolant System High Point Vents . . .... .. 5.4-65 5.4.13 Core Makeup Tank . . . . . .. .. ... .. . .. . 5.4-68 5.4.14 Passive Residual Heat Removal Heat Exchanger . .. . . 5.4-71 5.4.15 Combined License Information . . . . . . . . . . . . . 5.4-74 5.4.16 References ........... ... . . ... ..... . 5.4-74 CHAPTER 6 ENGINEERED SAFETY FEATURES .. . . . ..... . 6.0-1 6.1 Engineered Safety Features Materials .. . . . . . ..... 6.1-1 79 6.1.1 Metallic Materials . .. . . . ...... ... 6.1-1 (j 6.1.2 Organic Materials . . ... .. . .. . . ... . . 6.1-5 6.1.3 Combined License Information Items . . . . . .... . 6.1-11 6.1.4 References . . . . ..... ... . .. .. 6.1-12 6.2 Containment Systems . ... . .. . . . .. . 6.2-1 6.2.1 Containment Functional Design . . . . . . . 6.2-1 6.2.2 Passive Containment Cooling System . . . .. . 6.2-20 6.2.3 Containment Isolation System ..... . . .. . . 6.2-28 6.2.4 Containment Hydrogen Control System . . . . . . . . 6.2-378 6.2.5 Containment Leak Rate Test System . . . . .... . . 6.2-48 6.2.6 References ....... ... . . . . ... ... . . 6.2-55 6.3 Passive Core Cooling System .... . ... . .. . 6.3-1 ;
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| 6.3.1 Design Basis . 6.3-2 j
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| 6.3.2 System Design . ... . . ... .... .... . 6.3-6 ,
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| 6.3.3 Performance Evaluation . . . 6.3-28 l
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| 6.3.4 Post-72 Hour Actions . . . . ... ... .. . 6.3-41 1 6.3.5 Limits on System Parameters ... . .. . . 6.3-41 6.3.6 Inspection and Testing Requirements . . . ... . ..... 6.3-42 {
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| 6.3.7 Instrumentation Requirements .. . . .. .. . . 6.3-43 i 6.3.8 Combined License Information . . . . ..... . 6.3-48 I 6.3.9 References . . . . .. . .. .. .. . . 6.3-48 l 6.4 Habitability Systems . . . . .. . .. .. . . . . 6.4-1 6.4.1 Safety Design Basis .. .. .... . . . . . . 6.4-1 6.4.2 System Description .. .. . . .. . ... 6.4-2 6.4.3 System Operation . . . . . ... 6.4-6 m
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| V 1 Revision: 10 W Westingh0uS8 x ii December 20,1996
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| .X l Master Table of Contents MASTER TABLE OF CONTENTS (Cont.) j Section Title h 6.4.4 System Safety Evaluation . .. .. ... . . . .. . 6.4-8 6.4.5 Inservice Inspection / Inservice Testing . ..... ... . . . . 6.4-10 6.4.6 Instrumentation Requirements .. ...... ... . . . . 6.4-10 6.4.7 Combined License Information . . .. . .. .. . 6.4-11 6.4.8 References ..... .... ... ..... .. . .. . . . 6.4-11 6.5 Fission Product Removal and Control Systems . . . .......... .. . . 6.5-1 6.5.1 Engineered Safety Feature (ESF) Filter Systems . . ....... . . 6.5-1 6.5.2 Containment Spray System .. .. . . . .. . . .. .. . 6.5-1 6.5.3 Fission Product Control Systems . .... ... . 65-1 6.5.4 Combined License Information . . . . .. . . . . 6..t-2 6.6 Inservice Inspection of Class 2 and 3 Components . . .. .. ...... .... 6.6-1 6.6.1 Components Subject to Examination . ....... . . . . 6.6-1 6.6.2 Accessibility .. ... .. .. .. .. . .. . .... . 6.6-1 6.6.3 Examination Techniques and Procedures ..... .. .. . 6.6-2 6.6.4 Inspection Intervals . . .. . . .... . . ..... ..... . . 6.6-3 6.6.5 Examination Categories and Requirements . . ... . ... ... . 6.6-3 6.6.6 Evaluation of Examination Results . . ... . . ... ... 6.6-3 6.6.7 System Pressure Tests . .. .... . . ... . ... . . 6.6-3 6.6.8 Augmented Inservice Inspection to Protect against Postulated Piping Failures . .. ... . .. . ... . .. . .. 6.6-3 6.6.9 Combined License Information Items . . .. .. . . . 6.6-4 CHAPTER 7 INSTRUMENTATION AND CONTROLS . . . . .. . ... 7.1-1 7.1 Introduction . ..... . ... .... . ...... ... ... 7.1-1 7.1.1 The AP600 Instmmentation and Control Architecture . ... . 7.1-2 7.1.2 General Protection Subsystem Configuration . . . . .. .. . 7.1-6 7.1.3 Plant Control System .... .. . .... . ... . . 7.1-27 7.1.4 Identification of Safety Criteria . . . ... . . ...... . 7.1-32 7.1.5 AP600 Protective Functions . . ..... .. ... 7.1-48 7.1.6 Combined License Information . ........ .. . . . 7.1-48 7.1.7 References . . ......... . . . . .... . .. ... . 7.1-49 7.2 Reactor Trip . . .. . .. . .. ... .. . .. . 7.2-1 7.2.1 Description . .. ... . . . ..... . .. . 7.2-14 7.2.2 Analyses . . . . ...... . . ........... .... . 7.2-14 7.2.3 Combined License Information .. . ... .. . 7.2-17 7.2.4 References . .. ........ . ... .. .... . .. 7.2-17 7.3 Engineered Safety Features . . . .... ... . .... .... .. . 7.3-1 7.3.1 Description ... . ....... . ..... .. . ... .. . 7.3-1 7.3.2 Analysis for Engineered Safety Features Actuation . . . .. .... 7.3 19 7.3.3 Combined License Information . . . . . ... . . 7.3-22 7.4 Systems Required for Safe Shutdown .. .. .. . . .. . . 7.4-1 O
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| Revision: 10 December 20,1996 xiy [ Westingh00S8
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| l Section Title P_ age 7.4.1 Safe Shutdown . . . . . .. .. . ..... . . ........ . . . 7.4-3 7.4.2 Safe Shutdown Systerns . .. ... . ....... .... . 7.4-10 7.4.3 Safe Shutdown from Outside the Main Control Room . . .... .. 7.4-11 7.4.4 Combined License Information . . . . . ... . .. .... . 7.4-14 7.4.5 References ... ... .. ... .. . .... . . . 7.4-14 7.5 Safety-Related Display Information . . . .. . . .. . .. . .. 7.5-1 I 7.5.1 Introduction . . . . . ..... . . .. .... ... . .. .. 7.5-1 i 7.5.2 Variable Classifications and Requirements . .... . . . . 7.5-1 i 7.5.3 Description of Variables ....... . . .... . .. . . . 7.5-9 7.5.4 Processing and Display Equipment ... .. ... ... ... . 7.5-11 1
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| 7.5.5 Combined License Information . . . . . . ..... .... . 7.5-13 7.6 Interlock Systems Important to Safety . . .. . ... . . ... . ... 7.6-1 l 7.6.1 Prevention of Overpressurization of Low-Pressure Systems .. 7.6-1 l 7.6.2 Availability of Engineered Safety Features . ... . . .... 7.6-2 7.6.3 Combined License Information . . . . . . .. .. .. .. 7.6-5 7.7 Control and Instrumentation Systems . . . .. . . ... . 7.7-1 7.7.1 Description .. . .. . ... . . .... ... 7.7-2 7.7.2 Analysis . . ... ... .. . .. . . . . . . 7.7-20 t i rm! 7.7.3 Combined License Information . . . .. . . . . . 7.7-21 I v i Volume 5 l
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| CHAPTER 8 ELECTRIC POWER .. ... .. . . .. .. .. . ... . . . . . 8.1-1 8.1 Introduction . ... ... ..... . . . .... . . 8.1-1 l 8.1.1 Utility Grid Description . .. ... .. . . . .. .. . 8.1-1 8.1.2 Onsite Power System Description . . . . . ... .. 8.1-1 8.1.3 Safety-Related Loads . .. .. . .. . ... .. 8.1-2 8.1.4 Design Basis . . . . . .. . ... . . . . 8.1-2 8.1.5 Combined License Information . . .. . . . . ... . 8.1-5 l 8.2 Offsite Power System . . . . . . . . .. . . . .... 8.2-1 8.2.1 System Description . . ...... . . . 8.2-1 8.2.2 Conformance to Criteria .. . . ..... . .... 8.2-2 i 8.2.3 Standards and Guides .. . ... . ... .. . 8.2-2 l 8.2.4 Combined License Information for Offsite Electrical Power . . . . . 8.2-2 l 8.2.5 References . . . . . . . .... .. . ..... 8.2-2 l 8.3 Onsite Power Systems . . . . . . . . . ... . 8.3-1 l 8.3.1 AC Power Systems .. . . . .. . .. . . .. . 8.3-11 l 8.3.2 DC Power Systems . . . . . . . . ...... . ... . 8.3-13 8.3.3 Combined License Information for Onsite Electrical Power . . 8.3-21 8.3.4 References . .... ... .. . . 8.3-22
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| Section Title Pm CHAPTER 9 AUXILIARY SYSTEMS ..... ... . . . .. . ...... . . 9.1-1 9.1 Fuel Storage and Handling .... ... . . ....... .. . 9.1-1 9.1.1 New Fuel Storage . . . . . . . . .. . . ..... .. .... .. . 9.1-1 9.1.2 Spent Fuel Storage ... .. ... . . .. .... . 9.1-5 9.1.3 Spent Fuel Pool Cooling System . . . . ... . 9.1-10 9.1.4 Light Load Handling System (Related to Refueling) . .. . 9.1-21 9.1.5 Overhead Heavy Load Handling Systems .... .. .... .. 9.1-34 9.1.6 Combined License Information for Fuel Storage Handling . . . 9.1-40 9.1.7 References . . . . ... ..... . ... . .... .. . . 9.1-40 9.2 Water Systems . . . . ... . . ..... .. . ....... .. . 9.2-1 9.2.1 Service Water System ..... . . . . . .... .. 9.2-1 9.2.2 Component Cooling Water System ... .. ... .... . .. . 9.2-7 9.2.3 Demineralized Water Treatment System . . ... ..... . 9.2-16 9.2.4 Demineralized Water Transfer and Storage System . .. .. 9.2-20 9.2.5 Potable Water System .... . . .. .. ... . . 9.2-25 9.2.6 Sanitary Drainage System . . . . .... . ... . . . . . . . 9.2-28 9.2.7 Central Chilled Water System .. .. . . .... . . . . 9.2-30 9.2.8 Turbine Building Closed Cooling Water System . . .. . . . 9.2-36 9.2.9 Waste Water System . ..... ..... . . 9.2-40 9.2.10 Hot Water Heating System .... . . . . ..... . . 9.2-44 9.2.11 Combined License Information . . . . .. ...... .. . . 9.2-47 9.2.12 References .. . .. . . .. .... . . 9.2-48 9.3 Process Auxiliaries .. .. . .. . . . . ....... . . 9.3-1 9.3.1 Compressed and Instrument Air System ... ...... ...... . 9.3-1 9.3.2 Plant Gas System . .. . .... . .... .... . .. 9.3-7 9.3.3 Primary Sampling System . . .. . .. ....... . . . 9.3-10 9.3.4 Secondary Sampling System .... . .. .. . . . . . ... . . 9.3-15 j 9.3.5 Equipment and Floor Drainage Systems . . . . . . 9.3-17 !
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| 9.3.6 Chemical and Volume Control System . ... . . .. .. 9.3-22 i 9.3.7 Combined License Information .. . .. ... . 9.3-43 l 9.3.8 References .. .... .... . .. .... . . . 9.3-43 Volume 6 i 9.4 Air-Conditioning, Heating, Cooling, and Ventilation System ......... . . 9.4-1 9.4.1 Nuclear Island Nonradioactive Ventilation System ... ... . . 9.4-1 9.4.2 Annex / Auxiliary Buildings Nonradioactive HVAC System .. 9.4-15 9.4.3 Radiologically Controlled Area Ventilation System .. ... . 9.4-26 9.4.4 Balance-of-Plant Interface . . . . . . ..... .. . .. 9.4-36 9.4.5 Engineered Safety Features Ventilation System . . . . 9.4-36 !
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| Oll Revision: 10 December 20,1996 xvi [ Westinghouse
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| Section Title P_gge 9.4.6 Containment Recirculation Cooling System . .... ... .. . . . 9.4-36 9.4.7 Containment Air Filtration System . ... . ... ...... . . 9.4-41 !
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| 9.4.8 Radwaste Building HVAC System . . .. .... ... . . . . . . . 9.4-49 I
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| 9.4.9 Turbine Building Ventilation System . ..... . .... . .. 9.4-54 9.4.10 Diesel Generator Building Heating and Ventilation System .. 9.4-59 l 9.4.11 Health Physics and Hot Machine Shop HVAC System ... 9.4-65 j 9.4.12 Combined License Information . ... . . . . 9.4-70 '
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| 9.4.13 References . . . .. . .. . ....... .. . 9.4-70 1 9.5 Other Auxiliary Systems . . . . . . . ... .. . . ... ... . 9.5-1 ;
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| 9.5.1 Fire Protection System ... . .... .... .. . . 9.5-1 1 9.5.2 Communication System ... .. . .. .. . . . . 9.5-14 9.5.3 Plant Lighting System . . ... .. . . ... ....... . . 9.5-18 ,
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| 9.5.4 Standby Diesel and Auxiliary Boiler Fuel Oil System ... . . . . . 9.5-21 9.5.5 References . . . . . . ... ... . . .. .. . . . 9.5-27 APPENDIX 9A FIRE PROTECTION ANALYSIS . .. . .... ... 9A-1 9A.1 Introduction . . . . . . . . ... . . . . . .. ... 9A-1 9A.2 Fire Protection Analysis Methodology . . . . . 9A-1 (N
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| 9A.2.1 Fire Area Description . . . . . . .
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| 9A.2.2 Combustible Material Survey . . .
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| . 9A-1
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| . 9A-2 9A.2.3 Fire Severity Categorization . . . . ...... .. ... . . 9A-2 9A.2.4 Combustible Loading and Equivalent Fire Duration !
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| Calculations . . . . . . .... ...... .. . ... .,. . . 9A-2 9A.2.5 Fire Protection Adequacy ..... . ...... . . 9A-3 9A.2.6 Fire Protection System Integrity . . ... . . . .. .. .. 9A-4 9A.2.7 Safe Shutdown Evaluation . .. . . 9A-4 9A.3 Fire Protection Analysis Results ... . .
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| . .. . 9A-8
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| 9A.3.1 Nuclear Island . . . . . . . . . . . 9A-9 9A.3.2 Turbine Building . .... .. . . . . . .. . 9A-61 9A.3.3 Yard Area And Outlying Buildings . . . . . . . 9A-72 9A.3.4 Annex I and II Buildings . . .. .. . . .. 9A-72 9A.3.5 Radwaste Building . . .. .... . . . . . . . . 9A-88 i 9A.3.6 Diesel Generator Building . . . . .. . . . . 9A-90 9A.3.7 Special Topics .. ... . . . . . .. . . 9A-94 ,
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| 9A.4 References . .. . . . .. .. . 9A-97 I Volume 7 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM . .. .. . .. 10.1-1 10.1 Summary Description ... ... . . . . 10.1-1 10.1.1 General Descriptionn . . . ... .. .. . 10.1-1 10.1.2 Protective Features .. . .. . 10.1-2 Q,/ i Revision: 10
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| Section Title Page 10.1.3 Combined License Information on Erosion-Corrosion Monitoring . . . 10.1-4 10.2 Turbine-Generator . . .. . ... .. . ... .. .. . . 10.2-1 10.2.1 Design Basis .. . ... . . .. . .. . .. 10.2 1 10.2.2 System Description . . . . .. . . .. .. ... . 10.2-1 10.2.3 Turbine Rotor Integrity . .. . . . .. .. .. ... 10.2-11 10.2.4 Evaluation .. .. . . . ... ..... . ..... ..... 10.2-17 10.2.5 Instrumentation Applications . . . . .. ... 10.2-17 10.2.6 Combined License Information on Turbine Maintenance and Inspection . . . . . . . . . .... .. .. . . 10.2-19 10.2.7 References . . . . . . .. .... . ... . . . . .... .. 10.2-19 10.3 Main Steam Supply System . . . . .... . . . . ..... . 10.3-1 10.3.1 Design Basis . .. ..... . ... . . . . 10.3-1 10.3.2 System Description . .. . . . . . . .. . 10.3-4 10.3.3 Safety Evaluation . . . . .. ..... .. . . 10.3-10 10.3.4 Inspection and Testing Requirements . . 10.3-12 10.3.5 Water Chemistry . ... . .. . 10.3-12 10.3.6 Steam and Feedwater System Materials . . .. . . . . 10.3-16 10.3.7 Combined License Information ... . . . . . 10.3-17 10.3.8 References ...... . ...... .. . .. .. . .. .. 10.3-17 l 10.4 Other Features of Steam and Power Conversion System . .. . . . . 10.4-1 10.4.1 Main Condensers . . ...... . . . . 10.4-1 10.4.2 Main Condenser Evacuation System . . . .. . .. .. . 10.4-4 10.4.3 Gland Seal System . . . . . . . .... . . ..... . . 10.4-6 )
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| 10.4.4 Turbine Bypass System . . .. . . . .. . 10.4-8 j 10.4.5 Circulating Water System . . . ... .... 10.4-12 1 10.4.6 Condensate Polishing System . . . . . .. . .. . . . . . 10.4-17 I 10.4.7 Condensate and Feedwater Systems . .... .... . 10.4 20 l 10.4.8 Steam Generator Blowdown System . .... . . ... 10.4-35 l 10.4.9 Startup Feedwater System . . ... . . . .. 10.4-44 10.4.10 Auxiliary Steam System .. . .. .. . .. 10.4-53 10.4.11 Turbine Island Chemical Feed . . . . 10.4-56 j 10.4.12 Combined License Information . . ... . . ... 10.4-59 10.4.13 References . . . ... . . . . .. .. . 10.4-59 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT . . . . .. ... . 11.1-1 11.1 Source Terms . . ... .. .. .. ..... . ... . . I1.1-1 11.1.1 Design Basis Reactor Coolant Activity . . . . . .... . I1.1-1 11.1.2 Design Basis Secondary Coolant Activity . .. . . . . I1.1-3 11.1.3 Realistic Reactor Coolant and Secondary Coolant Actisity .. 11.1-4 11.1.4 Core Source Term . . . .. .. .. . . ... . . 11.1-4 O
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| Resision: 10 December 20,1996 xviii W85tingh00S8
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| Section Title Page 11.1.5 Process Leakage Sources . . . .. ... ... 11.1-4 11.1.6 Combined License Information . .. . .. .. ..... 11.1-4 11.1.7 References . . . ... .. . ... . . . . .... . I1.1-5 11.2 Liquid Waste Management Systems . . ... .. .. ... 11.2-1 11.2.1 Design Basis . ... . .... .. . .... .. .... I1.2-1 !
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| 11.2.2 System Description .. .. .... . .. .. . .. . . . 11.2-6 l 11.2.3 Radioactive Releases .. ..... ... ... .. . . .. 11.2-18 j 11.2.4 Combined License Information . . . . .. . . . .. .... . 11.2-20 11.2.5 References ...... .. . . . .. ... . .... . 11.2-20 11.3 Gaseous Waste Management System . .... . . . .... . 11.3-1 11.3.1 Design Basis . . .. .. . .... ... .. . . . . 11.3-1 11.3.2 System Description . . . . ... ... . . .... . 11.3-4 11.3.3 Radioactive Releases ... . . . .. . . . . 11.3-9 11.3.4 Combined License Information . . . . . .. .. . 11.3-11 l 11.3.5 References . .... . . . ... . ... . .. . . . . 11.3-11 11.4 Solid Waste Management .. . . . ... .... ... . 11.4-1 l 11.4.1 Design Basis .. . . .. ... . . .. .... . . . I1.4-1 11.4.2 System Description . .. . . . . 11.4-3 I (3 11.4.3 System Safety Evaluation . . ... . . . . .. . . 11.4-13
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| ( l1.4.4 Tests and Inspections .... ... . ... . . .. I1.4-13 11.4.5 Quality Assurance . . . . ... . .. . . . .. . 11.4-13 11.4.6 Combined License Information for Solid Waste Management System Process Control Program . . .... ... ... . ..... I1.4-13 11.4.7 References ... . ... . .. ... ..... . I1.4-14 11.5 Radiation Monitoring . ... . . . ... ... . ... . . . 11.5-1 11.5.1 Design Basis . . . ... . . . ... .......... .. . I1.5-1 11.5.2 System Description . . .... ... . ... .. . . I1.5-2 11.5.3 Effluent Monitoring and Sampling . . ... . . . .. I1.5-13 11.5.4 Process and Airborne Monitoring and Sampling .... . . ... 11.5-13 11.5.5 Post-Accident Radiation Monitoring . . . . . .... I1.5-14 11.5.6 Area Radiation Monitors ...... .... .. . .. . . . I1.5-14 11.5.7 Combined License Information . . . . . ... . 11.5-17 CHAPTER 12 RADIATION PROTECTION . .. . . . .. .. .. . 12.1-1 12.1 Assuring that Occupational Radiation Exposures are As-Low-As-Reasonably Achievable (ALARA) . . .. . . 12.1-1 12.1.1 Po: icy Considerations . . . . . . ... .. . .. 12.1-1 12.1.2 Design Considerations . .. .. ... . 12.1-2 12.1.3 Combined License Information . . . . . .. . . . . . . . . 12.1-6 12.2 Radiation Sources . . . . . .. . .. .. . . . . .. . . . 12.2-1 12.2.1 Contained Sources ... ...... ... . . . . . 12.2-1 12.2.2 Airborne Radioactive Material Sources . . . . 12.2-6 I i Revision: 10
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| [' WBStingt10USS xix December 20,1996
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| m- Master Table of Contents l
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| l MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Pace 12.2.3 Combined License Information . . . . .... ... . . 12.2-8 12.2.4 References . . . . . . . . . .. . ........ . . . 12.2-8 12.3 - Radiation Protection Design Features . . . .. . . .. .. . .. . 12.3-1 12.3.1 Facility Design Features .. . .. . . . 12.3-1 12.3.2 Shielding . . . . . ..... .. .... . . ... .. . .. . 12.3-9 12.3.3 Ventilation .. ...... ... .. . .. . .. 12.3-15 12.3.4 Area Radiation and Airbome Radioactivity Monitoring Instrumentation . . . . .. .... . . . . . . . . . 12.3-19 12.3.5 Combined License Information . . . .. .. . . . . 12.3-19 12.3.6 References ...... ..... .. .. . . . .. . . . 12.3-19 12.4 Dose Assessment . . .. . .... . ... ..... . .. . 12.4-1 12.4.1 Occupational Radiation Exposure . . ... .... .... . 12.4-1 12.4.2 Radiation Exposure at the Site Boundary . .- ... . 12.4-4 12.4.3 Combined License Information . . . . .... . ... . . . . 12.4-4 12.5 Health Physics Facilities Design . . ... . ... ... . . 12.5-1 12.5.1 Objectives . . .. .. . ... . . .... . 12.5-1 12.5.2 Equipment, Instrumentation, and Facilities . . . . . ...... 12.5-1 12.5.3 Other Design Features . ... . . .. ... . 12.5-3 12.5.4 Controlling Access and Stay Time . . .. .. . . 12.5-4 12.5.5 Combined License Information . . . ...... .. 12.5-5 Volume 8 CHAPTER 13 CONDUCT OF OPERATION . . ..... . .. . . . . . . .. 13-1 13.1 Organizational Structure of Applicant .. ... . . . . .... 1 13.1.1 Combined License Information Item . .. ... . . . 13-1 13.2 Training . . . . . .... . . . ... . .. . 13-1 13.2.1 Combined License Information Item .. . . . 13-1 13.3 Emergency Planning .. .. . ... . ... 13-1 l 13.3.1 Combined License Information Item . . . 13-2 13.4 Operational Review ...... .... . . .. . 13-2 13.4.1 Combined License Information Item . ... . . . 13-2 13.5 Plant Procedures . . . . ..... .. . . . . .. 13-2 13.5.1 Administrative Procedures . .. . . . .. 13-2 13.6 Industrial Security . . ... .. . . ...... .. 13-3 13.6.1 Preliminary Planning . .. . . .... ... . . . . 13 3 13.6.2 Security Plan . .. . . .. . . . .. . . 13-3 13.6.3 Plant Protection System .. . ..... . 13-3 13.6.4 Physical Security Organization .. . . .. . 13-5 13.6.5 Physical Barriers . .... . . 13-5 9
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| l Section Title ,Page 13.6.6 Access Requirements . .... . .... ... ... ... 13-6 13.6.7 Detection Aids . ... ... .. . .... . . .... 13-7 13.6.8 Se:urity Lighting . . . . .. . .... . .. . .. 13-7 i' 13.6.9 Security Power Supply System . . . . ...... ...... . 13-7 13.6.10 Communications . . .. .. . ... .... . .. .... . 13-7 13.6.11 Testing and Maintenance . . . .. .. .. .. . . 13-8 I 13.6.12 Response Requirements . ... . . . ...... 13-8 l 13.6.13 Combined License Information Item . ... . ... . . .... 13-8 13.7 References . . ........ ......... . . . . . . . 13-8 CHAFTER 14 INITIAL TEST PROGRAM . . . . ... . . . . . . 14.1-1 i 14.1 Specific Information to be Included in Preliminary / Final Safety i Analysis Reports .... . .... .. . .... . .... .. .... . 14.1-1 14.2 Specific Information to be Included in Standard Safety Analysis Reports . . . 14.2-1 !
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| 14.2.1 Summary of Test Program and Objectives ... .. . . . 14.2-1 !
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| 14.2.2 Organization, Staffing, and Responsibilities . . .... . . . 14.2-4 14.2.3 Test Specifications and Test Procedures . ... ... . . 14.2-4 14.2.4 Compliance of Test Program with Regulatory Guides ... . ... 14.2-6 ,
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| 14.2.5 Utilization of Reactor Operating and Testing Experience in the i d(~x Development of Test Program . .... . . . . ... 14.2-6 l 14.2.6 Use of Plant Operating and Emergency Procedures . . . 14.2-6 14.2.7 Initial Fuel Loading and Initial Criticality . . . .. . . . 14.2-7 14.2.8 Test Program Schedule . . .... .. . . .. .... 14.2-10 1 14.2.9 Preoperational Test Descriptions . . . . . . . . . ..... . . ... 14.2-10 14.2.10 Startup Test Procedures ..... ... ... .... . .. 14.2-80 14.3 Certified Design Material . . . . ....... . ... . ... .. 14.3-1 14.3.1 CDM Section 1.0, Introduction ... . .. . . 14.3-2 14.3.2 CDM Section 2.0, System Based Design Descriptions and ITAAC . . . .. .. . . . .. .. . 14.3-3 l
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| 14.3.3 CDM Section 3.0, Non-System Based Design Descriptions and ITAAC .. . . ... .... .. . . 14.3-9 14.3.4 Certified Design Material Section, 4.0 Interface Requirements . 14.3-10 14.3.5 CDM Section 5.0, Site Parameters . . . .. . . .. . . . 14.3-10 14.3.6 Initial Test Program . . . . . . . . . . 14.3-10 14.3.7 Summary . .... . .. . . .. . . . .. 14.3-11 14.3.8 References . . . . .. . . . . . . . 14.3-11 14.4 Combined License Applicant Responsibilities . . . . . .. 14.4-1 14.4.1 Organization and Staffing . . . . .. . . . 14.4-1 14.4.2 Test Specifications and Procedures . . . . 14.4-1 14.4.3 Conduct of Test Program . . .. . . . 14.4-1 14.4.4 Review and Evaluation of Test Results . . . . . 14.4-1 v)
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| l Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page CHAPTER 15 ACCIDENT ANALYSES . . .. ... .. ... ... . .. . 15.0-1 15.0.1 Classification of Plant Conditions . . . ... .. . .. ... . 15.0-1 15.0.2 . Optimization of Control Systems . .... .......... ... ... . . 15.0-5 15.0.3 Plant Characteristics and Initial Conditions Assumed in the Accident Analyses . . . . .. .. ... . .. .. . . . . 15.0-5 15.0.4 Reactivity Coefficients Assumed in the Accident Analysis . . . .. 15.0-7 15.0.5 Rod Cluster Control Assembly Insertion Characteristics . . .. .. . . 15.0-7 15.0.6 Trip Points and Time Delays to Trip Assumed in Accident Analyses . . 15.0-8 15.0.7 Instrumentation Drift and Calorimetric Errors, Power Range Neutron Flux . . 15.0-9 15.0.8 Plant Systems and Components Available for Mitigation of Accident Effects . 15.0-9 15.0.9 Fission Product Inventories . . . . . .... ......... ... .. 15.0-10 15.0.10 Residual Decay Heat . .. ... . . . . . .... . . . 15.0-10 15.0.11 Computer Codes Utilized . . . .. . . . . . .. .. ... 15.0-11 15.0.12 Component Failures . . . .. ... . . . . ...... .. 15.0-13 15.0.13 Operator Actions . ..... ..... . . .. .. . .. .... . 15.0-14 15.0.14 Combined License Information . . . . .. . . . . . . 15.0-14 15.0.15 References . . . . . . . . . . . . . . . .. . . . ........ . . . 15.0-14 -
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| 15.1 Increase in Heat Removal from the Primary System . .. .. . . . . 15.1-1 15.1.1 Feedwater System Malfunctions that Result in a Decrease in Feedwater Temperature ... . ... . . .... .... 15.1-1 15.1.2 Feedwater System Malfunctions that Result in an Increase in Feedwater Flow . . .. ..... ... .. . 15.1-3 15.1.3 Excessive Increase in Secondary Steam Flow . .. ... . . . 15.1-5 15.1.4 Inadvertent Opening of a Steam Generator Relief or Safety Valve . 15.1-8 15.1.5 Steam System Piping Failure . . ... ... . .. .. ... . 15.1-11 15.1.6 Inadvertent Operation of the Passive Residual Heat Removal Heat Exchanger . . . . ... . ...... . . 15.1-20 15.1.7 Combined License Information . . . . . .. . 15.1-24 15.1.8 References .... . .. ... .. . . . . . 15.1-24 15.2 Decrease in Heat Removal by the Secondary System . . . . 15.2-1 15.2.1 Steam Pressure Regulator Malfunction or Failure that Results in Decreasing Steam Flow . .. . . ... ... . . . 15.2-1 15.2.2 Loss of External Electrical Load . . . .... ... 15.2-1 15.2.3 Turbine Trip . . ... ..... . . . . . . 15.2-3 15.2.4 Inadvertent Closure of Main Steam Isolation Valves . . .. . 15.2-7 15.2.5 Loss of Condenser Vacuum and Other Events Resulting in 15.2.6 Loss of ac Power to the Plant Auxiliaries . .. .. ... 15.2-8 15.2.7 Loss of Normal Feedwater Flow . .. ... . . . . . 15.2-12 15.2.8 Feedwater System Pipe Break . . . .. . 15.2-16 15.2.9 Combined License Information . ... . 15.2-21 O
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| l Section Title P, a_ge 15.2.10 References . . . .. . . . . . .... . . . 15.2-21 15.3 Decrease in Reactor Coolant System Flow Rate . .. . .... . . 15.3-1 15.3.1 Panial Loss of Forced Reactor Coolant Flow . . . .. . ... 15.3-1 ;
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| 15.3.2 Complete Loss of Forced Reactor Coolant Flow . .. . . . . 15.3-3 !
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| 15.3.3 Reactor Coolant Pump Shaft Seizure (Locked Rotor) . .. .. . . 15.3-5 15.3.4 Reactor Coolant Pump Shaft Break . .. ...... . 15.3-10 15.3.5 Combined License Information . . . . .... . .. .. 15.3-10 j 15.3.6 References . . ....... . . . .. .... ..... . 15.3-11 {
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| 15.4 Reactivity and Power Distribution Anomalies . . .... ... . . .. . 15.4-1 -
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| 15.4.1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Suberitical or Low-Power Startup Condition . . .. . . 15.4-1 15.4.2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal 15.4.3 R Cluster Control ss bly Misalignment (System I Malfunction or Operator Error) . . ...... . 15.4-11 l 15.4.4 Startup of an Inactive Reactor Coolant Pump at an Incorrect l
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| Temperature . . . . . . . . . ...... .. .. 15.4-17
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| {
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| 15.4.5 A Malfunction or Failure of the Flow Controller in a Boiling 1 7 Water Reactor Loop that Results in an Increased Reactor (3) Coolant Flow Rate . . . . .
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| 15.4.6 Chemical and Volume Control System Malfunction That
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| . ... ... . 15.4-19 !
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| Results in a Decrease in the Boron Concentration in the Reactor Coolant . . . ....... . . . .. ..... . . 15.4-19 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position . . . . . .. . . . . ..... .. . 15.4-25 15.4.8 Spectrum of Rod Cluster Control Assembly Ejection Accidents 15.4-28 15.4.9 Combined License Information . ...... .. . .. 15.4-39 15.4.10 References . . . ... .. . .. . .... . . 15.4-39 Volume 9 15.5 Increase in Reactor Coolant Inventory . . .. . . . 15.5-1 15.5.1 Inadvertent Operation of the Core Makeup Tar.ks (CMT) During Power Operation . . . . ... . . . . . 15.5-1 15.5.2 Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory . .... . 15.5-4 15.5.3 Boiling Water Reactor Transients . . . .... . 15.5-8 15.5.4 Combined License Information . . . . . . 15.5-8 15.5.5 References . . . ... . . . . ... . . . . 15.5-8 15.6 Decrease in Reactor Coolant Inventory . .. . . . 15.6-1 15.6.1 Inadvertent Opening of a Pressurizer Safety Valve or Inadvertent Operation of the ADS . .. . 15.6-1 U
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| i i MASTER TABLE OF CONTENTS (Cont.) l l Section Title Page 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment . . . . . . .... ... . ... ... . ... . 15.6-4 15.6.3 Steam Generator Tube Rupture ... ....... .. . .. . 15.6-5 15.6.4 Spectrum of BWR Steam System Piping Failures Outside of Containment . . . ........ ... . ... . 15.6-15 15.6.5 Loss of Coolant Accidents Resulting from a Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary . ... . . .. . . . 15.6-15 15.6.6 References ... .. . .. .... .. . . .. .. . 15.6-64 15.7 Radioactive Release From a Subsystem or Component .... . . . 15.7-1 15.7.1 Gas Waste Management System Leak or Failure .. .... . 15.7-1 15.7.2 Liquid Waste Management System Leak or Failure (Atmospheric Release) ... . . .. . . . . .. . .. . . 15.7-1 15.7.3 Release of Radioactivity to the Environment Due to a Liquid Tank Failure . ... .. . . ... . . ... . . 15.7-1 15.7.4 Fuel Handling Accident . . . . .. . . 15.7-1 15.7.5 Spent Fuel Cask Drop Accident . . . . . . 15.7-6 15.7.6 Combined License Information . . . .. . . . . . 15.7-6 15.7.7 References .... . . ... . . . . 15.7-7 15.8 Anticipated Transients without Scram . .. ... .... 15.8-1 15.8.1 General Background ...... .. ... ... . . . . 15.8-1 15.8.2 Anticipated Transients without Scram in the AP600 . . . ... .. . 15.8-1 15.8.3 Conclusion . . .. . . .. . . .. . . ... 15.8-1 15.8.4 Combined License Information . . . . ... . . 15.8-1 15.8.5 References . .. . . ... .. ... . . . . .... . 15.8-1 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS .. . 15A-1 15A.1 Offsite Dose Calculation Models . . . .. .. 15A-1 15 A.I .1 Immersion Dose Models ... . . . . 15A-1 15A.l.2 Inhalation Dose (Committed Effective Dose Equivalent) . 15A-2 15A.I.3 Total Dose (Total Effective Dose Equivalent) . . .. . 15A-2 15A.2 Main Control Room Dose Models .... . .. . . .. . 15A-2 15A.2.1 Immersion Dose Models . . . . . 15A-2 15A.2.2 Inhalation Dose . .. .. . . .. .... ... 15A-4 15A.2.3 Total Dose (Total Effective Dose Equivalent) .. . 15A-4 15A.3 General Analysis Parameters . .... . . .. .. . . .. . 15A-4 15A.3.1 Source Terms . . . . .. .. ...... . . 15A-4 15A.3.2 Nuclide Parameters . . . . . . . . . 15A-6 15A.3.3 Atmospheric Dispersion Factors . . . .. . 15A-6 15A.4 References .. . . . . . ... 15 A-6 9
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| Y./ MASTER TABLE OF CONTENTS (Cont.)
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| i Section Title P_ age Volume 10 I CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS ..... .. .. ..... ....... . 16.1-1 16.1.1 Introduction to Technical Specifications . .. . ... ..... 16.1-1 1.0 Use and Application . ... . . . . .. . .. 1.1-1 1.1 Definitions . . . . ... . .. . . . 1.1-1 1.2 Logical Connectors . . . . . . ... . . 1.2-1 l 1.3 Completion Times . . ... ... . . .. ... . . 1.3-1 l 1.4 Frequency . ..... ... .. ........... ... . 1.4-1 1 2.0 Safety Limits (SLs) . . ... . . .. ... ... .. .... 2.0-1 2.1 SLs . .. .. .. . ... .. ... ... . .. . 2.0-1 2.2 SL Violations . ... .... ..... ... .. .. . 2.0-1 ;
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| 3.0 Limiting Conditions for Operation (LCO) Applicability .. .. 3.0-1 !
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| 3.0 Surveillance Requirement (SR) Applicability ... . ... 3.0-4 l 3.1 Reactivity Control Systems . . .. ... . ... .. . 3.1-1 l 3.1.1 Shutdown Margin (SDM) . .. . ... . . . 3.1-1 3.1.2 Core Reactivity . . . . . . .. . .. 3.1-2 f's 3.1.3 Moderator Temperature Coefficient (MTC) . . . ..... 3.1-4
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| \js 3.1.4 Rod Group Alignment Limits ..... . . . . 3.1-6 l 3.1.5 Shutdown Bank Insertion Limits . . . .. . .. .... . 3.1-11 i 3.1.6 Control Bank Insertion Limits . . ... .. . . . 3.1-13 3.1.7 Rod Position Indication . . . ...... ... . . 3.1-16 i 3.'s.8 Physics Tests Exceptions - Mode 2 . . . .. . . . . 3.1-18 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves .. ... 3.1-20 3.2 Power Distribution Limits . . ... . ..... . .. . 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fn (Z))
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| (Fo Methodology) . . ... . .. . . . 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) . . ... ... . .. . .. . . 3.2-5 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . . ... . . 3.2-8 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . ... . . 3.2-10 3.2.5 OPDMS-Monitored Power Distribution Parameters . . . .. . . . .. 3.2-14 3.3 Instmmentation . . . . . . . .. .. .. 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation . . . 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation ... . . . 3.3-17 3.3.3 Post Accident Monitoring (PAM)Instmmentation . 3.3-45 g- 3.3.4 Remote Shutdown Workstation . . 3.3-48 (y
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| Revision: 10 W8Sdl%rh0US8 xxy December 20,1996
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| . -- r Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_ age I
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| 3.4 Reactor Coolant System (RCS) . . ..... . . . . 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Depanure from Nucleate Boiling (DNB) Limits . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . ... . 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . 3.4-4 I 3.4.4 RCS Loops - Modes 1 and 2 . . . .. .. .... 3.4-6 3.4.5 RCS Loops - Modes 3,4, and 5 . . .. .. . .... 3.4-7 3.4.6 Pressurizer . ... . . .. . . . . . . . . 3.4-9 3.4.7 Pressurizer Safety Valves . . .. .. . .... . . 3.4-10 3.4.8 RCS Operational Leakage . ... 3.4-12 3.4.9 Minimum RCS Flow ...... . . .. . 3.4-14 3.4.10 RCS Leakage Detection Instrumentation . . .. .. ... 3.4-15 3.4.11 RCS Specific Activity . . . . . .. .. . ... ... 3.4-18 3.4.12 Automatic Depressurization System (ADS)- Operating 3.4-20 3.4.13 Automatic Depressurization System (ADS)- Shutdown, RCS Intact . .. ..... .. .. . . 3.4-22 3.4.14 Automatic Depressurization System (ADS) - Shutdown, RCS Open . . . . . . .. .. . . ..... .. 3.4-24 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . .. . . .. . . 3.4-26 3.5 Passive Core Cooling System (PXS) . . ... .. . . 3.5-1 3.5.1 Accumulators . . . ... . .. . . 3.5-1 3.5.2 Core Makeup Tanks (CMT) - Operating . ...... 3.5-4 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . 3.5-7 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating . . ..... . . . . . 3.5-9 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact . . . .... . 3.5-11 3.5.6 In-containment Refueling Water Storage Tank (IRWST) -
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| Operating .... . ... .. ... 3.5-13 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory High . . .. . . 3.5-16 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -
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| Shutdown, RCS Inventory Low . . . . . 3.5-18 3.6 Containment Systems . . . . .. .. . 3.6-1 3.6.1 Containment ..... . . ... . .. . 3.6-1 3.6.2 Containment Air Locks .. .. . .. . 3.6-3 3.6.3 Containment Isolation Valves . .. . . . 3.6-7 3.6.4 Containment Pressure ... . . 3.6-12 3.6.5 Containment Air Temperature . . .. ... . . 3.6-13 O
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| Revision: 10 December 20,1996 xxvi [ W85tingh00S8
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| 't MASTER TABLE OF CONTENTS (Cont.)
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| Section Title Page.
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| 3.6.6 Passive Containment Cooling System (PCS) - Operation . 3.6-14 3.6.7 Passive Containmi.nt Cooling System (PCS) - Shutdown . 3.6-17 3.6.8 Containment Penetrations . . ... . .......... . 3.6-19 3.6.9 pH Adjustment . .. ..... . .. .... . 3.6-22 3.7 Plant Systems .. . . . .. .. ... . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) .... .. . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . ... .. .. 3.7-5 3.7.3 Main Feedwater Isolation and Control Valves (MFIV and MFCV) . . ..... . .. ... .. . 3.7-7 3.7.4 Secondary Specific Activity . . . . . ....... . . 3.7-9 3.7.5 Spent Fuel Pool Water Level . .. .... .. .. . . 3.7-10 3.7.6 Main Control Room Habitability System (VES) . . . . . . 3.7-11 3.7.7 Startup Feedwater Isolation and Control Valves . . 3.7-15 3.8 Electrical Power Systems . . . .. . .... . . 3.8-1 3.8.1 DC Sources - Operating . . .... ... .. . 3.8-1 3.8.2 DC Sources - Shutdown . .. .. ..... 3.8-5 3.8.3 Inverters - Operating . . . . ... . ... .. . . 3.8-7 3.8.4 Inverters - Shutdown . . . .. . . . . . . . . 3.8-9
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| (] 3.8.5 Distribution Systems - Operating . ... . .. . . . 3.8-11
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| \s 3.8.6 Distribution Systems - Shutdown .. . ... ..... 3.8-13 3.8.7 Battery Cell Parameters ... . .. . . . .... 3.8-15 3.9 Refueling Operations .... .. . . . . ... .. . 3.9-1 3.9.1 Boron Concentration . . . .. .. .......... . . 3.9-1 3.9.2 Unborated Water Source Flow Paths ... ....... 3.9-2 3.9.3 Nuclear Instrumentation . .. .... . 3.9-4 3.9.4 Refueling Cavity Water Level . . . .. .. . . ... 3.9-6 4.0 Design Features .. . . .. . . ... ... . 4.0-1 4.1 Site . . . .. .. . . ... . . ... . 4.0-1 4.1.1 Site and Exclusion Boundaries .... . .. . 4.0-1 4.1.2 Low Population Zone (LPZ) . . . . . .. . 4.0-1 4.2 Reactor Core .... ... . .. . .. ... . . 4.0-1 4.2.1 Fuel Assemblies ... .. .. ..... . . .. 4.0-1 4.2.2 Control Rod and Gray Rod Assemblies . . ... .. 4.0-1 4.3 Fuel Storage . . . . . . . .. . . 4.0-2 4.3.1 Criticality . . .. . . . . ... 4.0-2 4.3.2 Drainage .. . . . .. .. . 4.0-2 4.3.3 Capacity . . . ....... . . . . . . .. 4.0-2 4.4 Hydrogen Control .. . . . .. . . . . 4.0-3 4.4.1 Passive Autocatalytic Recombiners (PARS) 4.0-3 5.0 Administrative Controls . .. . . . . . 5.0-1 5.1 Responsibility . . . .. . . . .... . ... 5.0-1 5.2 Organization . . . . ... . . . . . 5.0-2 i
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| ,~Q ,l Revision: 10 Westingt10USB xxvii December 20,1996
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| l Master Table of Contents H-MASTER TABLE OF CONTENTS (Cont.)
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| Section Title a Eage 5.3 Unit Staff Qualifications . . ... .. .... . . 5.0-5 5.4 Procedures . ...... . .. .... . 5.0-6 5.5 Programs and Manuals . . . . ... . .. .... 5.0-7 5.6 Reporting Requirements .... . .. . .. . 5.0-15 B 2.0 Safety Limits (SLs) . ... .. . . .. . .. .. B 2.0-1 B 2.1.1 Reactor Core Safety Limits (SLs) .. . B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL . . B 2.0-6 B 3.0 Limiting Conditions for Operation (LCO) Applicability . . . B 3.0-1 B 3.0 Surveillance Requirement (SR) Applicability . . . ..... B 3.0-12 B 3.1 Reactivity Control Systems . . . . . ... . . . . B 3.1-1 B 3.1.1 Shutdown Margin (SDM) . . ........ . B 3.1-1 B 3.1.2 Core Reactivity . . . . . . .. .. . ... B.3.1-7 B 3.1.3 Moderator Temperature Coefficient (MTC) . . B 3.1-13 B 3.1.4 Rod Group Alignment Limits . . .. . B 3.1-19 B 3.1.5 Shutdown Bank Insertion Limits . .. B 3.1-29 B 3.1.6 Control Bank Insertion Limits . B 3.1-34 B 3.1.7 Rod Position Indication ... ... .... B 3.1-40 B 3.1.8 Physics Tests Exceptions - Mode 2 . . . B 3.1-46 B 3.1.9 Chemical and Volume Control System (CVS)
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| Demineralized Water Isolation Valves .. B 3.1-53 B 3.2 Power Distribution Limits . . ..... . . .... . B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (Fn (Z)) !
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| (FqMethodology) . . ... . . ... . B 3.2-1 l B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%) .. ... .... B 3.2-10 B 3.2.3 Axial Flux Difference (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) . . . . . B 3.2-17 B 3.2.4 Quadrant Power Tilt Ratio (QPTR) . . ..... B 3.2-22 B 3.2.5 OPDMS-Monitored Power Distribution Parameters . . . . . ... B 3.2-28 B 3.3 Instrumentation . . . . . .. . . .. . . . B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation . . B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System l (ESFAS)Instmmentation . ... . . . B 3.3-53 B 3.3.3 Post Accident Monitoring (PAM)
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| Instrumentation .. ...... .. . . B 3.3-115 B 3.3.4 Remote Shutdown Workstation . .. . . B 3.3-125 B 3.4 Reactor Coolant System (RCS) . . .. . . . . . B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . . . . . B 3.4-1 O
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| Revision: 10 December 20,1996 xxviii W85tingh0USB
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| 1 II Master Tchte of Contents U MASTER TABLE OF CONTENTS (Cont.)
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| Section Title _P_ age B 3.4.2 RCS Minimum Temperature for Criticality . . B 3.4-6 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . B 3.4-9 B 3.4.4 RCS Loops - Modes 1 and 2 . . ....... B 3.4-17 B 3.4.5 RCS Loops - Modes 3,4, and 5 ...... . B 3.4-21 B 3.4.6 Pressurizer . . . . . . . .... .. . . B 3.4-25 B 3.4.7 Pressurizer Safety Valves . ......... . . B 3.4-28 B 3.4.8 RCS Operational Leakage .. .... ... B 3.4-32 B 3.4.9 Minimum RCS Flow . .. . . .. . . B 3.4-38 B 3.4.10 RCS leakage Detection Instrumentation .. B 3.4-41 B 3.4.11 RCS Specific Activity .. . ..... . B 3.4-46 B 3.4.12 Automatic Depressurization System (ADS)- ;
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| Operating .... ... . . .... .. . B 3.4-50 !
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| B 3.4.13 Automatic Depressurization System (ADS)-
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| Shutdown, RCS Intact ... .. ... . . B 3.4-54 1 B 3.4.14 Automatic Depressurization System (ADS)- 1 Shutdown, RCS Open . . ..... . . . B 3.4-57 B 3.4.15 Low Temperature Overpressure Protection (LTOP) System . . . . . . . ... .... B 3.4-60 (3 B 3.5 Passive Core Cooling System (PXS) . . .... . . . . B 3.5-1
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| () B 3.5.1 Accumulators .. .. . . . . . . . .. B 3.5-1 B 3.5.2 Core Makeup Tanks (CMT) - Operating . .. B 3.5-8 B 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact . . . . .... . ...... . . B 3.5-15 B 3.5.4 Passive Residual Heat Removal Heat l Exchanger (PRHR HX) - Operating . B 3.5-18 B 3.5.5 Passive Residual Heat Removal Heat Exchanger j (PRHR HX) - Shutdown, RCS Intact . . . .
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| .. B 3.5-24 B 3.5.6 In-containment Refueling Water Storage Tank (IRWST) - Operating .. ..... B 3.5-28 B 3.5.7 In-Containment Refueling Water Storage Tank (IRWST)- Shutdown. RCS Inventory High . B 3.5-34 B 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, RCS Inventory Low .... .. . ... B 3.5-38 B 3.6 Containment Systems . .. . . .... . . B 3.6-1 B 3.6.1 Containment . . . ... . . . . . B 3.6-1 B 3.6.2 Containment Air Locks ... . . ... . B 3.6-6 B 3.6.3 Containment Isolation Valves ....... . B 3.6-13 B 3.6.4 Containment Pressure . . . . B 3.6-23 B 3.6.5 Containment Air Temperature . . .. . B 3.6-26 B 3.6.6 Passive Containment Cooling System
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| , (PCS) - Operating . .. . . B 3.6-30
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| / ,.
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| Q Revision: 10 We5 $ 0US0 xxix December 20,1996
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| Master Table of Contents MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_ age B 3.6.7 Passive Containment Cooling System (PCS) - Shutdown ... .. .. . . B 3.6-37 B 3.6.8 Containment Penetrations . . .. .. . B 3.6-40 B 3.6.9 pH Adjustment .. . .. . . . . . . B 3.6-47 B 3.7 Plant Systems . . . . . . . .... . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . B 3.7.7 B 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) .. .. .... . . B 3.7-13 B 3.7.4 Secondany Specific Activity . . .... . . . B 3.7-18 B 3.7.5 Spent Fuel Pool Water Level . . . .. . B 3.7-21 B 3.7.6 Main Control Room Emergency Habitability System , ... ...... ... ... B 3.7-24 B 3.7.7 Startup Feedwater Isolation and Control Valves B 3.7-30 B 3.8 Electrical Power Systems . . . . . . . . . . . . . B 3.8-1 B 3.8.1 DC Sources - Operating . . . . .. . B 3.8-1 B 3.8.2 DC Sources - Shutdown .. .. B 3.8-11 B 3.8.3 Inverters - Operating . . . . . . . . . . . B 3.8-15 '
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| B 3.8.4 Inverters - Shutdown . .... .. B 3.8-20 B 3.8.5 Distribution Systems - Operating ... . B 3.8-24 B 3.8.6 Distribution Systems - Shutdown .. . . B 3.8.33 B 3.8.7 Battery Cell Parameters .. .. . .. . . B 3.8-37 B 3.9 Refueling Operations .. . . ... . B 3.9-1 i B 3.9.1 Boron Concentration . .. . . . . . . . B 3.9-1 !
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| B 3.9.2 Unborated Water Source Flow Paths . ... . B 3.9-5 l B 3.9.3 Nuclear Instrumentation ..... . . B 3.9-8 I B 3.9.4 Refueling Cavity Water Level . . . B 3.9-11 l Volume 11 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM . . . . 16.2-1 16.2.1 Introduction .. ... ... . .. .. 16.2-1 16.2.2 Scope . .... . . . .. 16.2-1 16.2.3 Design Considerations . . . .. .. ... . . 16.2-1 16.2.4 Relationship to Other Administrative Programs . . . 16.2-2 16.2.5 The AP600 Design Organization . .... .. . 16.2-2 16.2.6 Objective . .. . . . .... .. . . . ... 16.2-3 16.2.7 D-RAP, Phase I . . .. ..... .. . . . . . . . 16.2-4 16.2.8 Combined License Activities - O-RAP .. .. . .. 16.2-9 16.2.9 Glossary of Terms .. . . . . . 16.2-10 0
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| Resision: 10 December 20,19% xxx 3 Westinghouse
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| Master Table of Contents
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| ,- i V MASTER TABLE OF CONTENTS (Cont.)
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| Section Title P_ age 16.2.10 References . . . ... ...... . .. .... . . . . 16.2-11 CHAPTER 17 QUALITY ASSURANCE . . . .. .. . . .... ... . . . 17.1-1 17.1 Quality Assurance During the Design and Constmction Phases . .. ..... 17.1-1 17.2 Quality Assurance During the Operations Phase . . . . . . .. ... .. . 17.1-1 17.3 Quality Assurance During Design, Procurement, Fabrication, Inspection and/or Testing of Nuclear Power Plant Items and Services ... .. ... . 17.1-1 17.4 Combined License Information Items . .... .. . . ... . 17.1-2 17.5 References ... .. .. ... ....... .... .. 17.1-2 CHAPTER 18 HUMAN FACTORS ENGINEERING .. ...... .. . ..... . . . 18.1-1 18.1 Overview ........ .. ...... ... .. . . . .... . 18.1-1 18.1.1 References .... .. . . . . .. .. . . .. . . . 18.1-4 18.2 Human Factors Engineering Program Management . .. . . . .... . 18.2-1 18.2.1 Human Factors Engineering Program Goals, Scope, Assumptions, and Constraints . . . . . . . . . . . .... . . . . 18.2-1 18.2.2 Human System Interfaces Design Team and Organization}}
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