ML20247J787
| ML20247J787 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 05/08/1998 |
| From: | Mcintyre B, Piplica E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20247J767 | List: |
| References | |
| GW-GL-030, GW-GL-030-R05, GW-GL-30, GW-GL-30-R5, NUDOCS 9805210411 | |
| Download: ML20247J787 (800) | |
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Simplified Passive Advanced Light Water Reactor Plant Program I AP600 [ Tier 1 Material Prepared for U.S. Department of Energy San Francisco Operations Office DE-AC03-90SF18495 n DOC O!hh 3
@ Westinghouse Electric Company
AP600 DOCUMENT COVER SHEET TDC: IDS: 1 S Form 58202G(5/94)[o:\itaac\ cover.wpf) AP600 CENTRAL FILE USE. ONLY: 0058.FRM RFS#: RFS ITEM #:
/^ AP600 DOCUMENT NO. RI. VISION NO. ASSIGNED TO Q} GW-GL-030 ALTERNATE DOCUMENT NUMBER:
5 Page 1 of WORK BREAKDOWN #: 3.2.5 DESIGN AGENT ORGANIZATION: PROJECT: AP600 TITLE: AP600 Tier 1 Material ATTACHMENTS: DCP #/REV. INCORPORATED IN THIS DOCUMENT REVISION:
- CALCULATION / ANALYSIS
REFERENCE:
ELECTRONIC FILENAME ELECTRONIC FILE FORMAT ELECTRONIC FILE DESCRIPTION l Wordperfect (C) WESTINGHOUSE ELECTRIC COMPANY 1998 WESTINGHOUSE PROPRIETARY CLASS 2 This documont contains information propiletary to Westinghouse Electric Company; it is submitted in confidence and is to be used solely for the purpose for which it is fumished and retumed 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 Company, Energy Systems Business Unit, subject to the legends contained hereof. O WESTINGHOUSE PROPRIETARY CLASS 2C V This document is the property of and contains Proprietary information owned by Westinghouse Electric Company and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in stnct accordance with the terms and conditions i of the agreement under which it was provided to you. ' WESTINGHOUSE CLASS 3 (NON PROPRIETARY) COMPLETE 1 IF WORK PERFORMED UNDER DESIGN CERTIFICATION QB COMPLETE 2 IF WORK PERFORMED , UNDER FOAKE. l l 1 ODOE DESIGN CERTIFICATION PROGRAM - GOVERNMENT LIMITED RIGHTS STATEMENT [See page 2) Copyright statement A license is reserved to the U.S. Government under contract DE-AOJ3-90SF18495. EDOE CONTRACT DELIVERABLES (DELIVERED DATA) Subject to specified exceptions, disclosure of this data is restricted until September 30,1995 or Design Certification under DOE contract DE-ACO3-90SF18495, whichever is later. EPRI CONFIDENTIAL: NOTICE: 1 E 2 0 3 0 4 O s O CATEGORY: AEBOCDDDEDFO 2 OARC FOAKE PROGRAM - ARC LIMITED RIGHTS STATEMENT [See page 2) Copyright statement A license is reserved to the U.S. Govemment under contract DE-FC02-NE34267 and subcontract ARC-93-3-SC-001. DARC CONTRACT DELIVERABLES (CONTRACT DATA) Subject to specified exceptions, disclosure of this data is restricted under ARC Subcontract ARC-93-3-SC 001. ORIGINATOR SIGNATURE /DATE E. J. Piplica 'P ) , e f[ 9f APM0 RESPONSIBLE MANAGER SIGNATUR / A[/ PROVAL D TE B. A. Mc!ntyre ( (, m /f[/ , ) [f
- Approval of the responsib6e manager signifies that document is compit!te, all required revbis are complete, electronid file is attached and document as released for use.
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AP600 DOCUMENT COVER SHEET Pcgea Form 58202G(5/94) LIMITED RIGHTS STATEMENTS \ DOE GOVERNMENT UMITED RIGHTS STATEMENT (A) These data are submitted with limited rights under government contract No. DE-ACO3-90$F18495. These data may be reproduced and used by the govemment with the expres* hmitation that they will not, without written permiss#on of the contractor, be used for purposes of manufacturer nor disclosed outside the govemment; except that the govemment may disdose these data outside the government for the following purposes, if any, provided that the govemment makes such disclosure subject to prohibition against further use and disclosure: (1) This ' Proprietary Data' may be disdosed for evaluation purposes under the restrictions above. (11) The ' Proprietary Data
- may be disclosed to the Electric Power Research Institute (EPRI), electnc utility representatives and their direct consultants, exduding direct commercial competitors, and the DOE National Laboratories under the prohibitions and restrictions above.
(B) This notice shall be marked on any reproduction of these data, in whole or in part. ARC UMITED RIGHTS STATEMENT: g This proprietary data, fumished under Subcontract Number ARC-93-3-SC-001 with ARC may be duplicated and used by the govemment and ARC, subject to the hmitations of Artcle H-17.F. of that subcontract, with the express limitations that the proprietary data may not be disclosed outside the govemment or ARC, or ARC's Class 1 & 3 members or EPRI or be used for purposes of manufacture without prior permission of the Subcontractor, except that further disdesure or use may be made solely for the follovnng purposes: This proprietary data may be disdosed to other than commercial competitors of Subcontractor for evaluation purposes of this subcontract under 1 the restnction that the proprietary data be retained in confidence and not be further disclosed, and subject to the terms of a non-disdosure ' agreement between the Subcontractor and that organization, excluding DOE and its contractors. j DEFINITIONS CONTRACT /DEUVERED DATA - Consists of docurnents (e.g. specifications, drawings, reports) which are generated under the DOE or ARC contracts which contain no background proprietary data. EPRI CONFIDENTIALITY / OBLIGATION NOTICES NOTICE 1: The data in this document is subject to no confidentiality obligations. NOTICE 2: The data in this document is propnetary and confidential to Westinghouse Electric Company and/or its Contractors. It is forwarded to recipient under an obligation of Confidence and Trust for limited purposes only. Any use, disclosure to unauthorized persons, or copying of this document or parts thereof is prohibited except as agreed to in advance by the Electric Power Research insttute (EPRI) and Westi house Electne Company. Recipient of this data has a duty to inquire of EPRI and/or Westinghouse as to the uses of the information contas he ein that are permitted. NOTICE 3: The data in this document is proprietary and confidential to Westinghouse Electric Company and/or its Contractors. It is forwarded to recipient under an obligation of Confidence and Trust for use only in evaluation tasks specifically authorized by the Electric Power Research Institute (EPRI). Any use, disdosure to unauthorized persons, or copying this document or parts thereof is prohibited except as agreed to in advance by EPRI and Westinghouse Electnc Company. 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. NOTICE 4: The data in this document is proprietary and confidential to Westinghouse Electric Cort.pany and/or its Contractors. it is being revealed in confidence and trust only to Emplo Any use, disdosure to unauthorized persons,yees or copying ofofthis EPFil and toorcertain document contractors parts thereof of EPRI is prohibited. Thisfor Lmited and Document evaluation tasks any copies or authonzed by EPR excerpts thereof that may have been generated are to be retumed to Westinghouse, directly or through EPRI, when requested to do so. NOTICE 5: The data in this document is proprietary and confidential to Westinghouse Electric Company and/or its Contractors. Access to this data is given in Confidence and Trust only at Westinghouse facilities for limited evaluation tasks assigned by EPRt. Any use, disdosure to unauthonzed persons, or copying of this document or parts thereof is prohibited. Neither this document nor any excerpts therefrom are to be removed from Westinghouse facilities. EPRI CONFIDENTIALITY / OBLIGATION CATEGORIES CATEGORY "A*-(See Delivered Data) Consists of CONTRACTOR Foreground Data that is contained in an issued reported. CATEGORY "B"- (See Delivered Data) Consists of CONTRACTOR Foreground Data that is not contained in an issued report, except for computer programs. CATEGORY 'C'- Consists of CONTRACTOR Background Data except for computer programs. CATEGORY 'D"- Consists of computer programs developed in the course of performing the Work. CATEGORY *E"- Consists of computer programs developed prior to the Effective Date or after the Effective Date but outside the scx)pe of the Work. CATEGORY 7"- Consists of administrative plans and administrative reports. l 9
O Simplified Passive Advanced Light Water Reactor Plant Program i AP600 TIER 1 MATERIAL O erepara for l U.S. Department of Energy San Francisco Operations Office DE-AC03-90SF18495 i Revision 5 i May 8,1998 l l I I O :
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1 l Certified Design Material l TABLE OF CONTENTS ~~~ ' A Revision: 5 E
) Effective: 5/8/98 TABLE OF CONTENTS Section Page LIST OF FIGURES vi
1.0 INTRODUCTION
1.1 Definitions 1.0-1 1.2 General Provisions 1.0-3 1.3 Figure Legend 1.0-5 1.4 List of Acronyms and Abbreviations 1.0-9 2.0 SYSTEM BASED DESIGN DESCRIPTIONS AND ITAAC 2.1 Reactor 2.1.1 Fuel Handling and Refueling System 2.1.1-1 2.1.2 Reactor Coolant System 2.1.2-1 2.1.3 Reactor System 2.1.3 1 2.2 Nuclear Safety Systems 2.2.1 Containment System 2.2.1-1 2.2.2 Passive Containment Cooling System 2.2.2-1 2.2.3 Passive Core Cooling System 2.2.3-1
,Q 2.2.4 Steam Generator System 2.2.4-1 C/ 2.2.5 Main Control Room Emergency Habitability System 2.2.5-1 2.3 Auxiliary Systems 2.3.1 Component Cooling Water System 2.3.1-1 2.3.2 Chemical and Volume Control System 2.3.2-1 2.3.3 Standby Diesel and Auxiliary Boiler Fuel Oil System 2.3.3-1 2.3.4 Fire Protection System 2.3.4-1 i 2.3.5 Mechanical Handling System 2.3.5-1 2.3.6 Normal Residual Heat Removal System 2.3.6-1 2.3.7 Spent Fuel Pool Cooling System 2.3.7-1 2.3.8 Service Water System 2.3.8-1 2.3.9 Containment Hydrogen Control System 2.3.9-1 2.3.10 Liquid Radwaste System 2.3.10-1 2.3.11 Gaseous Radwaste System 2.3.11-1 2.3.12 Solid Radwaste System 2.3.12-1 2.3.13 Primary Sampling System 2.3.13-1 2.3.14 Demineralized Water Transfer and Storage System 2.3.14-1 2.3.15 Compressed and Instrument Air System 2.3.15-1
- 2.3.16 Potable Water System 2.3.16-1 2.3.17 Waste Water System 2.3.17-1 2.3.18 Plant Gas System 2.3.18-1 2.3.19 Communications System 2.3.19-1 2.3.20 Turbine Buildine Closed Cooline Water System 2.3.20-1 2.3.21 Secondary Sampline System 2.3.21-1 l ln) s' W Westinghouse owsoonAAesvevsvntmtr.wpusoso7
Certified Design Material TABLE OF CONTENTS Revision: 5 Effective: 5/8/98 TABLE OF CONTENTS (cont.) Section Page 2.3.22 Containment Leak Rate Test System 2.3.22-1 2.3.23 This section intentionally blank 2.3.23-1 13.24 Demineralized Water Treatment System 2.3.24-1 2.3.25 Gravity and Roof Drain Collection System 2.3.25-1 2.3.26 This section intentionally blank 2.3.26-1 2.3.27 Sanitary Drainare System 2.3.27-1 2.3.28 Turbine Island Vents. I' rains. and Relief System 2.3.28-1 2.3.29 Radioactive Waste Drain System 2.3.29-1 2.4 Steam and Power Conversion Systems 2.4.1 Main and Startup Feedwater System 2.4.1-1 2.4.2 Main Turbine System 2.4.2-1 2.4.3 Main Steam System 2.4.3-1 2.4.4 Steam Generator Blowdown System 2.4.4-1 2.4.5 Condenser Air Removal System 2.4.5-1 2.4.6 Condensate System 2.4.6-1 2.4.7 This section intentionally blank 2.4.7-1 2.4.8 Auxiliary Steam Supply System 2.4.8-1 2.4.9 Condenser Tube Cleaning System 2.4.9-1 2.4.10 Turbine Island Chemical Feed System 2.4.10-1 2.4.11 Condensate Polishine System 2.4.11-1 2.4.12 Gland Seal System 2.4.12-1 2.4.13 Generator Hydrogen and CO System 2.4.13-1 2 2.4.14 Heater Drain System 2.4.14-1 2.4.15 Hvdrogen Seal Oil System 2.4.15-1 2.4.16 Main Turbine and Generator Lube Oil System 2.4.16-1 2.5 Instrumentation and Control Systems 2.5.1 Diverse Actuation System 2.5.1-1 l 2.5.2 Protection and Safety Monitoring System 2.5.2-1 2.5.3 Plant Control System 2.5.3-1 2.5.4 Data Display and Processing System 2.5.4-1 2.5.5 In-Core Instrumentation System 2.5.5-1 2.5.6 Special Monitoring System 2.5.6-1 2.5.7 Operation and Control Centers System 2.5.7-1 l 2.5.8 This section intentionally blank 2.5.8-1 2.5.9 Seismic Monitoring System 2.5.9-1 2.5.10 Main Turbine Control and Diarnostic System 2.5.10-1 2.6 Electrical Power Systems 2.6.1 Main ac Power System 2.6.1-1 2.6.2 Non-Class IE de and Uninterruptible Power Supply System 2.6.2-1 O W Westinghouse oMp600nAACSVev5Vntmtr.wpub-oSO 1
l Certified Design Material , i 1 ( TABLE OF CONTENTS ( % ! l (T Revision: 5 - m ; V Effective: 5/8/98 I { TABLE OF CONTENTS (cont.) Section Page 2.6.3 Class IE de and Uninterruptible Power Supply System 2.6.3-1 2.6.4 Onsite Standby Power System 2.6.4-1 2.6.5 Lighting System 2.6.5-1 2.6.6 Grounding and Lightning Protection System 2.6.6-1 1 2.6.7 Snecial Process Heat Tracine S.ystem 2.6.7-1 j 2.6.8 7his section intentionally blank 2.6.8-1 2.6.9 This section intentionally blank 2.6.9-1 2.6.10 This section intentionally blank 2.6.10-1 2.6.11 Main Generation System 2.6.11-1 2.6.12 Excitation and Voltare Regulation System 2.6.12-1 2.7 HVAC Systems 2.7.1 Nuclear Island Nonradioactive Ventilation System 2.7.1-1 2.7.2 Central Chilled Water System 2.7.2-1 , 2.7.3 Annex / Auxiliary Building Nonradioactive Ventilation System 2.7.3 1 l 2.7.4 Diesel Generator Building Ventilation System 2.7.4 1 2.7.5 Radiologically Controlled Area Ventilation System 2.7.5-1 2.7.6 Containment Air Filtration System 2.7.6-1
/ 2.7.7 Containment Recirculation Cooling System 27.7-1 V 2.7.8 Radwaste Bailding HVAC System 2.7.8-1 2.7.9 Turbine Island Buildine Ventilation System 2.7.9-1
, 2.7.10 Health Physics and Hot Machine Shop HVAC System 2.7.10-1 1 2.7.11 Hot Water Heatine System 2.7.11-1 3.0 NON-SYSTEM BASED DESIGN DESCRIPTIONS AND ITAAC l 3.1 Emergency Response Facilities 3.1-1 3.2 Human Factors Engineering 3.2-1 3.3 Buildings 3.3-1
]
3.4 Initial Test Program 3.4-1 3.5 Radiation Monitoring 3.5-1 3.6 Reactor Coolant Pressure Boundary Leak Detection 3.6-1 3.7 Design Reliability Assurance Program 3.7-1 4.0 INTERFACE REQUIREMENTS 4.0-1 5.0 SITE PARAMETERS 5.0-1 l l
- Underlined sections - title only, no entry for Design Certification. 1 i
V r NE o:\ap600\lTAACS\rev5\fntmtr.wpf.1 b-05079 ( _ .
Certified Design Material TABLE OF CONTENTS "== (] () 8tevision: 5 Effective: 5/8/98 LIST OF FIGURFE Figure Title Page 2.1.2-1 Reactor Coolant System 2.1.2-30 2.1.3-1 Reactor Upper Intemals Rod Guide Arrangement 2.1.3-12 2.1.3-2 Rod Cluster Control and Drive Rod Arrangement 2.1.3-13 2.1.3-3 Reactor Vessel Arrangement 2.1.3-14 2.2.1 -1 Containment System 2.2.1-15 . 2.2.2-1 Passive Containment Cooling System 2.2.2-15 2.2.3-1 Passive Core Cooling System 2.2.3-26 2.2.4-1 Steam Generator System 2.2.4-22 2.2.5-1 Main Control Room Emergency Habitability System 2.2.5-16 2.3.1-1 Component Cooling Water System 2.3.1-5 2.3.2-1 Chemical and Volume Control System 2.3.2-15 2.3.3-1 Standby Diesel and Auxiliary Boiler Fuel Oil System 2.3.3-5 2.3.4-1 Fire Protection System (Seismic Piping) 2.3.4-6 2.3.6-1 Normal Residual Heat Removal System 2.3.6-17 2.3.7-1 Spent Fuel Pool Cooling System 2.3.7-7 2.3.8-1 Service Water System 2.3.8-5 2.3.10-1 Liquid Radwaste System 2.3.10-9 2.3.11-1 Gaseous Radwaste System 2.3.11-6 ( V j 2.3.13-1 Primary Sampling System 2.3.13-8 2.3.29-1 Radioactive Waste Drain System 2.3.29 3 2.4.1 -1 Main and Startup Feedwater System 2.4.1-4 2.5.2-1 Protection and Safety Monitoring System 2.5.2-19 2.6.1-1 Main ac Power System 2.6.1-11 l 2.6.2-1 Non-Class IE de and Uninterruptible Power Supply System 2.6.2-4 l 2.6.3-1 Class IE de and Uninterruptible Power Supply System (Division A) 2.6.3-16 l 2.7.1-1 Nuclear Island Nonradioactive Ventilation System 2.7.1-11 l 2.7.2-1 Central Chilled Water System 2.7.2-5 l 2.7.3-1 Annex / Auxiliary Building Nonradioactive Ventilation System 2.7.3-5 i 2.7.4-1 Diesel Generator Building Ventilation System 2.7.4-5 2.7.6-1 Containment Air Filtration System 2.7.6-5 3.2-1 Human Factors Engineering (HFE) Design and Implementation Process 3.2-11 3.3-1 Section A-A with Building Levels 3.3-31 3.3-2 Section B-B with Building Levels 3.3-33 3.3-3 NI Plan View Level 1 3.3-35 3.3-4 NI Plan View Level 2 3.3-37 l 3.3-5 NI Plan View Level 2.1 3.7-39 l~ 3.3-6 NI Plan View Level 3 3.3-41 3.3-7 N1 Plan View Level 4 3.3-43 3.3-8 NI Plan View Level 5 3.3-45 3.3-9 NI Plan View Level 6 3.3-47 3.3-10 NI Plan View Level 7 3.3-49 3.3-11 Annex Building Plan View Level 1 3.3-51
,fm 3.3-12 Annex Building Plan View I.evel 2 3.3-53 .( )
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Certified Design Material I TABLE OF CONTENTS h Revision: 5 E - l Effective: 5/8/98 P i LIST OF FIGURES (cont.) Figure Title Page 3.3-13 Annex Building Plan View Level 3 3.3-55 3.3-14 Nuclear Island Structures Dimension at Elevation Level 1 3.3-57 3.3-15 Legend 3.3-61 5.0-1 Horizontal Design Response Spectra Safe Shutdown Fmthquake 5.0-4 5.0-2 Vertical Design Response Spectra Safe Shutdown Eanhquake 5.0-5 O O f==a- . _ _ . _ _ - _ ;:
Certified De:Ign M:terill INTFtODUCTION ~ Revision: 5 E Effective: 5/8/98 l i 1.0 Introduction 1.1 Definitions The following definitions appiy to terms used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC). Acceptance Criteria means the performance, physical condition, or analysis result for a structure, system, or component that demonstrates that the design commitment is met. Analysis means a calculation, mathematical computation, or engineering or technical evaluation. Engineering or technical evaluations could include, but are not limited to, comparisons with operating experience or design of similar stmetures, systems, or components. As-built means the physical propenies of a stmeture, system, or component following the completion of its installation or construction activities at its final location at the plant site. Cable means an electrical conductor with or without insulation, or a combination ofinsulated electrical conductors. Design Commitment means that ponion of the design description that is verified by ITAAC. Design Description means that ponion of the design that is cenified. Division (for electrical systems or electrical equipment) is the designation applied to a given safety-related system or set of components tat is physically, electrically, and functionally independent from other redundant sets of components. Functional Arrangement means the physical arrangement of structures, systems, and components to provide the service for which the structure or system is intended, and which is described in the design description. Functional Capability (of a line) means the line maintains the ability to transfer fluid through the line while providing a pressure boundary, during and after a design basis event. Heavy Load means a load whose weight is greater than the combined weight of a single spent fuel assembly and its handling device. Inspect or Inspection means visual observations, physical examinations, or reviews of records braed on visual observadon or physical examination that compare the structure, system, or component condition to one or more design commitments. Examples include walkdowns, configuration checks, measurements of dimensions, or nondestructive examinations. Inspect for Retrievability of a display means to visually observe that the specified information appears on a monitor when summoned by the operator. DDLIS8 o \ap60mrTAACSVev5\it0101.wpt050398 1.0-1
Certified Design Material ihlTRODUCTION ' Revision: 5 Effective: 5/8/98 L, is the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J. Nominal means a dimension or size used to designate a name whereby such dimention or size may vary from the actual, or as measured, dimension or size, according to industry standards. Qualified for Harsh Environment means that equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of its safety function, for the time required to perform the safety function. Equipment identified in the Design Description as being Qualified for Harsh Environment includes the:
- a. equipment itself
- b. sensors, switches and lubricants that are an integral part of the equipment
- c. electrical components connected to the equipment (wiring, cabling and terminations)
Items b and c are Qualified for Harsh Environment only when they are necessary to support operation of the equipment to meet its safety-related function listed in the Design Description table and to the extent such equipment is located in a harsh environment during or following a design basis accident. Safe Shutdown refers to a plant condition where the reactor is subcritical with adequate coolant inventory and core cooling, with a coolant temperature less than 420*F. Safety-related is a classification applied to items relied upon to temain functional during or following a design basis event to provide a safety-related function. Safety-related also applies to documentation and services affecting a safety-related item. Sensor means a transmitter, resistance temperature detector, thermocouple or other transdocer, plus associated cables, connectors, preamplifiers, reference junction boxes, or other signal processing equipment that is located in the immediate proximity of the sensor and subject to the same environmental condidons. Test means the actuation, operation, or establishment of specified conditions to evaluate the performance or integrity of as-built stmetures, systems, or components, unless explicitly stated otherwise. Transfer Open (Closed) means to move from a closed (open) position to an open (closed) position. Type Test means a test on one or more sample components of the same type and manufacturer to qualify other components of the same type and manufacturer. A type test is not necessarily a test of the as-built stmetures, systems, or components. UA of a heat exchanger means the product of the heat transfer coefficient and the surface area. O 1.0-2 WBStifigh00S8 o: saps 0cuTAACSVev5Mt0101.wpf:050398
Certified Design Material INTRODilCTION C"~r A Revision: 5 - 3 Effective: 5/8/92
!w) _-
1
. et I.2 General Provisions The following general provisions are applicable to the design descriptions and associated ITAAC.
Treatment of Individual Items l *Ihe absence of any discussion or depiction of an item in the design description or accompanying figures shall not be construed as prohibiting a licensee from utilizing such an item, unless it would prevent an item from performing its safety functions as discussed or depicted in the design description i or accompanying figures. If an inspections, tests, or analyses (ITA) requirement does not specify the temperature or other l conditions under which a tot must be run, then the test conditions are not constrainert. I When the term " operate," " operates," or " operation" is used with respect to an item discussed in the l acceptance criteria, it refers to the actuation and running of the item. When the term " exist," " exists," I or " existence" is used with respect to an item discussed in the acceptance criteria, it means that the item is present and meets the design commitment. Implementation of ITAAC 1
'Ihe ITAACs are provided in tables with the following three-column fonnat:
\O) v l Design Inspections, Acceptance )
l Commitment Tests, Analyses Criteria l l l Each design commitment in the left-hand column of the ITAAC tables has an associated ITA j requirement specified in the middle column of the tables. 1 The identification of a separate ITA entry for each design commitment shall not be construed to require that separate inspections, tests, or analyses must be performed for each design commitment. l Instead, the activities associated with more than one ITA entry may be combined, and a single j inspection, test, or analysis may be sufficient to implement more than one ITA entry. An ITA may be performed by the licensee of the plant or isy its authorized vendors, contractors, or consultants. Furthermore, an ITA may be performed by more than a single individual or group, may be implemented through discrete activities separated by time, and may be perfonned at any time prior to fuel load (including before issuance of the combined operating license for those ITAACs that do not necessarily pertain to as-installed equipment). Additionally, an ITA may be performed as part of the activities that are required to be performed under 10 CFR Part 50 (including, for example, the quality assurance (QA) program required under Appendix B to Part 50); therefore, an ITA need not be performed as a separate or discrete activity. i G - 1.0-3 M ligh0LISS o$ap600VTAACSVev5Vt01o1.wpf.05D398
Certified Design Material INTRODUCTION T""C i Revision: 5 f ( Effective: 5/8/98 1 Discussion of Matters Related to Operations In some cases, the design descriptions in this document refer to matters that relate to operation, such as normal valve or breaker alignment during normal operation modes. Such discussions are provided . solely to place the design description provisions in context (for example, to explain automatic features ' for opening or closing valves or breakers upc,a off-normal conditions). Such discussions shall not be construed as requiring operators during operation to take any particular action (for example, to maintain valves or breakers in a particular position during normal operation). Interpretation of Figures la many but not all cases, the design demiptions in Section 2 include one or more figums. The figures may represent a functional diagram, gereral stmetural representation, or another general illustration. For instmmentation and control (I&C) systems, figures may also represent aspects of the relevant logic of the system or part of the system. Unless specified explicitly, the figures are not indicative of the scale, location, dimensions, shape, or spatial relationships of as-built stmetures, systems, and components. In particular, the as-built attributes of structures, systems, and components may vary from the attributes depicted on the figures, provided that those safety functions discussed in the design description pertaining to the figure are not adversely affected. Maximum Reactor Core Thermal Power The initial rated reactor core thermal power for the AP600 certified design is 1933 megawatts thermal (MWt). l l Qi DE o:\ap600VTAACSvev5WO101.mpf: i l
Certified Decign Material INTRODUCTION " j ,q Revision: 5 = 'Q Effective: 5/8/98 _ 1.3 Figure Legend The conventions used in this section are for figures desciibed in the design description. The figure legend is provided for information and is not part of the Certified Design Material. VALVES Volve [><] ] I Check Valve d Relief Valve 5I { d i l l V VALVE OPERATORS
~
Operator Of Unspecified Type T Motor Operator h l l Solenoid Operator h Pneumatic / Hydraulic Operator kS Pneumatic Operator h Squib Valve C 1.0-5 Westinghouse oMp600VTAACSVev5Mt0101.wpt:050398
Certified Design Material INTRODUCTION .. = -i ; Revision: 5 i l Effective: 5/8/9C WECHWCAL EQUIPWENT Wugd Pump Pump Type Not Specifed Tank Centrifugd Fan h Axid Fan C>C Heat Exclueger O vent p Dmin U D Pipe Cap _] Nad Flange _ll M*8 _lI - O N W
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7 Certified Design Material i INTRODUCTION (m (,) Revision: 5 Effective: 5/8/98 I l DAMPERS I J Gravity Or Wonuaity Operated Domper l I Remotely Operated Damper ,, l i ELECTRICAL EQUIPMENT l l Bottery 1 Circuit Brecker .n l l Disconnect Switch / lsolation _I_. Transformer AAA 9 Heoter LWJ
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Certified Design Material INTRODUCTION 1 Revision: 5 [ Effective: 5/8/98 - MISCELLANEOUS A component, that is part of the Component Name system functional arrangement shown Component Tag No. on the figure and is included ir. the design commitments for the system. A component that is part of the
, Component Namel system functional arrangement shown -
on the figure. Component Tag No.j- - [.,_ _ A system or component of another system F System or Component Name1 _,_ that is not part of the system functional -- System Acronym arrangement shown on the figure. L __ _ g A functional connection to another system that is not part of the system functional --g TEM ONYM arrangement shown on the figure. ASME CODE Cl. ASS BREAK An ASME Code class break is identified by a single line to the designated location for the class break, as shown in the example below (see note 1). I ASWE CODE SECDON W CLASS l L2 N,j
- x -
N : 1 NOTES:
- 1. The header, "ASME Code Section 111 Class", must appear at least once on each figure on which ASME class breaks are shown, but need not appear at every class break shown on a figure.
F Indicates Non-ASME Code Section 111 l l l \ O r ==a- _._ s' l l
Certified De:ign M:t: rill INTRODUCTION & Revision: 5 ug O Effective: 5/8/98 1.4 List of Acronyms and Abbreviations The acronyms presented in this section are used in the Certified Design Material. The acronyms are provided for information and are not part of the Certified Design Materia ac Alternating Current AC Acceptance Criteria ACC Accumulator ADS Automatic Depressurization System AHU Air Handling Units ASME American Society of Mechanical Engineers BTU British Thermal Unit CAS Compressed Air System CAV Cumulative Absolute Velocity CCS Component Cooling Water System CDM Certified Design Material CDS Condensate System CFR Code of Federal Regulations CIV Containment Isolation Valve CL Cold Leg CMT Core Makeup Tank O CNS COL CRDM Containment System Combined Operating License Control Rod Drive Mechanism CST Condensate Storage Tank CVS Chemical and Volume Control System DAC Design Acceptance Criteria DAS Diverse Actuation System DBA Design Basis Accident de Direct Current DC Design Commitment DDS Data Display and Processing System DOS Standby Diesel and Auxiliary Boiler Fuel Oil System DPU Distributed Processing Unit D-RAP Design Reliability Assurance Program DTS Demineralized Water Treatment System DVI Direct VesselInjection DWS Demineralized Water Transfer and Storage System ECS Main ac Power System EDS Non< lass 1E de and Uninterruptible Power Supply System EFS Communication System EGS Grounding and Lightening Protection System ELS Plant Lighting System EMI Electromagnetic Interference ERF Emergency Response Facility Mi@MB o$ap600VTAACSVev5Vt0101.wpf:050398 1.0-9
Certified Design Material INTRODUCTION === 7 2 . Revision: 5 l Effective: 5/8/98 i t l List of Acronyms and Abbreviations (cont.) ESD Electrostatic Discharge ESF Emergency Safety Features ESFAS Engineering Safety Feature Actuation System F Fahrenheit FHM Fuel Handling Machine FHS Fuel Handling and Refueling System FID Fixed Incore Detector . FPS Fire Protection System ft Feet FTS Fuel Transfer System FWS Main and Startup Feedwater System gpm Gallons per Minute HEPA High Efficiency Particulate Air HFE Human Factors Engineering HL Hot Leg hr Hour HSI Human-System Interface HVAC Heating, Ventilation, and Air Conditioning HX Heat Exchanger Hz Hertz I&C Instrumentation and Control IDS Class 1E de and Uninterruptible Power Supply System IIS In-core Instrumentation System ILRT Integrated Leak Rate Test IHP Integrated Head Package in Inches I/O Input / Output I&C Instrumentation and Control IRC Inside Reactor Containment ! I IRWST In-containment Refueling Water Storage Tank ISI Inservice Inspection IST Inservice Testing ITA Inspections, Tests, Analyses ITAAC Inspections, Tests, Analyses, and Acceptance Criteria LBB Leak Before Break LTOP Low Temperature Overpressure Protection MBru Million British Thermal Units MCC Motor Control Center MCR Main Control Room MHS Mechanical Handling System MMIS Man-machine Interface System G: 1.0-10 W8SIlllMUSB o:\ap600VTAACSvev5ilt0101.wpt:050398
Certified Design Material INTRODUCTION em Revision: 5 7-Q
!\-) Effective: 5/8/98 i e List of Acronyms and Abbreviations (cont.)
MOV Motor-operated Valve MSIV Main Steam Isolation Valve ' MSLB Main Steam Line Break MSS Main Steam System MTS Main Turbine System MW Megawatt MWe Megawatt Electric MWt Megawatt Thermal N/A Not Applicable NDE Nondestmetive Examination NI Nuclear Island NSSS Nuclen Steam Supply System OCS Operation and Control Centers System ORC Outside Reactor Containment ORE Occupational Radiation Exposure OSA Operational Sequence Analyses l OSC Operations Support Cercer ! PAR Passive Autocatalytic Recombiner PCCAWS Passive Containment Cooling Ancillary Water Storage Tank j'^} PCWS Passive Containment Cooling Water Storage sm_/ PCCWST Passive Containment Cooling Water Storage Tank PCS Passive Containment Cooling System P&ID Piping and Instrument Diagram PGS Plant Gas System pH Potential of Hy& ogen PLS Plant Control System PMS Protection and Safety Monitoring System PORV Power-operated Relief Valve PRA Probabilistic Risk Assessment PRHR Passive Residual Heat Removal psia Pounds per Square Inch Absolute PSS Primary Sampling System PXS Passive Core Cooling System PWR Pressurized Water Reactor RAP Reliability Assurance Program RAT Reserve Auxiliary Transformer RCDT Reactor Coolant Drain Tank RCP Reactor Coolant Pump RCPB Reactor Coolant Pressure Boundary l RCS Reactor Coolant System RFI Radio Frequency Interference RM Refueling Machine n RMS Radiation Monitoring System x W Westinghouse o%200FAACSVev5W0101mpf: 98 j 1 1
Certified Design Material INTRODUCTION *~ g Revision: 5 ~ Effective: 5/8/98 List of Acronyms and Abbreviations (cont.) l RNS Normal Residual Heat Removal System RPV Reactor Pressure Vessel RSR Remote Shutdown Room RSW Remote Shutdown Workstation RTD Resistance Temperature Detector RXS Reactor System RV Reactor Vessel scf Standard Cubic Feet scfm Standard Cubic Feet per Minute SFP Spent Fuel Pool SFS Spent Fuel Pool Cooling System SG Steam Generator SGS Steam Generator System SJS Seismic Monitoring System SMS Special Monitoring System SSAR Standard Safety Analysis Report SSCs Stmetures, Systems, and Components SSE Safe Shutdown Earthquake SWC Surge Withstand Capability SWS Service Water System TID Total Integrated Dose TSC Technical Support Center UAT Unit Auxiliary Transformer UBC Uniform Building Code UPS Uninterruptible Power Supply V Volt VAS Radiologically Controlled Area Ventilathn System VBS Nuclear Island Nonradioactive Ventilation System VCS Containment Recirculation Cooling System VES Main Control Room Emergency Habitability System VFS Containment Air Filtration System VHS Health Physics and Hot Machine Shop Areas VLS Containment Hydrogen Control System VWS Central Chilled Water System VXS Annex / Auxiliary Building Nonradioactive Ventilation System VZS Diesel Generator Building Ventilation System WGS Gaseous Radwaste System WLS Liquid Radwaste System WSS Solid Radwaste System ZOS Onsite Standby Power System O w ma- . _ _ =
I Certified Design Material i FUEL HANDLING AND REFUELING SYSTEM - (p v
/
Revision: 5 Effective: 5/8/98 2.1.1 Fuel Handling and Refueling System Design Description The fuel handling and refueling system (FHS) transfers fuel assemblies and core components during I fueling operations and stores new and spent fuel assemblies in the new and spent fuel storage racks. The refueling machine (RM) and the fuel transfer tube are operated during refueling mode. The fuel i handling machine (FHM) is operated dudng normal modes of plant operation, including startup, power operation, cooldown, shutdown and refueling. - he component locations of the FHS are as shown in Table 2.1.1-2. I 1. The functional arrangement of the FHS is as described in the Design Description of this l Section 2.1.1. I 2. The FHS has the RM, the FHM, and the new and spent fuel storage racks. I 3. He FHS preserves containment integrity by isolation of the fuel transfer tube penetrating containment. l 4. The RM and FHM gripper assemblies are designed to prevent opening while the weight of the fuel
/]
V assembly is suspended from the gripper, l S. The lift height of the RM and FHM masts is limited such that the minimum required depth of water shielding is maintained. I 6. The RM and FHM are designed to maintain their load carrying and structural integrity functions during a safe shutdown earthquake. I 7. The new and spent fuel storage racks maintain the effective neutron multiplication factor less than the required limits during normal operation, design basis seismic events, and design basis dropped fuel assembly accidents. i Inspections, Tests, Analyses, and Acceptance Criteria Table 2.1.1-1 specifies the inspections, tests, analyses, and associated acceptance criteda for the FHS. I l l !
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(% 2.1.1-1 i W8511Dgh0USB c:VTAACSvev5Mt020101.wpt:050198
I l Certified Design Material I i FUEL HANDLING AND REFUELING SYSTEM F*==
^
Revision: 5 3 Effective: 5/8/98 i .et j I i Table 2.1.1-1 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. The functional arrangement of Inspection of the as-built system The as-built FHS is as described I the FHS is as described in the will be performed, in the Design Description of this l Design Description of this Section 2.1.1. ) l Section 2.1.1. I l 2. He FHS has the refueling Inspection of the system will be he FHS has the RM, the FHM, machine (RM), the fuel handling performed. and the new and spent fuel machine (FHM), and the new and storage racks. spent fuel storage racks. l 3. The FHS preserves See Cenified Design Material, See Certified Design Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment l of the fuel transfer tube System. System. I penetrating containment. l 4. The RM and FHM gripper The RM and FHM will be tested He gripper will not open while assemblies are designed to by operating the open controls of suspending a dummy test ) prevent opening while the weight the gripper while suspending a assembly. ) of the fuel assembly is suspended dummy fuel assembly. from the gripper. l l 5. He lift height of the RM and He RM and FHM will be tested The bottom of the dummy fuel l l FHM masts is limited such that by attempting to raise a dummy assembly cannot be raised to I the minimum required depth of fuel assembly, within 24 ft,6 in of the operating I water shielding is maintained. deck floor. l 6. The RM and FHM are i) Inspection will be performed to i) The RM and FHM are located designed to maintain their load verify that the RM and FHM are on the nuclear island. carrying and structural integrity located on the nuclear island. functions during a safe shutdown earthquake. ii) Type test, analysis, or a ii) A report exists and concludes combination of type tests and that the RM and FHM can analyses of the RM and FHM will withstand seismic design basis be performed. dynamic loads without loss of load carrying or structural integrity functions. l l 9! T Westitighouse c:VTAACSVev5Vtq20101.wpf 19 l l
1 Certified Design Material l i FUEL HANDLING AND REFUELING SYSTEM - = Revision: 5 ' 5 g u
) Effective: 5/8/98 . ,ee Table 2.1.1 1 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 7. The new and spent fuel i) Analyses will be performed to i) The calculated effective storage racks maintain the calculate the effective neutron neutron multiplication factor for effective neutron multiplication multiplication factor in the new the new and spent fuel storage factor less than the required limits and spent fuel storage racks racks is less than 0.95 under I during normal operation, design during normal conditions. normal conditions. basis seismic events, and design basis dropped fuel assembly ii) Inspection will be performed ii) The new and spent fuel accidents. to verify that the new and spent storage racks are located on the fuel storage racks are located on nuclear island. the nuclear island. iii) Seismic analysis of the new iii) A report exists and concludes and spent fuel storage racks will that the new and spent fuel racks be performed. can withstand seismic design , basis dynamic loads and maintain { the calculated effective neutron { multiplication factor less than j p)
\
0.95. l iv) Analysis of the new and spent iv) A report exists and concludes fuel storage racks under design that the new and spent fuel racks basis dropped fuel assembly loads can withstand design basis will be performed. dropped fuel assembly loads and maintain the calculated effective neutron multiplication factor less than 0.95. I i
)
v 2.1.1-3 M llgl10LIS8 oNTAACCVev5Vt020101.wpt050198
1 i Certified Design Material l FUEL HANDLING AND REFUELING SYSTEM I
=-e Revision: 5 =
Effective: 5/8/98 1 *.ee Table 2.1.12 Component Name Tag No. Component Location Refueling Machine FHS-FH-01 Containment Fuel Handling Machine FHS-FH-02 Auxiliary Building ( Spent Fuel Storage kacks FHS-FS-20 Auxiliary Buildmg New Fuel Storage Racks FHS-FS-01 Auxiliary Building Fuel Transfer Tube FHS-FT-01 Auxiliary Building / Containment , O l O 21.1-4 WOMin@llSe o:VTAACSVev5Mt020101.wpf:050198
R Certified Design Material I l REACTOR COOLANT SYSTEM (^N Revision: 5 i
\ ) Effective: 5/8/98 2.1.2 Reactor Coolant System Design Description The reactor coolant system (RCS) removes heat from the reactor core and transfers it to the secondary side I of the steam generators for power generation. The RCS contains two vertical U-tube steam generators, I four canned motor reactor coolant pumps (RCPs), and one pressurizer.
The RCS is as shown in Figure 2.1.2-1 and the component locations of the RCS are as shown in Table 2.1.2-5.
- 1. The functional arrangement of the RCS is as described in the Design Description of this Section 2.1.2.
- 2. a) The components identified in Table 2.1.2-1 as ASME Code Section m are designed and constructed in accordance with ASME Code Section III requirements, b) The piping identified in Table 2.1.2-2 as ASME Code Section m is designed and constructed in accordance with ASME Code Section m requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.1.2-1 as ASME Code Section m meet ASME Code Section m requirements.
?
O I V b) Pressure boundary welds in piping identified in Table 2.1.2-2 as ASME Code Section III meet ASME Code Section m requirements.
- 4. a) The components identified in Table 2.1.2-1 as ASME Code Section m retain their pressure boundary integrity at their design pressure.
j b) The piping identified in Table 2.1.2-2 as ASME Code Section m retains its pressure boundary l integrity at its design pressure. l S. a) The seismic Category I equipment identified in Table 2.1.2-1 can withstand seismic design basis loads without loss of safety function. b) Each of the lines identified in Table 2.1.2-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss ofits functional capability. 6 Each of the as-built lines identified in Table 2.1.2-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line. l I \ V 2.1.2-1 W_ W85tiligh0US8 o:VTAACSVev520212a.wp6:1 b-050498 l l l
Certified Design Material REACTOR COOL. ANT SYSTEM .=C Revision: 5 - Effxtive: 5/8/98 i .
- 7. a) The Class 1E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perfonn the safety function.
b) The Class 1E components identified in Table 2.1.2-1 are powered from their respective Class IE divii. ion. c) Separation is provided between RCS Class 1E divisions. and between Class 1E divisions and non-Class IE cable.
- 8. The RCS provides the foMowing safety-related functions:
a) The pressurizer safety valves provide overpressure protection in accordance with Section III of the ASME Boiler and Pressure Vessel Code. b) The pressurizer safety valves operate with low flow at pressures near the valve set pressure. c) The reactor coolant pumps (RCPs) have a rotating inertia to provide RCS flow coastdown on loss of power to the pumps. d) Each RCP flywheel assembly can withstand a design overspeed condition. e) The RCS provides automatic depressurization during design basis events. f) The RCS provides emergency letdown during design basis events.
- 9. The RCS provides the following nonsafety-related functions:
a) The RCS provides circulation of coolant to remove heat from the core. b) The RCS provides the means to control system pressure. c) The pressurizer heaters trip after a signal is generated by the PMS.
- 10. Safety-related displays identified in Table 2.1.2-1 can be retrieved in the main control room (MCR).
I 1. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functi.ms. b) The valves identified in Table 2.1.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS. c) The valves identified in Table 2.1.2-1 c . having diverse actuation system (DAS) control perform an active safety function after receiving a signal from DAS. O M@0lJS8 oNTAAcsvevsao212a.wps:1b-oso 9
l I Certified Design Material l I A REACTOR COOLANT SYSTEM Revision: 5 7
~
( ) Effective: 5/8/98 1
- 12. a) The automatic depressurization valves identified in Table 2.1.2-1 perform an active safety-related i function to change position as indicated in the table. I b) After loss of motive power, the remotely operated valves identified in Table 2.1.2-1 assume the indicated loss of motive power position.
- 13. a) Controls exist in the MCR to trip the RCPs.
b) The RCPs trip after receiving a signal from the PMS. c) The RCPs trip after receiving a signal from the DAS.
- 14. Controls exist in the MCR to cause the components identified in Table 2.1.2-3 to perform the listed function.
- 15. Displays of the parameters identified in Table 2.1.2-3 can be retrieved in the MCR.
Inspections, Tests, Analyses,and Acceptance Criteria Table 2.1.2-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the RCS. o l C 2.1.2-3 W891$0llS8 o:VTAACSvev5WO212a.wp6:1b-050198
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Certified Design Material REACTOR COOLANT SYSTEM Zr ('N Revision: 5 T s V Effective: 5/8/98 i ,e. l Table 2.1.2 2 I ' ASME Code Leak Before Functional Capability Line Name Line Number Section III Break Required Hot legs RCS-1A01 A Yes Yes Yes RCS-LOOlB l Cold legs RCS-LOO 2A Yes Yes Yes RCS-LOO 2B RCS-IA02C RCS-IA02D Pressurizer Surge Line RCS-IA03 Yes Yes Yes ADS Inlet Headers RCS-LOO 4A/B Yes Yes Yes RCS-LD06A/B RCS-IA30A/B RCS-LO20A/B Safety Valve Inlet Piping RCS-LOO 5A Yes Yes Yes RCS-1A05B Safety Valve Discharge RCS-LOSOA/B Yes No Yes Piping RCS-LO51 A/B yg ADS First-stage Valve RCS-1A10A/B Yes No Yes
! Inlet Piping RCS-LOl1 A/B ADS Second-stage Valve RCS-IA21 A/B Yes Yes Yes l Inlet Piping RCS-1A22A/B ADS Third-stage Vale RCS-LO31 A/B Yes Yes Yes l Inlet Piping RCS-IA32A/B ES Outlet Piping RCS-LO12A/B Yes No Yes RCS-LO23A/B RCS-LO33A/B f
I RCS-LO34A/B RCS-1461 A/B RCS-LO63A/B RCS-IA64A/B RCS-L200A/B PXS-L130A/B ADS Fourth-stage inlet RCS-L133A/B Yes Yes Yes Piping RCS-L135A/B RCS-L136A/B RCS-L137A/B Pressurizer Spray Piping RCS-L110A/B Yes No No RCS-L212A/B RCS-L213 i RCS-L215 I l g I b 2.1.2-17 N SI D US8 c:VTAACSvevmit0212a.wp6:1 b-050198
Certified Design M:lerial REACTOR COOLANT SYSTEM -- Revision: 5 Effective: 5/8/98 - Table 2.1.2-3 Equipment Tag No. Display Control Function RCP 1 A Breaker (Status) ECS-ES-51 Yes - RCP I A Breaker (Status) ECS-ES-52 Yes - RCP IB Breaker (Status) ECS-ES-61 Yes - RCP IB Breaker (Status) ECS-ES-62 Yes - RCP 2A Breaker (Status) ECS-ES-53 Yes - RCP 2A Breaker (Status) ECS-ES-54 Yes - RCP 2B Breaker (Status) ECS-ES-63 Yes - RCP 2B Breaker (Status) ECS-ES-64 Yes - Pressurizer Heaters RCS-EM-03 Yes On/Off Pressurizer Heaters RCS-EH-04A Yes On/Off Pressurizer Heaters RCS-EH-04B Yes On'Off Pressurizer Heaters RCS-BH-04C Yes On/Off Pressurizer Heaters RCS-EH44D Yes On/Off Fourth-stage ADS Squib Valve RCS-PL-V004A Yes - (Position Indication) Fourth-stage ADS Squib Valve RCS-PL-V004B Yes - (Position Indication) Fourth-stage ADS Squib Valve RCS-PL-V004C Yes - (Position Indication) Fourth-stage ADS Squib Valve RCS-PL-V004D Yes - (Position Indication) Pressurizer Safety Valve RCS-PL-V005A Yes - (Position Indication) Pressurizer Safety Valve RCS-PL-V005B Yes - (Position Indication) Pressurizer Spray Valve RCS-PL-V110A Yes - (Position Indication) Note: Dash (-) indicates not applicable. O oNTAACSirev5\it0212a.wp6:1 19
Certified Design Material
,A REACTOR COOLANT SYSTEM Revision: 5 dM Effective: 5/8/98 li,*-
Table 2.1.2 3 (cont.) Equipment Tag No. Display Control Function Pressurizer Spray Valve RCS-PL-V110B Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-150A Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-150B Yes - l (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-150C Yes - (Position Indication) ' Reactor Vessel Head Vent Valve RCS-PL-150D Yes - (Position Indication) Note: Dash (-) indicates not applicable. r'N U i
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Certified Design Material REACTOR COOLANT SYSTEM Revision: 5 Effective: 5/8/98 Table 2.1.2 4 Inspections, Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. He functional arrangement of Inspection of the as-built system The as-built RCS is as described in the RCS is as described in the will be performed. the Design Description of this Design Description of this Section 2.1.2.
Section 2.1.2. 2.a) ne components identified in Inspection will be conducted of The ASME Code Section III design Table 2.1.2-1 as ASME Code the as-built components as reports exist for the as-built Section III are designed and documented in the ASME design components identified in constructed in accordance with reports. Table 2.1.2-1 as ASME Code ASME Code SectionIII Section III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME code Section IIIdesign Table 2.1.2-2 as ASME Code the as-built component as reports exist for the as-built piping Section IIIis designed and documented in the ASME design identified in Table 2.1.2-2 as ASME constructed in accordance with reports. Code Section III. ASME Code Section III requirements. 3.a) Pressure boundary welds in 3.a) Pressure boundary welds in A report exists and concludes that components identified in components identified in the ASME Code Section III Table 2.1.2-1 as ASME Code Table 2.1.2-1 as ASME Code requirements are met for non-Section III meet ASME Code Section III meet ASME Code destructive examination of pressure l Section III requirements. Section III requirernents. boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.1.2-2 boundary welds will be the ASME Code Section III as ASME Code Section III meet performed in accordance with the requirements are met for non-ASME Code Section III ASME Code Section III. destructive examination of pressure requirements. boundary welds. l l Ol. W Westinghouse 2.1.2-20 ! aum 0:\lTAACSvev.W10212a.wp6:1 b-050198 j 1
Certified Design Material i REACTOR COOLANT SYSTEM - r'~ Revision: 5 - C]/ Effective: 5/8/98 Table 2.1.2-4 (cont.) Inspections, Tests, Analyses,and Acceptance Criteria Design Commitment Inspections Tests, Analyses Acceptance Criteria 4.a) The components identified in A hydrostatic test will be A report exists and concludes that Table 2.1.2-1 as ASME Code performed on the components the results of the hydrostatic test of Section III retain their pressure required by the ASME Code the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.1.2-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.1.2-2 as ASME Code performed on the piping required the results of the hydrostatic test of Section III retains its pressure by the ASME Code SectionIIIto the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.1.2-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.1.2-1 can withstand equipment and valves identified Table 2.1.2-1 is located on the seismic design basis loads without in Table 2.1.2-1 are located on Nuclear Island. f'NI loss of safety function. the Nuclear Island. t ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a repon that the as. installed equipment verifying that the as-installed including anchorage is seisnscally equipment including anchorage is bounded by the tested or analyzed seismically bounded by the tested conditions. or analyzed conditions. 5.b) Each of the lines identified in Inspection will be performed for A report exists and concludes that Table 2.1.2-2 for which functional the existence of a report verifying each of the as-built lines identified capability is required is designed that the as-built piping meets the in Table 2.1.2-2 for which j to withstand combined normal and requirements for functional functional capability is required I seismic design basis loads without capability. meets the requirements for a loss ofits functional capability. functional capability. i q O i W Westinghouse o n csv e w sob l8 l l L-------_.---------.--_-- 1
Certified Design Material REACTOR COOLANT SYSTEM
- E Revision: 5 Effective: 5/8/98 i .e Table 2.I.2-4 (cont.)
Inspections, Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation report exists identified in Table 2.1.2-2 as the existence of an LBB and concludes that the LBB designed for LBB meets the LBB evaluation report or an evaluation acceptance criteria are met by the criteria, or an evaluation is report on the protection from as-built RCS piping and piping performed of the protection from dynamic effects of a pipe break. materials, or a pipe break evaluation the dynamic effects of a rupture of Certified Design Material, report exists and concludes that the line. Section 3.3, Nuclear Island protection from the dysuunic effects Buildings, contains the design of a line break is provided.
descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture. 7.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.1.2-1 as being combination of type tests and the Class IE equipment identified in qualified for a harsh environment analyses will be performed on Table 2.1.2-1 as being qualified for can withstand the environmental Class IE equipment located in a a harsh environment can withstand conditions that would exist before, harsh environment. the environmental conditions that during, and following a design would exist before, during, and basis accident without loss of following a design basis ac,:ident safety function for the time without loss of safety function for required to perform the safety the time required to perform the function. safety function. i 7.b) The Class IE components Testing will be performed on the A simulated test signal exists at the ( identified in Table 2.1.2-1 are RCS by providing a simulated test Class IE equipment identified in powered from their respective signal in each Class IE division. Table 2.1.2-1 when the assigned Class 1E division. Class 1E division is provided the test signal. 7.c) Separation is provided See Certified Design Material, See Certified Design Material, between RCS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. 8.a) The pressurizer safety valves i) Inspections will be conducted i) The sum of the rated capacities provide overpressure protection in to confirm that the value of the recorded on the valve ASME Code accordance with Section III of the vendor code plate rating is greater plates of the safety valves exceeds ASME Boiler and Pressure Vessel than or equal to system relief 800,000 lb/hr. Code. requirements. l ii) Testing and analysis in ii) A report exists and concludes accordance with ASME Code that the safety valves set pressure is Section III will be performed to 2485 psig 25 psi. determine set pressure. O NOME 80 o:VTAACSvev5Vt0212a.wp6:1 501
Certified Design Material REACTOR COOLANT SYSTEM T7 Revision: 5 " h Effective: 5/8/98 {
)
Table 2.1.2-4 (cont.) Inspections Tests Analyses,and Acceptance Criteria Design Commitment Inspections. Tests, Analyses Acceptance Criteria 8.b) The pressurizer safety valves Tests or type tests are performed A report exists and concludes that operate with low flow at pressures to correlate flow through the the safety valves operate in a stable near the valve set pressure. safety valves as a function ofinlet manner with a leakage rate greater pressure. or equal to 0.35 lbm/sec at a pressure below the valve full-open pressure. 8.c) The RCPs have a rotating Inspection of as-built RCP vendor The calculated rotating inertia of inertia to provide RCS flow data will be performed. each RCP is no less than 5000 lb-ft'. coastdown on loss of power to the pumps. 8.d) Each RCP flywheel assembly Shop testing of each RCP Each RCP flywheel assembly has can withstand a design overspeed flywheel assembly will be passed an overspeed condition of no condition. performed at the vendor facility at less than 125% of operating speed. overspeed conditions. 8.e) The RCS provides automatic i) A low pressure flow test and i) The calculated ADS piping flow depressurization during design associated analysis will be resistance from the pressurizer basis events. conducted to determine the total through the sparger with all valves piping flow resistance of each of each ADS group open is /N- ADS valve group connected to s 2.46E-6 ft/gpm 2.
- h. the pressurizer (i.e., ADS Stages 1-3) from the pressurizer through the outlet of the downstream ADS control valves.
The reactor coolant system will be at cold conditions with the pressurizer full of water. The normal residual heat removal pumps will be used to provide injection flowinto the RCS discharging through the ADS valves. Inspections and associated analysis of the piping flow paths from the discharge of the ADS valve groups connected to the pressurizer (i.e., ADS Stages 1-3) to the spargers will be conducted l to verify the linnoutings are consistent wit'.. the line routings used for d' i flow resistance calculav b LJ
\
M @0m o:VTAACSvev5\it0212a.wp6:1 501 l
Certified Design Material REACTOR COOLANT SYSTEM 2' Revision: 5 " Effective: 5/8/98 . i Table 2.1.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections. Tests Analyses Acceptance Criteria ii) Inspections and associated ii) The calculated flow resistance analysis of each fourth-stage ADS for each group of fourth-stage ADS valve group (four valves and valves and piping with all valves associated piping connected to open is s 3.30E-7 ft/gpm2. cach hot leg) will be conducted to verify the line routing is consistent with the line routing used for design flow resistance calculations. iii) Inspections of each fourth- iii) The flow area through each stage ADS valve will be fourth-stage ADS valve is 2 38 in 8. conducted to determine the flow area through each valve. iv) Type tests and analysis will iv) A report exists and concludes be performed to determine the that the effective flow area through effective flow area through each each stage 1 ADS valve a 4.6 in2 stage 1,2,3 ADS valve. and each stage 2,3 ADS valve is a 21 in2, v) Inspections of the elevation of v) The minimum elevation of the the ADS stage 4 valve discharge bottom inside surface of the outlet will be conducted. of these valves is greater than plant elevation i10 feet. vi) Inspections of the ADS stage vi) The discharge of the ADS stage 4 valve discharge will be 4 valves is directed into the steam conducted. generator compartments. vii) Inspection of each ADS vii) The flow area through the holes sparger will be conducted to in each ADS sparger is a 274 in2 , determine the flow area through the sparger holes. viii) Inspection of the elevation viii) The centerline of the of each ADS sparger will be connection of the sparger arms to conducted. the sparger hub is s 11.5 feet below the IRWST overflow level. 8.f)The RCS provides emergency Inspections of the reactor vessel A report exists and concludes that letdown during design basi; head vent valves and inlet and the capacity of the reactor vessel events. outlet piping will be conducted. head vent is sufficient to pass not less than 8.2 lbm/sec at 1250 psia in the RCS. O DE o:VTAACSVev5Mt0212a.wp6:1 5019 1
Certified Design M;terial REACTOR COOLANT SYSTEM R "
/~ ~N Revision: 5 '
- h Effective: 5/8/98 _
Table 2.1.2-4 (cont.) Inspections, Tests, Analyses,and Acceptance Criteria Design Commitroent Inspections, Tests, Analyses Acceptance Criteria 9.a) The RCS provides circulation Testing and analysis to measure . The calculated post.fuelload RCS of coolant to remove heat from the RCS flow with four reactor flow rate is 2193,200 gpm. core. coolant pumps operating at no-load RCS pressure and temperature conditions will be performed. Analyses to convert the measured pre-fuelload flow will be performed. This analysis accounts for flow measurement uncertainties. 9.b) The RCS provides the means i) Inspections will be performed i) Pressurizer heater backup groups to control system pressure. to verify the rated capacity of A and B each has a rated capacity of pressurizer heater backup groups at least 166 kW. A and B. ii) Tests will be performed to ii) Controls in the MCR operate to verify that the pressurizer spray cause the pressurizer spray valves to valves can open and close when open and close. operated from the MCR. (A) v 9.c) The pressurizer heaters trip after a signalis generated by the Testing will be performed to confirm trip of the pressurizer The pressurizer heaters identified in Table 2.1.2-3 trip after a signalis PMS. heaters identified in generated by the PMS. i Table 2.1.2-3.
- 10. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.1.2-1 can be retrievability of the safety-related Table 2.1.2-1 can be retrieved in the retrieved in the MCR. displays in the MCR. MCR. I 11.a) Controls exist in the MCR to i) Testing will be performed on i) Controls in the MCR operate to cause the remotely operated valves the squib valves identified in cause a signal at the squib valve identified in Table 2.1.2-1 to Table 2.1.2-1 using controls in electricalleads which is capable of perform active functions. the MCR without stroking the actuating the squib valve.
valve. ii) Stroke testing will be ii) Controls in the MCR operate to performed on the other remotely cause the remotely operated valves operated valves listed in (other than squib valves) to perform Table 2.1.2-1 using controls in active functions. the MCR. I m ld \ \ 1 2.1.2-25 1 W9Sdfigi100S8 oNTAACSvev5Vt0212a.wp6:1 b-050198 l l i L_____ ___
Certified Design Material REACTOR COOLANT SYSTEM ~ G~ i Revision: 5 ! Effective: 5/8/98 Table 2.1.2-4 (cont.) Inspections, Tests Analyses,and Acceptance Criteria Design Commitment Inspections Tests, Analyses Acceptance Criteria 11.b) The valves identif ed in i) Testing will be performed on i) "Ihe squib valves receive a signal Table 2.1.2-1 as having PMS the squib valves identified in at the valve electricalleads that is control perform an active safety Table 2.1.2-1 using real or capable of actuating the squib valve. function after receiving a signal simulated signals into the PMS 4 from the PMS. without stroking the valve. . j l ii) Testing will be performed on ii) The other remotely operated l the other remotely operated valves identified in Table 2.1.2-1 as 1 valves identified in Table 2.1.2-1 having PMS control perform the using real or simulated signals active function identified in the ' into the PMS. table after receiving a signal from PMS. iii) Testing will be performed to iii) These valves open within the demonstrate that remotely following times after receipt of an operated RCS isolation valves actuation signal: RCS-V001 A/B, V002A/B, V003A/B open within the V001A/B s 30 sec required response times. V002A/B, V003A/B s 80 see i V0ll A/B s 20 sec
! V012A/B. V013A/B s 30 sec 11.c) The valves identified in i) Testing will be performed on i) The squib valves receive a signal Table 2.1.2-1 as having DAS the squib valves identified in at the valve electricalleads that is control perform an active safety Table 2.1.2-1 using real or capable of actuating the squib valve.
function after receiving a signal simulated signals into the DAS from DAS. without stroking the valve. ii) Testing will be performed on ii) The other remotely operated the other remotely operated valves identified in Table 2.1.2-1 as valves identified in Table 2.1.2-1 having DAS control perform the using real or simulated signals active function identified in the into the DAS. table after receiving a signal from DAS. O [ W85tillgfl0US8 c:VTAACSVev5Vt020102.wp6:1 98
I Certified Design Material REACTOR COOT. ANT SYSTEM J=l Revision: 5
- I O)
! Effective: 5/8/98 i * *e Table 2.1.2-4 (cont.) ;
Inspections, Tests, Analyses,and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 12.a) The automatic i) Tests or type tests of motor- i) A test report exists and concludes depressurization valves identified operated valve.; will be performed that each motor-operated valve in Table 2.1.2-1 perform an active that demonstrate the capability of changes position as indicated in safety-related function to change the valve to operate under its Table 2.1.2-1 under design position as indicated in the table. design conditions. conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are bounded by the tests or motor-operated valves are type tests, bounded by the tests or type tests. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under pre-operational Table 2.1.2-1 under pre-operational flow, differential pressure and test conditions. temperature conditions. iv) Tests or type tests of squib iv) A test report exists and O valves will be performed that concludes that each squib valve demonstrate the capability of the changes position as indicated in valve to operate under its design Table 2.1.2-1 under design conditions. conditions. v) Inspection will be performed v) A report exists and concludes for the existence of a report that the as-installed squib valves are verifying that the as-installed bounded by the tests or type tests. squib valves are bounded by the tests or type tests. I vi) See item 8.e.i in this table. vi) See item 8.e.iin this table. The ADS stage 1-3 valve flow resistances are verified to be consistent with the ADS stage 1-3 path flow resistances. I vii) See item 8.e.iiin this table. vii) See item 8.e.ii in this table. The ADS stage 4 valve flow resistances are verified to be consistent with the ADS stage 4 path flow resistances. O V UDE oNTAACSirev5\it0212a.wp6:1 19 l I L E
Certified Design Material REACTOR COOLANT SYSTEM -
=
Revision: 5 Effective: 5/8/98 Table 2.1.2-4 (cont.) Inspections Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l viii) See item 8.e.iiiin this table. viii) See item 8.e.iii in this table. I ix) See item 8.c.iv in this table. i;.) See item 8.e.iv in this table. 12.b) After loss of motive power, Testing of the installed valves Upon loss of motive power, each the remotely operated valves will be performed under the remotely operated valve identified identified in Table 2.1.2-1 assume conditions ofloss of motive in Table 2.1.2-1 assumes the the indicated loss of motive power power. indicated loss of motive power position. position. 13.a) Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to trip trip the RCPs. RCPs using controls in the MCR. the RCPs. 13.b) The RCPs trip after Testing will be performed using The RCPs trip after receiving a receiving a signal from the PMS. real or simulated signals into the signal from the PMS. PMS. 13.c) The RCPs trip after Testing will be performed using The RCPs trip after receiving a receiving a signal from the DAS. real or simulated signals into the signal from the DAS. DAS.
- 14. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to cause the components identified in components in Table 2.1.2-3 cause the components listed in Table 2.1.2-3 to perform the listed using controls in the MCR. Table 2.1.2-3 to perform the listed function. functions.
- 15. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.1.2-3 can be retrievability of the RCS Table 2.1.2-3 can be retrieved in the retrieved in the MCR. parameters in the MCR. MCR.
O W Westinghouse 2.1.2-28 m oNTAACSVev5\h0212a.wp6:1b-050198
C:rtified Dealgn M:t: rill ( REACTOR COOLANT SYSTEM Revision: 5 f[ O Effective: 5/8/98
~
Table 2.1.2-5 Component Name Tag No. Component Location Steam Generator 1 RCS-MB-01 Containment Steam Generator 2 RCS-MB-02 Containment Reactor Coolant Pump 1 A RCS-MP41A Containment Reactor Coolant Pinnp IB RCS-MP-OlB Containment Reactor Coolant Pump 2A RCS-MP-02A Containment Reactor Coolant Pump 2B RCS-MP-02.B Containment Pressurizer RCS-MV-02 Containment ADS Sparger A PXS-MW-01A Containment ADS Sparger B PXS-MW-OlB Containment S O E oNTAACSVev5Vt0212a.wp6:1 501
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Certified Design M:t;ri:1 REACTOR SYSTEM ZC Revision: 5 O Effective: 5/8/98
=
1 - E e 2.1.3 Reactor System Design Description The reactor system (RXS) generates heat by a controlled nuclear reaction and transfers the heat generated to the reactor coolant, provides a barrier that prevents the release of fission products to the I atmosphere and a means to insert negative reactivity into the reactor core and to shutdown the reactor I core. I I The reactor core contains a matrix of fuel rods assembled into fuel assemblies using stmetural
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l elements. Rod cluster control assemblies (RCCAs) are positioned and held within the fuel assemblies I by control rod drive mechanisms (CRDMs). The CRDMs unlatch upon termination of electrical power I to the CRDM thereby releasing the RCCAs. The RXS is operated during normal modes of plant operation, including startup, power operation, cooldown, shutdown and refueling. q The component locations of the RXS are as shown in Table 2.1.3-3. I
- 1. The functional arrangement of the RXS is as described in the Design Description of this l Section 2.1.3.
I 2. a) The reactor upper intemals rod guide arrangement is as shown in Figure 2.1.3-1. b) The rod cluster control and drive rod arrangement is as shown in Figure 2.1.3-2. c) The reactor vessel arrangement is as shown in Figure 2.1.3-3. I
- 3. The components identified in Table 2.1.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
I 4. Pressure boundary welds in components identified in Table 2.1.3-1 as ASME Code Section III meet ASME Code Section III requirements. I
- 5. The pressure boundary components (reactor vessel [RV], control rod drive mechanisms [CRDMs],
incore instrument guide tubes) identified in Table 2.1.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure. I
- 6. The seismic Category I equipment identified in Table 2.1.3-1 can withstand seismic design basis loads without loss of safety function.
I
- 7. The reactor internals will withstand the effects of flow induced vibration.
I
- 8. The reactor vessel direct injection nor21e limits the blowdown of the reactor coolant system (RCS) following the break of a direct vessel injection line.
M@lSe 2.1.3-1 o:VTAACSVev5Vt020103.wpf:050498
Certified Design Material REACTOR SYSTEM 7-~~i~ Revision: 5 "E ! Effective: 5/8/98 }i e 1 9. a) *Ihe Class IE equipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety , function. ) b) The Class IE components identified in Table 2.1.3-1 are powered from their respective Class IE division. c) Separation is provided between RXS Class IE divisions, and between Class IE divisions and non-Class IE cable. I 10. The reactor lower internals assembly is equipped with holders for at least eight capsules for storing material surveillance specimens. I 11. The reactor pressure vessel (RPV) beltline material has a Charpy upper-shelf energy of no less than 75 ft-lb. I 12. Safety-related displays of the parameters identified in Table 2.1.3-1 can be retrieved in the main control room (MCR). I 13. The fuel assemblies and rod control cluster assemblies intended for initial core load and listed in i Table 2.1.3-1 have been designed and constructed in accordance with the principal design i requirements. Inspections, Tests, Analysis, and Acceptance Criteria Table 2.1.3-2 specifies the inspections, tests, analysis, and associated acceptance criteria for the RXS. M@Se 2.1.3-2 el o:VTAACSVev5Vt020103.wpf:050498
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Certified Design Material REACTOR SYSTEM " Revision: 5 Effective: 5/8/98 Table 2.1.3-2 Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections, Tests, Analysis Acceptance Criteria i 1. De functional arrangement of Inspection of the as-built system The as-built RXS conforms with I the RXS is as described in the will be performed. the functional arrangement as i Design Description of this described in the Design l Section 2.1.3. Description of this Section 2.1.3. I 2.a) The reactor upper internals Inspection of the as-built system The as-built RXS will rod guide arrangement is as will be performed. accommodate the fuel assembly shown in Figure 2.3.1-1. and control rod drive mechanism pattern shown in Figure 2.3.1-1. I 2.b) The rod cluster control and Inspection of the as-built system The as-built RXS will drive rod arrangement is as will be performed. accommodate the rod cluster shown in Figure 2.1.3-2. control and drive rod arrangement shown in Figure 2.1.3-2. l 2.c) The reactor vessel Inspection of the as-built system The as-built RXS will arrangement is as shown in will be performed. accommodate the reactor vessel Figure 2.1.3-3. arrangement shown in Figure 2.1.3-3. I 3. The components identified in Inspection will be conducted of The ASME Code Section III Table 2.1.3-1 as ASME Code the as-built components as design reports exist for the as-l Section III are designed and documented in the ASME design built components identified in j constructed in accordance wita reports. Table 2.1.3-1 as ASME Code l ASME Code Section III Section Ill. requirements. I 4. Pressure boundary welds in Inspection of as-built pressure A report exists and concludes that l components identified in boundary welds will be performed the ASME Code Section III Table 2.1.3-1 as ASME Code in accordance with the ASME requirements are met for non-( Section III meet ASME Code Code Section III. destructive examination of Section III requirements. pressure boundary welds. l 5. The pressure boundary A hydrostatic test will be A report exists and concludes that components (RV, CRDMs, incore performed on the components of the results of the hydrostatic test instrument guide tubes) retain the RXS required by the ASME of the pressure boundary their pressure boundary integrity Code Section III to be components (RV, CRDM's, at their design pressure. hydrostatically tested. incore instrument guide tubes) conform with the requirements of the ASME Code Section III. 1 0 2.1.3-6 UDM 0:VTAACSVev5Mt020103.wpf:050498 l 1 1 , i
Certified Design Mat: rial REACTOR SYSTEM i Revision: 5 E Effective: 5/8/98 l l Table 2.1.3-2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Comruitment Inspections, Tests, Analysis Acceptance Criteria 1 6. The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.1.3-1 can withstand equipment identified in Table 2.1.3-1 it located on the seismic design basis loads withou Table 2.1.3-1 is located on the Nuclear Island. loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as. installed including anchorage is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or analyzed conditions. or analyzed conditions. 1 7. The reactor internals will i) A vibration type test will be i) A report exists and concludes withstand the effects of flow conducted on the AP600 prototype that the prototype reactor
'nduced vibration. reactor internals. internals have no observable damage or loose parts as a result of the vibration type test.
ii) A pre-test inspection, a flow ii) The as-built reactor internals test and a post-test inspection will have no observeble damage or be conducted on the as-built loose parts, reactor internals. I 8. The reactor vessel direct An inspection will be conducted The throat area of the direct vessel injection nozzle limits the to verify the flow area of the flow vessel injection line nozzle flow blowdown of the RCS following limiting venturi within each direct limiting venturi is less than or the break of a direct vessel vesselinjection nozzle. equal to 12.57 in2, injection line. 2.1.3-7 M n@l0E0 o:VTAACSirev5\it020103.wpf:0SO498
Certified Design Material REACTOR SYSTEM . E- i l Revision: 5 j I l Effective: 5/8/98 _ 5 l Table 2.1.3-2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections, Tests, Analysis Acceptance Criteria 1 9.n) The Class IE equipment Type tests, analysis, or a A report exists and concludes that identified in Table 2.1.3-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analysis will be performed on in Table 2.1.3-1 as being environment can withstand the Class IE equipment located in a qualified for a harsh environment - environmental conditions that harsh environment. can withstand the environmental would exist befere, during, and conditions that would exist 1 following a design basis accident before, during, and following a without loss of safety function for design basis accident without loss j the time required to perform the of safety function for the time i safety function. required to pe-form the safety l function. j i 9.b) The Class IE components Testing will be performed by A simulated test signal exists for identified in Table 2.1.3-1 are providing simulated test signals in Class IE rquipment identified in I powered from their respective each Class IE division. Table 2.1.3-1 when the assigned Class IE division. Class IE division is provided the test signal. I 9.c) Separation is provided See Certified Design Material, See Certified Design Material, between RXS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. I 10. 'Ihe reactor lower internals inspection of the reactor lower At least eight capsules are in the assembly is equipped with holders internals assembly for the reactor lower internals assembly. for at least eight capsules for presence of capsules will be storing material surveillance performed. specimens. I 11. The RPV beltline material Testing of the Charpy V-Notch A report exists and concludes that has a Charpy upper-shelf energy specimen of the RPV beltline the initial RPV beltline Charpy of no less than 75 ft-Ib. material will be performed. upper-shelf energy is no less than 75 ft-lb. 1 i l 12. Safety-related displays of the Inspection will be performed for Safety-related displays identified parameters identified in retnevability of the safety-related in Table 2.1.3-1 can be retrieved Table 2.1.3-1 can be retrieved in displays in the MCR. in the MCR. the MCR. l l
)
l i O 2.1.3-8 T Westirighollse oNTAACSVev5Vt020103.wpf:050498 i
Certified Design Material l REACTOR SYSTEM i = :. (~g Revision: 5 - ' 4
- () Effective
- 5/8/98 1 .
e e. Table 2.1.3 2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Conunitment Inspections, Tests, Analysis Acceptance Criteria l 13. The fuel assemblies and rod An analysis is performed of the A report exists and conclndes that I control cluster assemblies reactor core design. the fuel assemblies and rod I intended for initial core load and cluster control rod assemblies I listed in Table 2.1.3-1 have been intended for the initial core load I designed and constructed in and listed in Table 2.1.3-1 have i accordance with the principal been designed and constructed in i design requirements. accordance with the principal i design requirements. G (/ J l l I o U l 2.1.3-9 3 Westinghouse o:vTAAesvevssito201os.wpr:ososea
l Certified Design Material REACTOR SYSTEM ;" Revision: 5 Effective: 5/8/98 ji H Table 2.1.3-3 Ccmponent Name Tag No. Component Location RV RXS-MV-01 Containment Reactor Upper Internals Assembly RX-MI-01 Containment Reactor Lower Internals Assembly RXS-MI-02 Containment Fuel Assemblies (145 locations) RXS-FA- Containment A04/A05/A06/A07/A08/A09/ A10/B03/B04/B05/B06/B07/ B08/B09/B10/B11/C02/C03/ C04/C05/C06/C07/C08/C09/ C10/C11/C12/D01/D02/D03/ D04/D05/D06/D07/D08/D09/ D10/Dll/D12/D13501E02/ E03E04E05E06/E07E08/ E09/E10/E11E12E13/F01/ F02/F03/F04/F05/F06/F07/F08/ F09/F10/F11/F12/F13/G01/ G02/G03/004/G05/G06/G07/ G08/G09/G10/G11/G12/G13/ H01/H02/H03/H04/H05/H06/ H07/H08/H09/H10/Hil/H12/ H13/J01/J02/J03/J04/J05/J06/ J07/J08/JO9/J10/Jil/J12/J13/ K01/K02/K03/K04/K05/K06/ K07/K08/K09/K10/K11/K12/ K13/LO2/LO3/LO4/LOS/LO6/ LO7/L08/LO9/L10/Lil/L12/ M03/M04/M05/M06/M07/ M08/M09/M10/M1I/N04/N05/ N06/N07/N08/N09/N10 Rod Cluster Control Assemblies RXS-FR- Containment (RCCAs) (minimum 45 locations) B04/B06/B08/B10/C05/ C07/C09/D02/D04/D06/D08/ D10/D12E03 Ell /F02/F04/ F06/F08/F12/G03/G07/ Gill H02/HG4/H06/H08/H10/H12/ J03/JlI/K02/K04/K06/K08/ K10/K12/LOS/LO7/M04/M06/ M08/M10 9 [ W85tingh00S8 o:VTAACSVev5Vt020103.wpf: 9
l l l Certified Design Material l REACTOR SYSTEM g 2; (q)
/ Revision: 5 Effective: 5/8/98 i Es ee Table 2.1.3-3 Component Name Tag No. Component Location Control Rod Drive Mechanisms RXS-MV. Containment (CRDMs)(61 Locations) II A07/llB04/ IIB 06/llB08/
11B10/11C03/11C05/11C07/ 11C09/11C11/11D02/1ID04/ 11D06/IID08/llD10/llD12/ 11E03/11E05/11E07/11E09/ 11El1/11F02/11F04/11F06/ 11F08/IIF10/llF12/IlG01/ 11G03/11G05/11G07/11G09/ 11011/11G13/11H02/11H04/ 11H06/11H08/lIH10/11H12/ 11J03/11J05/11J07/11J09/ 11J11/11K02/11K04/11K06/ 11K08/11K10/11K12/11LO3/ 1ILOS/l1LO7/11LO9/1IL11/ 11M04/11M06/11M08/l1M10/ 11N07 Incore Instrument Guide Tubes (38 IIS-JT- Containment [] Core Locations) G01 through G38 Source Range Detectors (4) RXS-JE-NE001A/NE001B/ Containment NE001C/NE001D Intermediate Range Detectors (4) RXS-JE-NE002A/NE002B/ Containment NE002C/NE002D Power Range Detectc,rs Lower (1) RXS-JE-hE003A/NE003B/ Containment NE003C/NE003D Power Range Detectors - Upper (4) RXS-JE-NE004A/NE004B/ Containment NE004C/NE004D
/'^s O
2.1.3-11 Westinghouse o:MTAACSVev5Vt020103.wpt:050498
Certified Design Material REACTOR SYSTEM ~ F#! ive: 5/8/98 E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E , M M M M M M M M M M M M M M M M M M M M M ROD GUIDE LOCATIONS FUEL ASSEMBLY PATTERN Reactor Upper Internals Rod Guide r ge t O, i j h Westinghouse m u esv m otos. [ _ - - - - \
Certified Design Material REACTOR SYSTEM * * =j"*
/^g Revision: 5
(
' ,/ Effective: 5/8/98 1 .e CROM REACTOR PRESSURE VESSEL D
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Certified Design Material CONTAINMENT SYSTEM Revision: 5 F -
!q ! Effective: 5/8/98 ]
v 2.2.1 Containment System Design Description The containment system (CNS) is the collection of boundaries that r,eparates the containment atmosphere from the outside environment during design basis accidents. The CNS is as shown in Figure 2.2.1-1 and the component locations of the CNS are as shown in Table 2.2.1-4,
- 1. The functional arrangement of the CNS and associated systems is as described in the Design Description of this Section 2.2.1.
- 2. a) He components identified in Table 2.2.1-1 as AShE Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping ider tified in Table 2.2.12 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.1-1 as ASME Code Section III meet ASME Code Section III requirements.
V b) Pressure boundary welds in piping identified in Table 2.2.1-2 as AShE Code Section III meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.2.1-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) He piping identified in Table 2.2.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. The seismic Category I equipment identified in Table 2.2.1-1 can withstand seismic design basis loads without loss of safety function.
l
- 6. a) He Class IE equipment identified in Table 2.2.1-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety fur.ction for the time required to perform the safety 4 function.
]
b) He Class IE components identified in Table 2.2.1-1 are powered from their respective Class IE division. l c) Separation is provideo between CNS Class 1E divisions, and between Class 1E divisions and ( non-Class IE cable. I v l 2.2.1-1 3 W8Stingh00S8 c:\rTAACSVev5\it020201.wpf;1b-050398
l l Certified Design Material l CONTAINMENT SYSTEM t~ Revision: 5 Effective: 5/8/98 I
- 7. The CNS provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere.
- 8. Conminment electrical penetration assemblies are protected against currents that are greater than the continuous ratings.
- 9. Safety-related displays identified in Table 2.2.1-1 can be retrieved in the main control room (MCR).
- 10. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions.
b) The valves identified in Table 2.2.1-1 as having protecnon and safety monitoring system (PMS) control perform an active function after receiving a signal from the PMS. c) The valves identified in Table 2.2.1-1 as having diverse actuation system (DAS) control perform an active function after receiving a signal from the DAS.
- 11. a) The motor-operated and check valves identified in Table 2.2.1-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.1-1 assume the indicated loss of motive power position. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.2.1-3 specifies the inspections, tests, analyses, and associated acceptance criteria for the CNS. l l l I O 2.2.1-2 M M@0M8 oNTAACSirev5\it020201.wpf:1b-oS0398
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r-Certified Design Material CONTAINMENT SYSTEM : l 7' Revision: 5 -. Effective: 5/8/98 I Table 2.2.12 ASME Code Line Name Line Number Section III l l Instrument Air In CAS-PL-L0l6 Yes Service Air In CAS-PL-L204 Yes Component Cooling Water Supply to Containment CCS-PL-L201 Yes Component Cooling Water Outlet from Containment CCS-PL-L207 Yes Demineralized Water In DWS-PL-L245 Yes Fire Protection Supply to Containment FPS-PL-L107 Yes Spent Fuel Pool Cooling Discharge SFS-PL-L017 Yes Spent Fuel Pool Cooling Suction from Containment SFS-PL-LO38 Yes I Containment Purge Inlet to Containment V: S-PL-L104 L105, L106 Yes 1 Containment Purge Discharge from Containment VFS-PL-L203, L2G4, L205 Yes { q Fan Cooler Supply Line to Containment VWS-PL-LO32 Yes Fan Cooler Return Line from Containment VWS-PL-LOSS Yes 1 RCDT Gas Out WLS-PL-LO22 Yes Waste Sump Out WLS-PL-LO73 Yes l l l i i i i b 2.2.1-9 WBSil!1gh0llS8 o:VTAACSVev5Mt020201.wpf:1 b-050398
Certified Design Material CONTAINMEN1 SYSTEM : H Revision: 5 i Effective: 5/8/98 - ! Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built CNS conforms with the CNS and associated systems will be performed. the functional arrangement as is as described in the Design described in the Design Description of this Section 2.2.1. Description of this Section 2.2.1.
2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.2.1-1 as ASME Code the as-built components as design reports exist for the as-Section III are designed and documented in the ASME design built components identified in constructed in accordance with reports. Table 2.2.1-1 as ASME Code ASME Code Section III Section III. requirements. 2.b)'Ihe piping identified in Inspection will be conducted of The ASME Code Section III Table 2.2.1-2 as ASME Code the as-built piping as documented design reports exist for the as-Section III is designed and in the ASME design reports. built piping identified in constmeted in accordance with Table 2.2.1-2 as ASIGE Code ASME Code Section III Section III, requirements. 3.a) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that components identified in boundary welds will be performed the ASME Code Section III Table 2.2.1-1 as ASME Code in accordance with the ASME requirements are met for non-Section III meet ASME Code Code Section III. destructive examination of Section III requirements, pressure boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.2.1-2 boundary welds will be performed the ASME Code Section III as ASME Code Section III meet in accordance with the ASME requirements are met for non-ASME Code Section III Code Section III. destructive examination of requirements. pressure boundary welds. O 2 2.1-10 UDU8 oNTAACS\rev5\it020201.wpf;1 t>O50398
l l l Certified Design Material CONTAINMENT SYSTEM p- l l r^x Revision: 5
- V Effective: 5/8/98 b l
Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptacte Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.a) The components identified in i) A hydrostatic or pressure test iii) A report exists and Table 2.2.I-1 as ASME Code will be performed on the concludes that the results of the j Section III retain their pressure components required by the pressure test of the components boundary integrity at their design ASME Code Section III to be identified in Table 2.2.1-1 as pressure. tested. ASME Code Section III conform i with the requirements of the ASME Code Section III. ii) Impact testing will be ii) A report exists and conc!udes performed on the containment and that the containment and pressure-retaining penetration p* essure-retaining penetration materials in accordance with the materials conform with fracture ASME Code Section III, toughness requirements of the Subsection NE, to confirm the ASME Code Section III. fracture toughness of the materials.
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4.b) The piping identified in A hydrostatic or pressure test will A report exists and concludes that Table 2.2.1-2 as ASME Code (k.; Section III retains its pressure be performed on the piping required by the ASME Code the results of the pressure test of the piping identified in boundary integrity at its design Section III to be pressure tested. Table 2.2.1-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code I Section III.
- 5. He seismic Category I i) Inspection will be performed to i) He seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.2.1-1 can withstand equipment and valves identified in Table 2.2.1-1 is located on the seismic design basis loads Table 2.2.1-1 are located on the Nuclear Island.
without loss of safety function. Nuclear Island, ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis dynamic loads without loss of safety function. iii) Inspection will be performed iii) The as-installed equipment for the existence of a report including anchorage is verifying that the as-installed seismically bounded by the tested equipment including anchorage is or analyzed conditions. seismically bounded by the tested or analyzed conditions. O) L. 2.2.1-11 WB5tillgh0US0 o:UTAACS\rev5\it020201.wpf:1 b-050398 l 1 w_______-
Certified Design Material CONTAINMENT SYSTEM 9 Revision: 5 i Effective: 5/8/98 Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 6.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.2.1-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.2.1-1 as being environment can withstand the Class lE equipment located in a qualified for a harsh environment environmental conditions that harsh environment. can withstand the environmental would exist before, during, and conditions that would exist following a design basis accident before, during, and following a without loss of safety function for design basis accident without loss the time required to perform the of safety function for the time safety function. required to perform the safety l function. I 6.b) The Class IE components Testing will be performed by A simulated test signal exists at identifbd in Table 2.2.1-1 are providing a simulated test signal the Class IE equipment identified powned from their respective in each Class IE division. in Table 2.2.1-1 when the Clas IE division. assigned Class IE division is provided the test signal. 6.c) Separation is provided See Certified Design Material, See Certified Design Material, between CNS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable.
- 7. The CNS provides the safety- i) A containment integrated leak i) The leakage rate from related function of containment rate test will be performed. containment for the integrated isolation for containment leak rate test is less than L,.
boundary integrity and provides a barrier against the release of ii) Testing will be performed to ii) The containment purge fission products to the demonstrate that remotely isolation valves close within atmosphere. operated containment isolation 20 seconds and all other valves close within the required containment isolation valves close response times. within 60 seconds upon receipt of an actuation signal. Oi l l 2.2.1-12 l g- W85tingt10US8 o:VTAACSVev5Mt020201.wpf:1 tK50398 i
j Certified Design Material l l CONTAINMENT SYSTEM v-O Revision: 5 = a (J ! Effective: 5/8/98 1 .ee Tal,le 2.2.1-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 8. Containment electrical An analysis for the as-built Analysis exists for the as-built penetration assemblies are containment electrical penetration containment electrical penetration protected against currents that are assemblies will be performed to assemblies and concludes that the greater than the continuous demonstrate (1) that the matimum penetrations are protected agaiust ratings. current of the circuits does not currents which a greater than exceed the continuous rating of their continuous natings.
the containment electrical penetration assembly, o-(2) that the circuits have redundant protection devices in series and that the redundant current protection devices are coordinated with the containment electrica! l penetration assembly's rated short ' circuit thermal capacity data and prevent current from exceeding the continuous current rating of the containment electrical (A) penetration assembly.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.1-1 can be retrievability of the safety-related in Table 2.2.1-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause those remotely operated on remotely operated valves cause remotely operated valves l valves identified in Table 2.2.1-1 identified in Table 2.2.1-1 using identified in Table 2.2.1-1 to to perform active functions. l the controls in the MCR. perform active safety functions. i 10.b) The valves identified in Testing will be performed on The remotely operated valves Table 2.2.1-1 as having PMS remotely operated valves listed in identified in Table 2.2.1-1 as control perform an active safety Table 2.2.1-1 using rul or having PMS control perform the function after receiving a signal simulated signals into the PMS. active function identified in the from the PMS. table after receiving a signal from PMS. 1 10.c) "Ihe valves '.dentified in Testing will be performed on The remotely operated valves ! Table 2.2.1-1 as having DAS remotely operated valves listed in identified in Table 2.2.1-1 as l control perform an active safety Table 2.2.1-1 using real or having DAS conuol perform the I function after receiving a signal simulated signals into the DAS. active function identified in the from DAS. table after receiving a signal from DAS. l O N. 2.2.1-13 W8Sdfl@0US8 oNTAACSVev5Nt020201.wpti b-050398
Certified Design Material CONTAINMENT SYSTEM &C; Revision: 5 - 2 l Effective: 5/8/98 i et Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 11.a) 'Ihe motor-operated and i) Tests or type tests of motor- i) A test report exists and check valves identified in operated valves will be performed concludes that each motor-Table 2.2.1-1 perform an active to demonstrate the capability of operated valve changes position safety-related function to change each valve to operate under design as indicated in Table 2.2.1-1 , position as indicated in the table. conditions. under design conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-verifying that the as-installed operated valves are bounded by motor-operated valves are the tests or type tests. bounded by the tests or type tests. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under preoperational Table 2.2.1-1 under pre-flow, differential pressure, and operational test conditions. temperature conditions. iv) Exercise testing of the check iv) Each check valve changes valves with active safety functions position as inidcated in Table identified in Table 2.2.1-1 will be 2.2.1-1. performed under preoperational test pressure, temperature and fluid flow conditions. I1.b) After loss of motive power, Testing of the installed valves will After loss of motive power, each the remotely operated valves be performed under the conditions remotely operated valve identified identified in Table 2.2.1-1 assume of loss of motive power. in Table 2.2.1-1 assumes the the indicated loss of motive indicated loss of motive power power position. position. Table 2.2.1-4 Component Name Tag.No. Component Location Containment Vessel CNS-MV-01 Shield Building 9 2.2.1 14 [ W85tingh0tlS8 c:\lTAACSirev5\it020201.wpf:1 b-OS0398
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i Certified Design Material l PASSIVE CONTAINMENT COOLING SYSTEM --=: l q Revision: 5
- 5 Effective: 5/8/98 i ..
2.2.2 Passive Containment Cooling System Design Description The passive containment cooling system (PCS) provides heat removal from the containment during design basis events. The PCS is as shown in Figure 2.2.2-1 and the component locations of the PCS are as shown in Table 2.2.2-4.
- 1. The functional arrangement of the PCS is as described in the Design Description of this Section 2.2.2.
- 2. a) The components identified in Table 2.2.2-1 as ASME Code Section m are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.2-2 as ASME Code Section m is designed and constructed in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.2-1 as ASME Code Section III meet ASME Code Section III requirements.
(^\ d b) Pressure boundary welds in piping identified in Table 2.2.2-2 as ASME Code Section m meet AShE Code Section m requirements.
- 4. a) The components identified in Table 2.2.2-1 as ASME Code Section W retain their pressure boundary integrity at their design pressure, b) The piping identified in Table 2.2.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.2.2-1 can withstand sekmic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.2-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability, c) The passive containment cooling ancillary water storage tank (PCCAWST) can withstand a seismic event.
- 6. a) The Class 1E equipment identified in Table 2.2.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety p function.
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Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM Revision: 5 Effective: 5/8/98 b) The Class IE components identified in Table 2.2.2-1 are powered from their respective Class IE division. c) Separation is provided between PCS Class IE divisions, and between Class 1E divisions and non-Class 1E cable.
- 7. The PCS provides the following safety-related functions:
a) The PCS provides the delivery of water to the outside of the containment vessel. b) The PCS provides wetting of the outside surface of the containment vessel. c) The PCS provides air flow over the outside of the containment shell by a natural circulation air flow path from the air inlets to the discharge structure. d) The PCS provides drainage of the excess water from the outside of the containment vessel through the two upper annulus drains. e) The PCS provides a flow path for long-term makeup to the passive containment cooling water storage tank (PCCWST). f) The PCS provides for long-term makeup from the PCCWST to the spent fuel pool.
- 8. The PCS provides the following nonsafety-related functions:
a) The PCS provides a PCCAWST initial inventory of cooling water for PCS delivery from hour 72 through day 7. b) The PCS provides the delivery of water from the PCCAWST to the PCCWST. c) The PCS provides water inventory for the fire protection system.
- 9. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the main control room (MCR).
- 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.2-1 to perform active functions.
b) The valves identified in Table 2.2.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS. c) The valves identified in Table 2.2.2-1 as having diverse actuation system (DAS) control perform an active safety function after receiving a signal from the DAS. O 2.2.2-2 M M S8 oNTAACSvev5W020202.wpf:oS0398
Certified Design Material , l l PASSIVE CONTAINMENT COOLING SYSTEM A= q Revision: 5 - M l Q Effective: 5/8/98 1 . e l 11. a) The motor-operated and check valves identified in Table 2.2.2-1 perform an active safety-l related function to change position as indicated in the table. b) After loss of motive power, the remotely operated valves identified in Table 2.2.2-1 assume the indicated loss of motive power position. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.2.2-3 specifies the inspections, tests, analyses, and associated acceptance criteria for the PCS. ( )
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Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM Revision: 5
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Effective: 5/W98 _ Table 2.2.2 2 Functional ASME Code Capability Line Name Line Number Section III Required PCCWST Discharge Lines PCS-PL-LO0IA/B/C/D Yes Yes PCCWST Discharge Crossconnect PCS-PL-LOO 2 Yes Yes Line PCCWST Discharge Header Lines PCS-PL-LOO 3A, LOO 3B Yes Yes Post-72-hour PCCWST Makeup PCS-PL-LOO 4 Yes Yes Supply Line Connection PCS-PL-LO51 Post-72-hour PCCWST Makeup PCS-PL-LO29 Yes Yes Supply Line PCS-PL-LOS4 Post-72-hour SFS Makeup PCS-PL-L0l7 Yes Yes PCS-PL-LO49 O O DU o:\lTAACSVev5\it020202 wpf 05M
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM - r'~T Revision: 5 E ) Q Effective: 5/8/98 _ . i Table 2.2.2-3 ; Inspections, Tests, Analyses, and Acceptance Criteria ' Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement Inspection of the as-built system The as-built PCS conforms with of the PCS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design l Section 2.2.2. Description of this Section 2.2.2.
{ 2.a) The components identified Inspection will be conducted of The ASME Code Section III l in Table 2.2.2-1 as ASME Code the as-built components as dcsign reports exist for the as-Section III are designed and documented in the ASME design built components identified in constructed in accordance with reports. Table 2.2.2-1 as ASME Code . ASME Code Section III Section III. I requirements. 1 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.2.2-2 as ASME Code the as-built piping as documented design reports exist for the as-Section III is designed and in the ASME design reports. built pipirg identified in constructed in accordance with Table 2.2.2-2 as ASME Code l { ASME Code Section III Sectior. III. { requirements. j 3.a) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that components identified in boundary welds will be performed the ASME Code Section III Table 2.2.21 as ASME Code in accordance with the ASME requirements are met for non-Section III meet ASME Code Code Section III. destructive examination of Section III requirements. pressure boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.2.2-2 boundary welds will be performed the ASME Code Section III as ASMS Code Section III meet in accordance with the ASME requirements are met for non-ASME Code Section III Code Section III. destructive examination of requirements, pressure boundary welds. 4.a) The components identified A hydrostatic test will be A report exists and concludes that in Table 2.2.21 as ASME Code performed on the components the results of the hydrostatic test Section III retain their pressure required by the ASME Code of the components identified in ; boundary integrity at their design Section III to be hydrostatically Table 2.2.2-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. I n i %./ 2.2.2-7 W8SININUS8 c:VTAACSVev5Vt020202.wpf:050399
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM =:= Revision: 5 . I Effective: 5/8/98 . I Table 2.2.2-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.2.2-2 as ASME Code perfonned on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code Section III to of the piping identified in 3 boundary integrity at its design be hydrostatically tested. Table 2.2.2-2 as ASME Code I pressure. Section III conform with the requirements of the ASME Code Section III. t' 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.2.2-1 can withstand equipment and valves identified in Table 2.2.2-1 is located on the seismic design basis loads Table 2.2.2-1 are located on the Nuclear Island. without loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) The report exists and for the existence of a report concludes that the as-installed verifying that the as-installed equipment including anchorage is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or analyzed conditions. or analyzed conditions. 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that in Table 2.2.2-2 for which the existence of a report each of the as-built lines functional capability is required concluding that the as-built piping identified in Table 2.2.2-2 for is designed to withstand meets the requirements for which functional capability is combined normal and seismic functional capability. required meets the requirements design basis loads without a loss for functional capability. of its functional capability. 5.c) 'Ihe PCCAWST can Inspection will be performed for A report exists and concludes that withstand a seismic event. the existence of a report verifying the as-installed PCCAWST and that the as-installed PCCAWST its anchorage are designed using and its anchorage are designed seismic Category II methods and using seismic Category II methods criteria. and criteria. O E Westinghouse omTAAesv.vswmmm.wp I 1 1 l
) I l Certified Design Material I l I l PASSIVE CONTAINMENT COOLING SYSTEM EE _ Flevislen: 5 E! 1,A) Effective: 5/8/98 l Table 2.2.2 3 (cont.) Inspections, Test:,, Analyses, and Areptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 6.a) He Class IE equipment Type tests or a combination of A report exists and concludes that identified in Table 2.2.2-1 as type tests and analyses will be the Class IE equipment identified being qualified for a harsh performed on Class IE equipment in Tables 2.2.2-1 as being environment can withstand the located in a harsh environment. qualified for a harsh environment ,, environmental conditions that can withstand the environmental would exist before, during, and conditiens that would exist before, following a design basis accident during, and following a design without loss of safety function basis accident without loss of for the time required to perform safety function for the time the safety function. required to perform the safety function. 6.b) He Class IE components Testing will be performed by A simulated test signal exists at identified in Table 2.2.2-1 are providing a simulated test signal the Class IE equipment identified powered from their respective in each Class IE division. in Table 2.2.2-1 when the Class IE division. assigned Class IE division is provided the test signal, [ j n 6.c) Separation is provided See Certified Design Material, See Certified Design Material, b' between PCS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildmgs. Buildings. and non-Class IE cable. o 2.2.2 9 W6Stingh00S6 o:\lTAACS\rev5Mt020202.wpf:050398
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM Revision: 5 Effective: 5/8/98 Table 2.2.2 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.a) 'Ihe PCS provides the i) Testing will be pt . '..med to i) When tested separately, each delivery of water to the outside measure the PCCWST delivery of the two flow paths delivers of the containment vessel. rate from each of the two parallel greater than or equal to: flow paths.
- 442 gpm at a PCCWST water level of 23.75 ft 0.25 ft above the lowest standpipe b,' -
122 gpm at a PCCWST wa:er level of 20.65 ft c 0.25 ft above the lowest standpipe
- 71.5 gpm at a PCCWST water level of 13.55 ft 0.25 ft above the lowest standpipe.
ii) Testing and or analysis will be ii) When tested and/or analyzed performed to demonstrate the with both flow paths delivering PCWST inventory provides and an initial water level at 72 hours of cooling. 24.25 + 0.25, - 0.00 ft, the water inventory provides greater than or equal to 72 hours of flow with a flow rate greater than or equal to 62 gpm. iii) Inspection will be performed iii) The elevations of the to determine the PCCWST standpipes above the bottom standpipes elevations. standpipe are: 6.7 ft 0.25 ft 14.2 ft 0.25 ft
- 21.7 ft 0.25 ft O
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Certified Design Material PASSIVE Col 4TAINMENT COOLING SYSTEM = 2
= E m Revision: 5
( ) Effective: 5/8/98 i * . e e. V l Table 2.2.2 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 7.b) 7he PCS provides wetting i) Testing will be performed to i) A report exists and concludes of the outside surface of the measure the wetted surface of the that with water in the PCCWST containment vessel. containment vessel from either of at the following levels, water the two parallel flow paths to the delivery to the containment shell containment vessel. provides coverage measured at the spring line that is equal to or greater than the corresponding coverage used to calculate peak containment pressure in the safety , analysis, i l
- 23,75 0.25 ft above the
{' lowest standpipe
- 20.65 0.25 ft above the lowest standpipe i
- 13.55 2 0.25 ft above the lowest standpipe (q ) ii) Inspection of the containment ii) A report exists and concludes )
exterior coating will be conducted. that the containment exterior surface is coated with an 1 inorganic zinc coating. 7.c) The PCS provides air flow Inspections of the air flow path Flow paths exist at each of the l over the outside of the segments will be performed. following locations: { containment shell by a natural circulation air flow path from the - Air inlets air inlets to the discharge - Base of the outer annulus i structure. - Base of the inner annulus l
- Discharge structure 7.d) The PCS provides drainage Testing will be performed to With a water level within the of the excess water from the verify the upper annulus drain upper annulus 10" 1" ebove the ,
outside of the containment vessel flow performance. annulus drain inlet, the flow rate l through the two upper annulus through each drain is greater than drains. or equal to 450 gpm. l ( l l; (3 i V 2.2.2 11 l [ W85tiflghotise o:VTAACS\rev5Vt020202.wpf:050398
r f Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM Revision: 5 f=]
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Effective: 5/8/98 . e/ Table 2.2.2-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.e) ne PCS provides a flow i) See item I in this table. i) See item I in this table. path for long-term makeup to the PCCWST. ii) Testing will be perfonned to ii) With a water supply measure the delivery rate from the connected to the PCS long-term , long-term makeup connection to makeup connection, each PCS the PCCWST. recirculation pump delivers greater than or equal to 62 gpm when tested separately. 7.f) ne PCS provides for long- i) Testing will be performed to i) With the PCCWST water level term makeup from the PCCWST measure the delivery rate from the at 23.75 ft 0.5 ft above the to the spent fuel pool. PCCWST to the spent fuel pool. bottom of the tank, the flow path l from the PCCWST to the spent fuel pool delivers greater than or equal to 50 gpm. ii) Inspection of the PCCWST ii) The volume of the PCCWST will be perfomied. is greater than 400,000 gallons. 8.a) ne PCS provides a Inspection of the PCCAWST will The volume of the PCCAWST is PCCAWST initial inventory of be performed. greater than 363,000 gallons. cooling water for PCS delivery from hour 72 through dr.y 7. 8.b) He PCS provides the Testing will be performed to With PCCASWST aligned to the delivery of waer from the measure the delivery rate from the suction of the recirculation PCCAWST to the PCCWST. PCCAWST to die PCCWST. pumps, each pump delivers greater than or equal to 62 gpm when tested separately. 8.c) The PCS provides water See Certified Design Material See Certified Design Material, inventory for the fire protection subsection 2.3.4, Fire Protection subsection 2.3.4, Fire Protection system. System. System.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.2-1 can be retrievability of the safety-related in Table 2.2.2-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause the remotely operated on the remotely operated valves cause remotely operated valves valves identified in Table 2.2.2-1 identified in Table ? 2.2-1 using identified in Table 2.2.2-1 to to perform active functions. the controls in the MCR. perform active functions. O 2.2.2-12 W85tiligt10USB o:MTAACSVev5Mt020202.wpf:050798
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM ~ " ( Revision: 5 V] Effective: 5/8/98 _
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Table 2.2.2 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitmut Inspections, Tests, Analyses Acceptance Criteria 10 b) The valves identified in Testing will be performed on the The remotely operated valves Table 2.2.2-1 as having PMS remotely operated valves in identified in Table 2.2.2-1 as control perform an active safety Table 2.2.2-1 using real or having PMS control perform the function after receiving a signal simulated signals into the PMS. active function identified in the from the PMS. table after receiving a signal from the PMS. 4 10.c) The valves identified in Testing will be performed on the The remotely operated valves j Table 2.2.2-1 as having DAS remotely operated valves listed in identified in Table 2.2.2-1 as ! control perform an active safety Table 2.2.2-1 using real or having DAS control perform the function after receiving a signal simulated signals into the DAS. active function identified in the from the DAS. table after receiving a signal from 4 the DAS. 1 11.a) The motor-operated and i) Tests or type tests of motor- l i) A test report exists and - check valves identified in operated valves will be performed concludes that each motor-Table 2.2.21 perform an active to demonstrate the capability of operated valve changes position safety-related function to change the valve to operate under its as indicated in Table 2.2.21
- position as indicated in the table. design conditions under design conditions.
v} ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-verifying that the as-installed operated valves are bounded by motor-operated valves are bounded the tested conditions. by the tested conditions. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under preoperational Table 2.2.21 under preoperational flow, differential pressure, and test conditions. 1 temperature conditions. iv) Exercise testing of the check iv) Each check valve changes valves with active safety functions position as indicated in identified in Table 2.2.2-1 will be Table 2.2.2-1. performed under preoperational test pressure, temperature and fluid flow conditions. 11.b) After loss of motive Testing of the installed valves will After loss of motive power, each power, the remotely operated be performed under the conditions remotely operated valve identified valves identified in Table 2.2.2-1 of loss of motive power. in Table 2.2.2-1 assumes the assume the indicated loss of indicated loss of motive power motive power position. position. lv2 2.2.2-13 UIIblIS8 oNTAACSVev5ht020202.wpf:050398
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM .t= 'd
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Revision: 5 Effective: 5/8/98 1 . ea l Table 2.22-4 Component Name Tag No. Component Location PCCWST PCS-MT-01 Shield Building PCCAWST PCS-MT-05 Yard Recirculation Pump A PCS-MP-01A Auxiliary Building Recirculation Pump B PCS-MP-OlB Auxiliary Building O O w =Saa- _ _._ _ = :
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Certified Design Material PASSIVE CORE COOLING SYSTEM ~ * - A Revision: 5 - E I ) Effective: 5/8/98 V . e j 2.2.3 Passive Core Cooling System Design Description The passive core cooling system (PXS) provides emergency core cooling during design basis events. I The PXS is as shown in Figure 2.2.3-1 and the component locations of the PXS are as shown in Table 2.2.3-5.
- 1. The functional arrangement of the PXS is as described in the Design Description of this Section 2.2.3.
- 2. a) The components identified in Table 2.2.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements, b) The piping identified in Table 2.2.3-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundasy welds in components identified in Table 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.
(~N b) Pressure boundary welds in piping identified in Table 2.2.3-2 as ASME Code Section III l () meet ASME Code Section III requirements. l
- 4. a) The components identified in Figure 2.2.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Figure 2.2.3-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.3-2 for which functional capability is required is designed to withstand cc,mbined normal and seismic design basis loads without a loss of its functional capability.
- 6. Each of the as-built lines identified in Table 2.2.3-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
- 7. a) The Class IE equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required 7 to perform the safety function.
2.2.3-1 [ W85tingil00S8 o:VTAACSVev5Nt020203.wpf:1 twos 0198
Certified Design Material PASSIVE CORE COOLING SYSTEM Revision: 5 : Effective: 5/8/98 _ b) The Class IE components identified in Table 2.2.3-1 are powered from their respective Class 1E division. c) Separation is provided between PXS Class IE divisions, and between Class IE divisions and non-Class IE cable.
- 8. The PXS provides the following safety-related functions:
a) The PXS provides containment isolation of the PXS lines penetrating the containment. b) The PRHR HX provides core decay heat removal during design basis events. c) The CMTs, accumulators, in-containment refueling water storage tank (IRWST) and containment recirculation provide reactor coolant system (RCS) makeup, boration, and safety injection during design br. sis events. d) The PXS provides pH adjustment of water flooding the containment following design basis accidents.
- 9. He PXS has the following features:
I a) The PXS provides a function to cool the outside of the reactor vessel during a severe I accident. b) The accumulator discharge check valves (PXS-PL-V028A/B and V029A/B) are of a different check valve type than the CMT discharge check valves (PXS-PL-V016A/B and V017A/B).
- 10. Safety-related displays of the parameters identified in Table 2.2.3-1 can be retrieved in the main control room (MCR).
- 11. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.3-1 to perform their active function (s).
b) The valves identified in Table 2.2.3-1 as having protection and safety monitoring system (PMS) control perform their active function after receiving a signal from the PMS. c) The valves identified in Table 2.2.3-1 as having diverse actuation system (DAS) control perform their active function after receiving a signal from the DAS.
- 12. a) The motor-operated and check valves identified in Table 2.2.3-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.3-1 assume the indicated loss of motive power position. I DN o:VTAACSVev5Vt020203.wpf:1 9 i w
Certified Desigt. Material PASSIVE CORE COOLING SYSTEM p Revision: 5 4' = -- 2 Effective: 5/8/98 i .s
- 13. Displays of the parameters identified in Table 2.2.3-3 can be retrieved in the MCR.
Inspection, Tests, Analyses, and Acceptance Criteria Table 2.2.3-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the PXS. O l l 2.2.3-3 [ W85tiflgh00S8 c:VTAACSvev5Vt020203.wpf:1 t> 050198
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Certified Design Material l PASSIVE CORE COOLING SYSTEM f=5 A Revision: 5 5 5 i Effective: 5/8/98 !.,ee Table 2.2.3 3 Equipment Tag No. Display Control Function CMT A Discharge Isolition Valve PXS-PL-V014A Yes (Position) - (Position) CMT B Discharge Isolation Valve PXS-PL-V014B Yes (Position) - (Position) CMT A Discharge Isolation Wlve PXS-PL-V015A Yes (Position) - (Position) CMT B Discharge Isolation Valve PXS-PL-VOISB Yes (Position) - (Position) Accumulator A Nitrogen Vent Valve PXS-PL-V021 A Yes (Position) - (Position) Accumulator B Nitrogen Vent Valve PXS-PL-V021B Yes (Position) - (Position) Accumulator A Discharge Isolation Valve PXS-PL-V027A Yes (Position) - (Position)
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Accumulator B Discharge Isolation Valve PXS-PL-V027B Yes (Position) - (Position) PRHR HX Control Valve (Position) PXS-PL-V108A Yes (Position) - PRHR HX Control Valve (Position) PXS-PL-V108B Yes (Position) - Containment Recirculation A Isolation PXS-PL-VI 18A Yes (Position) - Valve (Position) Containment Recirculation B Isolation PXS-PL-V118B Yes (Position) - Valve (Position) Containment Recirculation A Isolation PXS-PL-V120A Yes (Position) - Valve (Position) Containment Recirculation B Isolation PXS-PL-V120B Yes (Position) - Valve (Position) IRWST Line A Isolation Valve (Position) IXS-PL-V121 A Yes (Position) - IRWST Line B Isolation Valve (Position) PXS-PL-V121B Yes (Position) -
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1RWST Injection A Isolation Squib PXS-PL-V123A Yes (Position) - l (Position) { Note: Dash (-) indicates not applicable. O V 2.2.3-13 1 MIINllS8 o:VTAACSvev5\it020203.wpf:1 b-050198
Certified Design Material PASSIVE CORE COOLING SYSTEM It-*; Revision: 5 9 Effective: 5/8/98 Table 2.2.3-3 (cont.) Equipment Tag No. Display Control Function IRWST Injection B Isolation Squib PXS-PL-V123B Yes (Position) - (Position) IRWST Injection A Isolation Squib PXS-PL-V125A Yes (Position) - (Position) IRWST Injection B Isolation Squib PXS-PL-V125B Yes (Position) - (Position) IRWST Gutter Bypass Isolation Valve PXS-PL-V130A Yes (Position) - (Position) IRWST Gutter Bypass Isolation Valve PXS-PL-V130B Yes (Position) - (Position) Accumulator A Level Sensor PXS-021 Yes - Accumulator B Level Sensor PXS-022 Yes - Accumulator A Level Sensor PXS-023 Yes - Accumulator B Level Sensor PXS-024 Yes - PRHR HX Inlet Temperature Sensor PXS-064 Yes - IRWST Surface Temperature Sensor PXS-041 Yes - IRWST Surface Temperature Sensor PXS-042 Yes - IRWST Bottom Temperature Sensor PXS-043 Yes - IRWST Bottom Temperature Sensor PXS-044 Yes - Note: Dash (-)indicaes not applicable. I O 2.2.3-14 E8dD M 0 o:VTAACSVev5\it020203.wpf:1 b-050198 I i
Certified Design Material A PASSIVE CORE COOLING SYSTEM Revision: 5 yy E-
) Effective: 5/8/98 1 -
ea Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria I. The functional arrangement of Inspectior, of the as-built system he as-built PXS conforms with the PXS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.2.3. Description of this Section 2.2.3. 2.a) The components identified Inspection will be conducted of The ASME Code Section III in Table 2.2.3-1 as ASME Code the as-built components as design reports exist for the as-built Section III are desigr ed and documented in the ASME design components identified in constructed in accordance with reports. Table 2.2.3-1 as ASME Code ASME Code Section III Section III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.2.3-2 as ASME Code the as-built piping as design reports exist for the as-built Section III is designed and documented in the ASME design piping identified in Table 2.2.3-2 constructed in accordance with reports. as ASME Code Section III. ASME Code Section III requirements. 3 3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes that (V components identified in Table 2.2.3-1 as ASME Code pressure boundary welds will be performed in accordance with the ASME Code Section III requirements are met for non-Section III meet ASME Code the ASME Code Section III. destructive examination of pressure Section III requirements, boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built A report exists and concludes that piping identified in Table 2.2.3-2 pressure boundary welds will be the ASME Code Section III as ASME Code S:ction III meet perfonned in accordance with requirements are met for non-ASME Code Section III the ASME Code Section III. destructive examination of pressure requirements. boundary welds. l _.Y 2.2.3-15 W WBSdligh0!JS8 o-VTAACSVev5Mt020203.wpf:1b-050198 1 l l
Certified Design Material PASSIVE CORE COOLING SYSTEM - -- Revision: 5 :l Effective: 5/8/98 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Comnitment Inspections, Tests, Analyses Acceptance Criteria 4.a) The components identified A hydrostatic test will be A report exists aad concludes that in Figure 2.2.3-1 as ASME Code performed on the components the results of the hydrostatic test of Section III retain their pressure required by the ASME Code the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.2.3-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Figure 2.2.3-2 as ASME Code performed on the piping required the results of the hydrostatic test of Section III retains its pressure by the ASME Code Section III the piping identified in boundary integrity at its design to be hydrostatically tested. Table 2.2.3-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed i) The seismic Category I equipment identified in to verify that the seismic equipment identified in Table 2.2.3-1 can withstand Category I equipment and valves Table 2.2.3-1 is located on the seismic design basis loads identified in Table 2.2.3-1 are Nuclear Island. without loss of safety function, located on the Nuclear Island. ii) Type tests, analyses, or a ii) A repon exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis dynamic loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the r.s-installed including anchorage is seismically equipment including anchorage bounded by the tested or analyzed j is seismically bounded by the conditions. tested or analyzed conditions. 5.b) Each of the lines identified Inspection will be performed A report exists and concludes that I in Table 2.2.3-2 for which verifying that the as-built piping each of the as-built lines identified functional capability is required is meets the requirements for in Table 2.2.3-2 for which designed to withstand combined functional capability. functional capability is required normal and seismic design basis meets the requirements for loads without a loss of its functional capability. functional capability. 1 0 2.2.3-16 W85tiligh0llSe oNTAACS\rev5\it020203 wpf:1t> 050198
Certified Design Material [ PASSIVE CORE COOLING SYSTEM Revision: 5 7"") : {Q) Effective: 5/8/98 _ Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation report exists identified in Table 2.2.3-2 as the existence of an LBB and concludes that the LBB {
designed for LBB meets the LBB evaluation report or an acceptance criteria are met by the criteria, or an evaluation is { evaluation report on the as-built RCS piping and piping j performed of the protection from protection from dynamic effects materials, or a pipe break j the dynamic effects of a rupture of a pipe break. Certified evaluation report exists and 1 of the line. Design Material, Section 3.3, concludes that protection from the Nuclear Island Buildings, dynamic effects of a line break is contains the design descriptions provided, and inspections, tests, analyses, I and acceptance criteria for ) protection from the dynamic
)
effects of pipe rupture. 7.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that I identified in Table 2.2.3-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be perfonned on
)
in Table 2.2.3-1 as being qualified i environment can withstand the Class IE equipment located in a for a harsh environment can j ( ) environmental conditions that - harsh environment. withstand the environmental V would exist before, during, ed conditions that would exist before, following a design basis accident during, and following a design I without loss of safety function for basis accident without loss of the tire required to perform the safety function for the time safety function. required to perform the safety function. 7.b) The Class IE components Testing will be performed by A simulated test signal exists at the identified in Table 2.2.3-1 are providing a simulated test signal Class IE equipment identified in powered from their respective in each Class IE division. Table 2.2.3-1 when the assigned Class IE division. Class IE division is provided the test signal. 7.c) Separation is provided See Certified Design Material, See Certified Design Material, between PXS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. 8.a) The PXS provides See Certified Design Material, See Certified Design Material, containment isolation of the PXS subsection 2.2.1, Containment subsection 2.2.1, Containment lines penetrating the containment. System. System. I
- }
l 2.2.347 W== Westinghouse o:\lTAACS\rev5\it020203.wpf:1b-OS0198
I l l Certified Design Material ! I PASSIVE CORE COOLING SYSTEM ~
---- I Revision: 5 Y )
Effective: 5/8/98 1 .
.et I
Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l l 8.b) The PXS provides core A heat removal performance test A report exists and concludes that decay heat removal during design and analysis of the PRHR HX the PRHR HX heat transfer rate
)
basis events. will be performed to determine with the design basis number of < the heat transfer from the HX. PRHR HX tubes plugged is: For the test, the reactor coolant hot leg temperature will be 21.06 x 108Bru/hr with 520 F initially at 2 540'F with the HL and 120'F IRWST reactor coolant pumps stopped. temperatures The IRWST water level for the test will be above the top of the 2 4.34 x 107Btu /hr with 420*F HX. The IRWST water HL and 212*F IRWST temperature is not specified for temperatures the test. The test will continue until the hot leg temperature decreases below 420 F. 8.c) The PXS provides RCS i) A low-pressure injection test i) The injection line flow makeup, boration, and safety and analysis for each CMT, each resistance from each source is as injection during design basis accumulator, each IRWST follows: events. injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve (s) in the line being tested. Test fixtures may be used to simulate squib valves. CMTs: CMTs: Each CMT will be initially filled The calculated flow resistance with water. All valves in these between each CMT and the lines will be open during the reactor vessel is test. 2 3.07 x 10 5 ft/gpm2 and 5 3.84 x 10-5 ft/gpm2, Accumulators: Accumulators: Each accumulator will be The calculated flow resistance partially filled with water and between each accumulator and pressurized with nitrogen. All the reactor vessel is 21.49 x 10-5 valves in these lines will be ft/gpm2 and s 1.86 x 10-5 ft/gpm2, open during the test. Sufficient flow will be provided to fully open the check valves. O 2.2.3-18 g_ W8Stirighouse o:VTAACSirev5Vt020203.wpf:1b-050198
Certified Dezign M:tirial PASSIVE CORE COOLING SYSTEM Revision: 5 F""C O Effective: 5/8/98 i
.ee ZE Table 2.2.3-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria IRWST Injection: IRWST Injection: The IRWST will be partially The calculated flow resistance filled with water. All valves in for each IRWST injection line these lines will be open during between the IRWST and the the test. Sufficient flow will be reactor vessel is 21.33 x 10 -5 provided to fully open the check 2 ft/gpm and valves. 5 2.66 x 10 5 ft/gpm2, Containment Recirculation: Containment Recirculation: A temporary water supply will The calculated flow resistance for be connected to the recirculation each containment recirculation lines. All valves in these lines line between the containment will be open during the test, and the reactor vessel is Sufficient flow will be provided 5 2,17 x 10 5 ft/gpm2, to fully open the check valves. ii) A low pressure test and ii) The flow resistance from analysis will be conducted for the cold leg to the CMT is O each CMT to determine piping flow resistance from the cold leg to the CMT. The test will be 5 7.69 x 104 ft/gpm2, performed by filling the CMT via the cold leg balance line by operating the normal residual heat removal pumps. W85tingh0llS8 2.2.3-19 c:VTAACSvev5Vt020203.wpf;1b-050198
Certified Design Material PASSIVE CORE COOLING SYSTEM a: =L Revision: 5 -
=
Effective: 5/8/98 . .ee l l Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria iii) Inspections of the routing of iii) These lines have no downward the following pipe lines will be sloping sections between the conducted: connection to the RCS and the high point of the line.
- CMT inlet line, cold leg to high point
- PRHR HX inlet line, hot leg to high point iv) Inspections of the elevation iv) The maximum elevation of the of the following pipe lines will top inside surface of these lines is ,
be conducted: less than the elevation of: I
- IRWST injection lines; - IRWST bottom inside surface IRWST connection to DVI nozzles
- Containment recirculation - IRWST bottom inside sur4ce l lines; containment to IRWST {
lines
- CMT discharge lines to DVI - CMT bottom inside surface connection !
- PRHR HX outlet line to SG - PRHR HX lower channel head connection top inside surface v) Inspections of the elevation v) The elevation of the bottom of the following tanks will be inside tank surface is higher than conducted: the direct vessel injection nozzle centerline by the following:
- CMTs - CMTs 2 7.5 ft
- IRWST - IRWST 2 3.4 ft vi) Inspections of each of the vi) The calculated volume of each ,
following tanks will be of the following tanks is as l conducted: follows:
- CMTs - CMTs 2 2000 ft 3
- Accumulators - Accumulators 2 2000 ft 3 l
- IRWST - IRWST 2 75,000 ft 3between l the tank outlet connection and the tank overflow O
2.2.3-20 W85tingh0US8 o:VTAACEvev5Nt020203.wpf;1 t>-050198
Certified Design Material PASSIVE CORE COOLING SYSTEM (N Flevision: 5 (wJ' Effective: 5/8/98 _ Table 2.2.3-4 (cont.) ! Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria vii) Inspection of the as-built vii) Plates located above each components will be conducted containment recirculation screen for plates located above the are no more than 10 ft above the containment recirculation top of the screen and extend out at screens. least 10 ft from the trash rack portion of the screen. l viii) Inspections of the IRWST viii) 'Ihe screen surface area and containment recirculation (width x height) of each screen is screens will be conducted. 2 2 70 ft . The bottom of the containment recirculation screens is 2 2 ft above the loop compartment l floor. ix) Inspections will be ix) The type of insulation used on l conducted of the insulation used these lines and equipment is not a inside the containment on ASME fiberous type. Class I lines and on the reactor p) (w/ vessel, reactor coolant pumps, pressurizer and steam generators. x) Inspections will be conducted x) A report exists t.nd concludes of the as-built nonsafety-related that the coatings used on these coatings or of plant records of surfaces has a dry film density of the nonsafety-related coatings 2100 lb/ft3. used inside containment on l walls, floors, ceilings, structural I steel which is part of the ) building structure and on the polar crane. xi) Inspection of the as-built xi) The CMT inlet diffuser has a CMT inlet diffuser will be flow area 2165 in2, conducted. xii) Inspections will be xii) The centerline of each upper conducted of the CMT level level tap line at the tee for each sensors (PSX-II A/B/D/C, - level sensor is located I" 21" 12A/B/C/D,- 13A/B/C/D - below the centerline of the upper 14A/B/C/D) upper level tap level tap connection to the CMT. lines. t
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2.2.3 21 l WOSdfl@lS8 oNTAACSVev5Vt020203.wpf;1 t>050198
Certified Design Material PASSIVE CORE COOLING SYSTEM ~ - Flevision: 5 = Effective: 5/8/98 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 8.d) The PXS provides pH Inspections of the pH adjustment Two pH adjustment baskets exist, l adjustment of water flooding the baskets will be conducted. each with a calculated volume I containment following design 2107 ft3. basis accidents. The pH baskets are located below plant elevation 107 ft,2 in. l 9.a) The PXS provides a i) A flow test and analysis for i) The calculated flow resistance function to cool the outside of the each IRWST drain line to the for each IRWST drain line reactor vessel during a severe containment will be conducted. between the IRWST and the accident. The test is initiated by opening containment is 51.38 x 104 isolation valves in each line. ft/gpm2, Test fixtures may be used to simulate squib valves. ii) Inspections of the as-built ii) The combined total flow area reactor vessel insulation will be of the water inlets is not less than performed. 6 ft2The combined total flow area of the steam outlet (s)is not less than 7.5 ft2, A report exists and concludes that the minimum flow area between the vessel insulation and reactor vessel for the flow path that vents steam is not less than 7.5 ft2 considering the maximum deflection of the vessel insulation with a static pressure of 12.95 ft of water. iii) Inspections will be lii) A flow path with a flow area conducted of the flow path (s) not less than 6 ft2 exists from the from the loop compartments to loop compartment to the reactor the reactor vessel cavity, vessel cavity. 9.b) The accumulator discharge An inspection of the accumulator The accumulator discharge check check valves (PXS-PL-V028A/B and CMT discharge check valves valves are of a different check and V029A/B) are of a different is perfonned. valve type than the CMT discharge check valve type than the CMT check valves. discharge check valves (PXS-Ple V016A/B and V017A/B). O
,,.s 2.2.3-22 L W85tklgt10llSB o:VTAACSVev5Vt020203.wpf:1b-050198
Ccrtified Design M tIri:1 PASSIVE CORE COOLING SYSTEM i EE: Revision: 5 Effective: 5/8/98 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 10. Safety-related displays of the Inspection will be performed for Safety-related displays identified in parameters identified in the retrievability of the safety- Table 2.2.3-1 can be retrieved in Table 2.2.3-1 can be retrieved in related displays in the MCR. the MCR.
the MCR. I1.a) Controls exist in the MCR i) Testing will be performed on i) Controls in the MCR operate to to cause the remotely operated the squib valves identified in cause a signal at the squib valve valves identified in Table 2.2.3-1 Table 2.2.3-1 using controls in electrical leads that is capable of to perform their active the MCR, without stroking the actuating the squib valve. function (s). valve. ii) Stroke testing will be ii) Controls in the MCR operate to performed on remotely operated cause remotely operated valves valves other than squib valves other than squib valves to perform identified in Table 2.2.3-1 using their active functions. the controls in the MCR. II.b) The valves identified in i) Testing will be performed on i) Squib valves receive an Table 2.2.3-1 as having PMS the squib valves identified in electrical signal at the valve control perform their active Table 2.2.3-1 using real or electrical leads that is capable of function after receiving a signal simulated signals into the PMS actuating the valve after a signal is from the PMS. without stroking the valve. input to the PMS. ii) Testing will be performed on ii) Remotely operated valves other the remotely operated valves than squib valves perform the other than squib valves identified active function identified in the in 'Iable 2.2.3-1 using real or table after a signal is input to the simulated signals into the PMS. PMS. iii) Testing will be performed to iii) These valves open within demonstrate that remotely 20 seconds after receipt of an operated PXS isolation valves actuation signal. PXS-V014A/B, V015A/B, V108A/B open within the required response times. I1.c) The valves identified in i) Testing will be performed on i) Squib valves receive an Table 2.2.3-1 as having DAS the squib valves identified in electrical signal at the valve control perform their active Table 2.2.3-1 using real or electrical leads that is capable of function after receiving a signal simulated signals into the DAS actuating the valve after a signal is from the DAS. without stroking the valve. input to the DAS. [ W85tiflgh0US8 2.2.3-23 o:vTAACSVev5Mt020203.wpf:1 b-050198
I Certified Design Material PASSIVE CORE COOLING SYSTEM . =% Revision: 5 -$ Effective: 5/8/98 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria ii) Testing will be performed on ii) Remotely operated valves other the remotely operated valves than squib valves perform the other than squib valves identified active function identified in in Table 2.2.3-1 using real or Table 2.2.3-1 after a signal is input simulated signals into the DAS. to the DAS. 12.a) The motor-operated i) Tests or type tests of i) A test report exists and and check valves identified in motor-operated valves will be concludes that each motor-operated 1 Table 2.2.3-1 perform an active performed that demonstrate the valve changes position as indicated safety-related function to change capability of the valve to operate in Table 2.2.3-1 under design position as indicated in the table, under its design conditions. conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are bounded by the tests or motor-operated valves are type tests. bounded by the tests or type tests. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in perfonned under preoperational Table 2.2.3-1 under preoperational flow, differential pressure, and test conditions. temperature conditions. iv) Exercise testing of the check iv) Each check valve changes. valves with active safety position as indicated in functions identified in Table 2.2.3-1. Table 2.2.3-1 will be performed under preoperational test pressure, temperature and fluid flow conditions. 12,b) After loss of mc,tive power, Testing of the installed valves After loss of motive power, each
]
the remotely operated valves will be performed under the remotely operated valve identified i identified in Table 2.2.3-1 assume conditions of loss of motive in Table 2.2.3-1 assumes the the indicated loss of motive l power. indicated loss of motive power j power position. position.
- 13. Displays of the parameters Inspection will be performed for Displays identified in Table 2.2.3-3 identified in Table 2.2.3-3 can be retrievability of the displays can be retrieved in the MCR.
retrieved in the MCR. identified in Table 2.2.3-3 in the MCR. 1 1 0 , 2.2.3-24 W85tiflgh0tlSe oNTAACSVev5\it020203.wpf:1 b-050198
C:rtified De:Ign M teri:1 PASSIVE CORE COOLING SYSTEM '
-q Revision: 5 O
t Effective: S/8/98 i . ea Table 2.2.3 5 Component Name Tag No. Component Location Passive Residual Heat Removal Heat PXS-ME-01 Containment Building Exchanger (PRHR HX) Accumulator Tank A PXS-MT-01A Containment Building Accumulator Tank B PXS-MT-01B Containment Building Core Makeup Tank (CMT) A PXS-MT-02A Containment Building CMTB PXS-MT-02B Containment Building IRWST PXS-MT-03 Containment Building IRWST Screen A PXS-MY-Y01A Containment Building IRWST Screen B PXS-MY-Y01B Containment Building Containment Recirculation Screen A PXS-MY-YO2A Containment Building Containment Recirculation Screen B PXS-MY-YO2B Containment Building pH Adjustment Basket A PXS-MY-YO3A Containment Building pH Adjustment Basket B PXS-MY Y03B Containment Building O 3 W8Stingt100$8 2.2.3-25 c:VTAACSvev5Mt020203.wpf:1 b-050198
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Certified Design Material STEAM GENERATOR SYSTEM = n Revision: 5 i
) Effective: 5/8/98 1 . ,,
2.2.4 Steam Generator System
)
Design Description
)
{ The steam generator system (SGS) and portions of the main and startup feedwater system (FWS) i transport and control feedwater from the condensate system to the steam generators during normal 3 operation. De SGS and portions of the main steam system (MSS) and turbine system (MTS) { transport and control steam from the steam generators to the turbine generator during normal { operadons. Rese systems also isolate the steam generators from the turbine generator and the I condensate system during design basis accidents. f I I The SGS is as shown in Figure 2.2.4-1, sheets 1 and 2, and portions of the FWS, MSS, and MTS are I as shown in Figure 2.2.4-1, sheet 3, and the locations of the components in these systems is as shown ; in Table 2.2.4-5. i
- 1. The functional arrangement of the SGS and portions of the FWS, MSS, and hfrS are as described in the Design Description of this Section 2.2.4.
l
- 2. a) The components identified in Table 2.2.4-1 as ASME Code Section IU are designed and constructed in accordance with ASME Code Section HI requirements.
1 ('] b) The piping identified in Table 2.2.4-2 as ASME Code Section m is designed and constructed l V in accordance with ASME Code Section UI requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.4-1 as ASME Code Section m meet ASME Code Section m requirements. i b) Pressure boundary welds in piping identified in Table 2.2.4-2 as ASME Code Section UI meet AShm Code Section m requirements.
- 4. a) The components identified in Table 2.2.41 as ASME Code Section m retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.4-2 as ASME Code Section m retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.2.4-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.4-2 for which functional capability is required is designed to withstand combined nonnal and seismic design basis loads without a loss of its functional capability. 2% ; 2.2.4-1 N IT M USO o:\lTAACS\rev5\it020204.wpf:1b-050198
Certified Design Material STEAM GENERATOR SYSTEM C"-~ ~ Revision: 5 Effective: 5/8/98 _
- 6. Each of the as-built lines identified in Table 2.2.4-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protecdon from the dynamic effects of a rupture of the line.
- 7. a) The Class IE equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class IE components identified in Table 2.2.4-1 are powered from their respective Class IE division. c) Separation is provided between SGS Class 1E divisions, and between Class IE divisions and non-Class 1E cable.
- 8. The SGS provides the following safety-related functions:
a) The SGS provides a heat sink for the reactor coolant system (RCS) and provides overpressure protection in accordance with Section III of the ASME Boiler and Pressure Vessel Code. b) During design basis events, the SGS limits steam generator blowdown and feedwater flow to the steam generator. c) The SGS preserves containment integrity by isolation ef the SGS lines penetrating the containment. The inside containment isolation function (isolatir:g the RCS and containment atmosphere from the environinent) is provided by the steam generator, tubes, and SGS lines inside containment while isolation outside containment is provided by manual and automatic valves. l 9. The SGS provides the following nonsafety-related functions: i a) Components within the main steam system, main and startup feedwater system, and the main , turbine system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam l generator blowdown and feedwater flow to Ge steam generator. b) During shutdown operations, the SGS removes decay heat by delivery of startup feedwater to the steam generator and venting of steam from the steam generators to the atmosphere.
- 10. Safety-related displays identified in Table 2.2.4-1 can be retrieved in the main control room (MCR).
I1. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.4-1 to perform active functions. 2.2.4-2 W85tiflghouse o:\rTAACSVev5Vt020204.wpt1b-050198 4
Certified Design Material STEAM GENERATOR SYSTEM .-
~
3 Revision: 5 (j ( Effective: 5/8/98 b) "Ihe valves identified in Table 2.2.4-1 as having PMS control perform an active safety function after receiving a signal from PMS.
- 12. a) The motor-operated valves identified in Table 2.2.4-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the reinotely operated valves identified in Table 2.2.4-1 assume the indicated loss of motive power position. l Inspections, Tests, Analyses, and Acceptance Criteria t Table 2.2.4-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the SGS. ' l % l l
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STEAM GENERATOR SYSTEM l Revision: 5 Effective: sew 98 Table 2.2.4-3 Equipment Name Tag No. Contml Function Turbine Stop Valve MTS-PL-V001 A Close Turbine 6 top Valve MTS-PL-V001B Close Turbine Control Valve MTS-PL-V002A Close Turbine Control Valve MTS-PL-V002B Close Turbine Stop Valve MTS-PL-V003A Close Turbine Stop Valve MTS-PL-V003B Close Turbine Control Valve MTS-PL-V004A Close Turbine Control Valve MTS-PL-V004B Close Turbine Bypass Control Valve MSS-PL-V001 Close Turbine Bypass Control Valve MSS-PL-V002 Closc Turbine Bypass Control Valve MSS-PL-V003 Close Turbine Bypass Control Valve MSS-PL-V004 Close Moisture Separator Reheat Supply Steam Control Valve MSS-PL-V016 Close Main to Startup Feedwater Crossover Valve FWS-PL-097 Close Main Feedwater Pump FWS-MP-02A Trip Main Feedwater Pump FWS-MP-02B Trip Startup Feedwater Pump FWS-MP-03A Trip Startup Feedwater Pump FWS-MP-03B Trip 9 w== uSe . _ . _ _ =
Certified Design Material STEAM GENERATOR SYSTEM I===
/~'T Revision: 5 E h Effective: 5/8/98 k,h e Table 2.2.4-4 Inspections, Tests, Analyses, and / cceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- l. The functional arrangement of Inspection of the as-built system The as-built SGS and portions of ,
the SGS and portions of the will be performed. the FWS, MSS, and MTS conform ' FWS, MSS, and MTS are as with the functional arrangement as described in the Design defined in the Design Description . Description of this Section 2.2.4. of this Section 2.2.4. 2.a) The components identified Inspection will be conducted of The ASME Code Section III in Lble 2.2.4-1 as ASME Code the as-built components as design reports exist for the as-built Section III are designed and documented in the ASME design components identified in constructed in accordance with reports. Table 2.2.4-1 as ASME Code ASME Code Section III Section III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.2.4-2 as ASME Code the as-built piping as documented design reports exist for the as-built Section III is designed and in the ASME design reports. piping identified in Table 2.2.4-2 constructed in accordance with as ASME Code Section III. ASME Code Section III reqmrements. (% j 1 3.a) Pressure boundary wclds in Inspection of the as-built pressure A report exists and concludes that I components identified in boundary welds will be the ASME Code Section III { Table 2.2.4-1 as ASME Code performed in accordance with the requirements are met for non- ' Section III meet ASME Code ASME Code Section III. destructive examination of Section III requirements. pressure boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.2.4-2 boundary welds will be the ASME Code Section III as ASME Code Section III meet performed in accordance with the requirements are met for non. ASME Code Section III ASME Code Section III. destructive examination of requirements. pressure boundary welds. l l O d
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Certified Design Material STEAM GENERATOR SYSTEM % Revision: 5 - M Effective: 5/8/98 Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.a) he components identified A hydrostatic test will be A report exists and concludes that in Table 2.2.4-1 as ASME Code performed on the components the results of the hydrostatic test Section III retain their pressure required by the ASME Code of the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.2.4-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. 4.b) ne piping identified in A hydrostatic test will be A report exists and concludes that Table 2.2.4-2 as ASME Code performed on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code Section III to of the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.2.4-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) De seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.2.4-1 can withstand equipment identified in Table Table 2.2.4-1 is located on the seismic design basis loads 2.2.4-1 is located on the Nuclear Nuclear Island. without loss of safety function. Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage is bounded by the tested or analyzed seismically bounded by the tested conditions. or analyze.d conditions. 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that in Table 2.2.4-2 for which the existence of a report each of the as-built lines functional capability is required concluding that the as-built piping identified in Table 2.2.4-2 for is designed to withstand meets the requirements for which functional capability is combined normal and seismic functional capability. required meets the requirements design basis loads without a loss for functional capability, of its functional capability. O [ WSStingh00S8 0:VTAACSVev5Mt020204.wpt1 019
Certified Design Material STEAM GENERATOR SYSTEM ~L Q Revision: 5 = h Effective: 5/8/98 l Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation report exists identified in Table 2.2.4-2 as the existence of an LBB and concludes that the LBB designed for LBB meets the LBB evaluation repon or an evaluation acceptance criteria are met by the criteria, or an evaluation is report on the protection from as-built RCS piping and piping performed of the protection from effects of a pipe break. Certified materials, or a pipe break the dynamic effects of a rupture Design Material, Section 3.3, evaluation report exists and of the line. Nuclear Island Buildings, contains concludes that protection from the the design descriptions and dynamic effects of a line break is inspections, tests, analyses, and provided.
acceptance criteria for protection from the dynamic effects of pipe rupture. 7.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.2.4-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses wil! be performed on in Table 2.2.41 as being qualified environment can withstand the Class IE equipment located in a for a harsh environment can p environmental conditions that harsh environment. withstand the environmental ('j would exist before, during, and conditions that would exist before, following a design basis accident during, and following a design without loss of safety function basis accident without loss of for the time required to perform safety function for the time the safety function, required to perform the safety function. 7.b) The Class IE components Testing will be performed by A simulated test signal exists at identified in Table 2.2.4-1 are providing a simulated test signal the Class IE equipment identified powered from their respective in each Class IE division. in Table 2.2.4-1 when the Class IE division. assigned Class IE division is provided the test signal. 7.c) Separation is provided See Certified Design Material. See Certified Design Material, between SGS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. l V 1 2.2.4-17 W82 5 0tlS8 oNTAACSVev5Vt020204.wpf;1 tK)S0198 i
Certified Design Material STEAM GENERATOR SYSTEM =J . Revision: 5 i Effective: 5/8/98 Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment laspections, Tests, Analyses Acceptance Criteria 8.a) ne SGS provides a heat i) Inspections will be conducted i) The sum of the rated sink for the RCS and provide.s to confirm that the value of the capacities recorded on the valve overpressure protection in vendor code plate rating of the vendor code plates of the steam accordance with Section III of steam generator safety valves is generator safety valves exceeds .. the ASME Boiler and Pressure greater than or equal to system 4,600,000 lb/hr per steam Vessel Code. relief requirements. generator. ii) Testing and analyses in ii) A report exists to indicate the accordance with ASME Code set pressure of the valves is less Section III will be performed to than 1195 psig. determine set pressure. 8.b) During design basis events, i) Testing will be performed to See item 11 in this table. the SGS limits steam generator confirm isolation of the main blowdown and feedwater flow to feedwater, startup feedwater, the steam generator. blowdown, and main steam lines. See item 11 in this table. ii) Inspection will be performed ii) A report exists to indicate the for the existence of a report installed flow limiting orifice confirming that the area of the within the SG main steam line flow limiting orifice within the SG discharge nozzle does not exceed main steam outlet nozzle will limit 1.4 sq. ft. releases to the containment. 8.c) The SGS preserves See Certified Design Material, See Certified Design Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the SGS lines penetrating the System. System. containment 9.a) Components within the i) Testing will be performed to i) The valves identified in main steam system, main and confirm closure of the valves Table 2.2.4-3 close after a signal startup feedwater system, and the identified in Table 2.2.4-3. is generated by the PMS. main turbine system identified in Table 2.2.4-3 provide backup ii) Testing will L: performed to ii) The pumps identified in isolation of the SGS to limit confirm the trip of the pumps Table 2.2.4-3 trip after a signal is steam generator blowdown and identified in Tablo 2.2.4 3. generated by the PMS. feedwater flow to the steam generator. O 2.2 4-18 1
@E o:VTAACSVev5NtJ20204.wpf:1t 50198
Certified Design Material i STEAM GENERATOR SYSTEM E. ~ p Revision: 5 ~ l ( Effective: 5/8/98 Table 2.2.4 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 9.b) During shutdown i) Tests will be performed to i) See Certified Design Material, operations, the SGS removes demonstrate the ability of the subsection 2.4.1, Main and decay heat by delivery of startup startup feedwater system to Startup Feedwater System. feedwater to the steam generator provide feedwater to the steam and venting of steam from the generators. steam generators to the atmosphere. ii) Tests and/or analyses will be ii) A report exists and concludes perfonned to demonstrate the that each power-operated relief ability of the power-operated relief valve will relieve greater than valves to discharge steam from the 200,000 lb/hr at 1003 psia steam generators to the 10 psi. atmosphere.
- 10. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.4-1 can be retrievability of the safety-related in Table 2.2.4-1 can be retrieved retrieved in the McR. displays in the MCR. in the MCR.
11.a) Convols exist in the MCR Stroke testing will be performed Controls in the MCR operate to 4 ) to cause the remotely operated on the remotely operated valves cause the remotely operated
\_/ valves identified in Table 2.2.41 listed in Table 2.2.4-1 using valves to perform active safety to perform active functions. controls in the MCR. functions.
I1.b) De valves identified in i) Testing will be performed on i) The remotely-operated valves Table 2.2.4-1 as having PMS the remotely operated valves listed identified in Table 2.2.4-1 as control perform an active safety in Table 2.2.4-1 using real or having PMS control perform function efter receiving a signal simulated signals into the PMS. the active function identified in from PMS. the table after receiving a signal from the PMS. ii) Testing will be performed to li) Rese valves close within the demonstrate that remotely following times after receipt of an operated SGS isolation valves actuation signal: SGS-V027A/B, V040A/B, V057/JB, V250A/B close within V027A/B < 44 see the required response times. VO40A/B, V057A/B < 5 see V250A/B < 5 sec r'N 2.2.4-19 W8Stkigh0tlS8 o:VTAACSVev5Mt020204.wpf:1 b-050198
l Certified Design Material l l STEAM GENERATOR SYSTEM -- m Revision: 5 Effective: 5/8/98 Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 12.a) The motor-operated valves i) Tests or type tests of anotor- i) A test report exists and identified in Table 2.2.4-1 operated valves will be performed concludes that each motor-perform an active safety-related to demonstrate the capability of operated valve changes position as function to change position as the valve to operate under its indicated in Table 2.2.4-1 under indicated in the table. design conditions design conditions. ii) Inspection will be perfonned ii) A report exists and concludes for the existence of a report that the as-installed motor-verifying that the as-installed operated valves are bounded by ) motor-operated valves are bounded the tests or type tests. l by the tests or type tests. iii) Tests of the as-installed motor- iii) Each motor-operated valve operated valves will be performed changes position as indicated in under pre-operational flow, Table 2.2.4-1 under pre- I l differential pressure, and operational test conditions. temperature conditions. i 1 12.b) After loss of motive Testing of the installed valves will After loss of notive power, each power, the remotely operated be performed under the conditions rcmotely operated valve identified valves identified in Table 2.2.4-1 ofloss of motive power. in Table 2.2.4-1 assumes the assume the indicated loss of indicated loss of motive power l motive power position. position. ! i 1 0 2.2.4-20 UUM oNTAACSvev5Vt020204.wpf;1 b-050198
Certified Design Material l STEAM GENERATOR SYSTEM .=i. m ! f Revision: 5 --- (J u
) Effective: 5/8/98 .k.1 e Table 2.2.4-S Component Name Tag No. Component Location Main Steam Line Isolation Valve SGS-PL-V040A Auxiliary Building Main Steam Line Isolation Valve SGS-PL-V040B Auxiliary Building Main Feedwater Isolation Valve SGS-PL-V057A Auxiliary Building Main Feedwater Isolation Valve SGS-PL-V357B Auxiliary Building Main Feedwater Control Valve SGS-PL-V250A Auxiliary Building ;
Main Feedwater Control Valve SGS-PL-V250B Auxiliary Building Turbine Stop Valves MTS-PL-V001 A Turbine Building MTS-PL-V001B MTS-PL-V003A P ITS-PL-V003B Turbine Control Valves MTS-PL-V002A Turbine Building MTS-PL-V002B MTS-PL-V0(MA 1 p MTS-PL-V004B I N Main Feedwater Pumps FWS-MP-01A Tu. ine Building FWS-MP-OlB Feedwater Booster Pumps FWS-MP-02A Turbine Building FWS-MP-02B l l l o CJ J 2.2.4-21 i [ Westinghouse o:\lTAACSirev5Nt020204.wpf;1b-050198
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Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM Revision: 5
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l ]) Effective: 5/8/98 2.2.5 Main Control Room Emergency Habitability System { Design Description The main control room emergency habitability system (VES) provides a supply of breathable air for ( the main control room (MCR) occupants and maintains the MCR at a positive pressure with respect to - the surrounding areas whenever ac power is not available to operate the nuclear island nonradioactive ventilation system (VBS) or high radioactivity is detected in the MCR air supply. (See CDM Section 3.5 for Radiation Monitoring). The VES also limits the heatup of the MCR, the irtstrumentation and control (I&C) equipment rooms, and the Class 1E de equipment rooms by using the heat capacity of surrounding structures. He VES is as shown in Figure 2.2.5-1 and the component locations of the VES are as shown in Table 2.2.5-6.
- 1. The functionan arrangement of the VES is as described in the Design Description of this Section 2.2.5.
- 2. a) The components identified in Table 2.2.5-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
O V b) He piping identified in Table 2.2.5-2 as ASME Code Section m is designed and constructed in accordance with ASME Code Section m requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.5-1 as ASME Code Section III meet ASME Code Section m requirements.
b) Pressure boundary welds in piping identified in Tab!e 2.2.5-2 as ASME Code Section III meet ASME Code Section m requirements.
- 4. a) He components identified in Table 2.2.5-1 as ASME Code Section m retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.5-2 as AShE Code Section m retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.2.5-1 can withstand seismic design i basis loads without loss of safety function. l b) Each of the lines identified in Table 2.2.5-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
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Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM ~ ~ = ~ Revision: 5 ~ 5 Effective: 5/8/98 1 .et
- 6. a) The Class 1E components identified in Table 2.2.5-1 ne powered from their respective Class IE division.
b) Separation is provided between VES Class IE divisions, and between Class 1E divisions and non-Class IE cable.
- 7. The VES provides the following safety-related functions:
a) ne VES provides a 72-hour supply of breathable quality air for the occupants of the MCR. b) The VES maintains the MCR pressure boundary at a positive pressure with rerpect to the surrounding areas. c) He heat loads within the MCR, the I&C equipment rooms, and the Class 1E de equipment rooms are within design basis assumptions to limit the heatup of the rooms identified in Table 2.2.5-4.
- 8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.
- 9. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.5-1 ,
to perform their active functions. b) The valves identified in Table 2.2.5-1 as having protection and safety tuonitoring system O (PMS) centrol perform their active safety function after receiving a signal from the PMS.
- 10. After loss of motive power, the remotely operated valves identified in Table 2.2.5-1 assume the indicated loss of motive power position.
- 11. Displays of the parameters identified in Table 2.2.5-3 can be retrieved in the MCR.
hispections, Tests, Analyses, and Acceptance Criteria Table 2.2.5-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the VES. I O 2.2.5-2 W_ Westinghouse o:bp600VTAACSVev5Mt020205.wpf:050198
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Effective: 5/8/98 1 . e e. Table 2.2.5-2 ASME Code Functional Capability Line Name Line Number Section III Required MCR Relief Line VES-PL-022A Yes Yes MCR Relief Line VES-PI 022B Yes Yes Table 2.2.5-3 Equipment Tag No. Display Air Storage Tank Pressure VES-Cola Yes Air Storage Tank Pressure VES-001B Yes Table 2.2.5-4 Heat Load 0 to 24 Hours Heat Load 24 to 72 Room Name Room Numbers (Btu /s) Hours (Btu /s) MCR Envelope 12401 12.8 (hour 0 through 3) 3.9 5.1 (hour 4 through 24) I&C Rooms 12301,12305 8.8 0 I&C Rooms 12302,12304 13.0 4.2 de Equipment Rooms 12201,12205 3.7 (hour 0 through 1) 0 2.4 (hour 2 through 24) de Equipment Rooms 12203,12207 5.8 (hour 0 through 1) 2.0 4.5 (hour 2 through 24) O 2.2.5-8 WB5tingh0US6 o \ap600VTAACSVev5 Tit 020205.wpf:050198
7 Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM .'=H I q Revision: 5 - 1_
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s Table 2.2.5 5 Inspections, Tests, Analyses, and Accer ance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria I. The functional arrangement of Inspection of the as-built system The as-built VES conforms with the VES is as described in the will be performed. the functional arrangement Design Description of this described in the Design Section 2.2.5. Description of this Section 2.2.5. 2.a) The components identified in Inspction will be conducted of 'Ihe ASME Code Section III Table 2.2.5-I as ASME Code the as-built components as lesign reports exist for the as-Section III are designed and documented in the ASME design built components identified in constructed in accordance with reports. Table 2.2.5-I as ASME Code ASME Code Section III Section III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.2.5-2 as ASME Code the as-built piping as documented design reports exist for tnc as-Section III is designed and in the ASME design reports. built piping identified in constructed in accordance with Table 2.2.5-2 as ASME Code ASME Code Section III Section III. requirements. (7 3.a) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that () components identified in boundary welds will be performed the ASME Code Section III Table 2.2.5-I as ASME Code in accordance with the ASME requirements are met for non-Section III meet ASME Code Code Section III. destructive exaraination of Section III requirements. pressure boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes thr.t piping identified in Table 2.2.5-2 boundary welds will be performed the ASME Code S ction III as ASME Code Section III meet in accordance with the ASME ree.sirements are met for non-ASME Code Section III Code Section III. destructive examination of i requirements. pressure boundary welds. ! l 4.a) The components identified in A hydrostatic test will be A report exists and concludes that Table 2.2.5-I as ASME Code performed on the components the results of the hydrostatic test l Section III retain their pressure required by the ASME Code of the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.2.5-I as ASME Code pressure. tested. Section III conform with the requiremen'.s of the ASME Code Section III. 4.b) The piping identified in A hydrostatic test wi'1 be
. A report exists ar.d concludes that Table 2.2.5-2 as ASME Code performed on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code S-ction III to of the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.2.5-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III.
2.2.5-9 Y W85tilighouse onap600VTAACSVev5\it020205.wpf:050198
i Certified Design Material l MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM = 2 Revision: 5 Effective: 5/8/98 Table 2.2.5-5 (cond.) Inspections, Tests, Analyses, and Acceptance Criteria j Design Commitment Inspections, Tests, Analyses Acceptance Criteria 5.a) Tne seismic Category I i) Inspection will be performed i) The seismic Category I equipment identified in to verify that the sei::mic equipment identified in Table 2.2.5-1 can withstand Category I equipment and valves Table 2.2.51 is located on the seismic design basis loads identified in Table 2.2.5-1 are Nuclear Island. without loss of safety function. located on the Nuclear Island. ii) Type tests, analyses, or a ii) A repon exists ar;d concludes combination of type t:sts and that the seismic Category I analyses of seismic Category I eqt.ipment can withstand seismic equipment will be perf9rmed. design basis loads without loss of safety function. iii) Inspetion will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifymg that the as-installed including ar.chorage is seismically equipment including anchorage bounded by the tested or analyzed is seismically bounded by the conditions. tested or analyzed condinons. 5.b) Each of the lines identified Inspection will be performed for A report exis and concludes that in Table 2.2.5-2 for which the existence of a report each of the as-built lines identified functional capability is required is verifying that the as-built piping in Table 2.2.5--2 for which designed to withstand combined meets the requirements for f;metional capability is required normal and seismic design basis functional capability, meets the requirements for loads without a loss of its functional capability. functional capability. 6.a) The Class IE components Testing will be performed by A simulated test signal exists at ider tified in Table 2.2.5-1 are providing a simulated test sigr.at the Class IE equipment identified powered from their respective in each Class IE division. in Table 2.2.5-1 when the assigned Class IE division. Class IE division is provided the test signal. 6.b) Separation is provided See Certified Design Material, See Ccrtified Design Mxeriai, between VES Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. O 2.2.5-10 DDM8 o:\ao600\lTAACSVev5Vt020205.wpf:050198
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM (S Revision: 5 (v) Effet.tive: 5/8/98 Table 2.2.5-5 (cont ) Inspections, Tests, Ar.alyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.a) The VES provides a 72-hour i) Testing will be performed to i) The air flow rate from the VES supply of breathable quality air confirm that the required amount is at least 60 scfm and not more for the occupants of the MCR. of air flow is delivered to the than 70 scfm. MCR. ii) The calculated storage capacity ii) Analysis of storage capacity is greater than or equal to will be performed based on as- 314,132 scf. built manufacturers data. I iii) MCR air samples will be iii) The MCR air is of breathable I taken dusing VES testing and quality. analyzed for quality. 7.b) The VES maintains the i) Testing will be performed The MCR pressure boundary is MCR pressure boundary at a with VES flowrate between 60 pressurized to greater than or equal positive pressure with respect to and 70 scfm to confinn that the to 1/8-in. water gauge with respect the surrounding areas. MCR is capable of maintaining to the surrounding area. the required pressurization of the pressure boundary. (']) L ii) Air leakage into the MCR ii) Analysis of air leakage will be measured during VES measurements indicate that VES testing using a tracer gas. operation limits MCR air infiltration consistent with operator dose analysis. l i i [ V 22.5 n
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Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM = ' l Revision: 5 Effective: 5/8/98 _ Table 2.2.5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria j Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.c) The heat loads within the An analysis will be performed to A report exists and concludes that: MCR, the I&C equipment rooms, determine that the heat loads the heat loads within rooms and the Class IE de equipment from as-built equipment within identified in Table 2.2.5-4 are less rooms are within design basis the rooms identified in than or equal to the specified assumptions to limit the heatup of Table 2.2.5-4 are less than or values or that an analysis report the rooms identified in equal to the design 'basis exists that concludes: l Table 2.2.5-4. assumptions l
- The temperature and humidity l in the MCR remain within limits for reliable human performance for the 72-hour period.
- He maximum temperature for the 72-hour period for the I&C rooms is less than or equal to 125'F.
- He maximum temperature for the 72-hour period for the Class IE de equipment rooms I is less than or equal to 120*F.
- 8. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.2.5-1 can be retrievability of the safety-related Table 2.2.5-1 can be retrieved in retrieved in the MCR. displays in the MCR. the MCR.
9.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause remotely operated valves on remotely operated valves cause remotely operated valves identified in Table 2.2.5-1 to identified in Table 2.2.5-1 using identified in Table 2.2.51 to perform their active functions. the controls in the MCR. perform their active safety functions. 9.b) He valves identified in Testing will be performed on ne remotely operated valves Table 2.2.5-1 as having PMS reinotely operated valves listed identified in Table 2.2.5-1 as control perform their active safety in Table 2.2.5-1 using real or having PMS control perform the function after receiving a signal simulated signals into the PMS. active safety function identified in from the PMS. the table after receiving a signal from the PMS.
- 10. After loss of motive power, Testing of the installed valves After loss of motive power, each the remotely operated valves will be performed under the remotely operated valve identified identified in Table 2.2.5-1 assume conditions ofloss of motive in Table 2.2.5-1 assumes the the indicated loss of motive power. indicated loss of motive power power position. position.
2.2.5-12 W85tilighouse* o:\ap600\lTAACSVev5Vt020205.wpf:050198
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM f = t.. p Revision: 5 T EE Q Effective: 5/8/98 1 -
. e Table 2.2.5-5 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l
- 11. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.2.5-3 can be retrievability of the parameters Table 2.2.5-3 can be retrieved in l l retrieved in the MCR. in the MCR. the MCR.
l 1 i ( v h d 2.2.5-13 T Westinghouse ospe0avrAACSVedt020205.wpf:050198
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM Revision: 5 = Effective: 5/8/98 _ Table 2.2.5-6 Component Name Tag Number Component Location Emergency Air Storage Tank 01 VES-MT-01 Auxiliary Building Emergency Air Storage Tank 02 VES-MT-02 Auxiliary Building Emergency Air Storage Tank 03 VES-MT-03 Auxiliary Building Emergency Air Storage Tank 04 VES-MT-04 Auxiliary Building Emergency Air Storage Tank 05 VES-MT-05 Auxiliary Building Emergency Air Storage Tank 06 VES-MT-06 Auxiliary Building Emergency Air Storage Tank 07 VES-MT-07 Auxiliary Building Emergency Air Storage Tank 08 VES-MT-08 Auxiliary Building Emergency Air Storage Tank 09 VES-MT-09 Auxiliary Building Emergency Air Storage Tank 10 VES-MT-10 Auxiliary Building Emergency Air Storage Tank 11 VES-MT-11 Auxiliary Building Emergency Air Storage Tank 12 VES-MT-12 Auxiliary Building Emergency Air Storage Tank 13 VES-MT-13 Auxiliary Building Emergency Air Storage Tank 14 VES-MT-14 Auxiliary Building Emergency Air Storage Tank 15 VES-MT-15 Auxiliary Building Emergency Air Storage Tank 16 VES-MT-16 Auxiliary Building
]
Emergency Air Storage Tank 17 VES-MT-17 Auxiliary Building ) Emergency Air Storage Tank 18 VES-MT-18 Auxiliary Building Emergency Air Storage Tank 19 VES-MT-19 Auxiliary Building l Emergency Air Storage Tank 20 VES-MT-20 Auxiliary Building Emergency Air Storage Tank 21 VES-MT-21 Auxiliary Building Emergency Air Storage Tank 22 VES-MT-22 Auxiliary Building Emergency Air Storage Tank 23 VES-MT-23 Auxiliary Building Emergency Air Storage Tank 24 VES-MT-24 Auxiliary Building Emergency Air Storage Tank 25 VES-MT-25 Auxiliary Building Emergency Air Storage Tank 26 VES-MT-26 Auxiliary Building Emergency Air Storage Tank 27 VES-MT 27 Auxiliary Building l Emergency Air Storage Tank 28 VES-MT-28 Auxiliary Building [ W8StiflCOUS0 o:\ap60(NTAACSirev5\it020205. 05 198 \
Ccrtified Design Mit:ri:1 MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM - Revision: 5 Effective: 5/8/98 Table 2.2.5-6 (cont.) Component Name Tag Number Component Location Emergency Air Storage Tank 29 VES-MT-29 Auxilian Building Emergency Air Storage Tank 30 '.TES-MT-30 Auxiliary Building Emergency Air Storage Tank 31 VES-MT-31 Auxiliary Building Emergency Att Storage Tank 32 VES-MT-32 Auxiliary Building O O r =at- o__.__ =
Ccrtified Design Miterizi MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM ": Revision: 5 T Effective: 5/8/98 - GB i i 7,,a== g m*-v=. M l ... c?? [".~[.,,.....(
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Certified Design Mat: rill COMPONENT COOLING W.A TER SYSTEM C- "~ Revision: 5 O Effective: 5/8/98 .
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2.3.1 Component Cooling Water System Design Description The component cooling water system (CCS) removes heat from various plant components and transfars this heat to the service ivater system (SWS) during normal modes of plant operation including power generation, shutdown and refueling. The CCS has two pumps and two heat exchangers. The CCS is as shown in Figure 2.3.1-1 and the CCS component locations are as shown in Table 2.3.1-3.
- 1. The functional arrangement of the CCS is as described in the Design Description of this Section 2.3.1.
- 2. The CCS preserves containment integrity by isolation of the CCS lines penetrating the containment.
- 3. The CCS provides the nonsafety-related functions of transferring heat from the normal residual heat removal system (RNS) during shutdown and the spent fuel pool cooling system during all modes of operation to the SWS.
4. Controls exist in the main control room (MCR) to cause the pumps identified in Table 2.3.1-1 to perform the listed functions.
- 5. Displays of the parameters identified in Table 2.3.1-1 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.1-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the CCS. UUMB oNTAACSVev5Vt020301.wpf:1 tNE0398 2.3.1-1
Certified Design Material COMPONENT COOLING WATER SYSTEM i Revision: 5 Effective: 5/8/98 _ Table 2.3.1 1 Equipmeat Name Tag No. Display Control Function CCS Pump A CCS-MP-01A Yes Start (Run Status) CCS Pump B CCS-MP-OlB Yes Start (Run Status) CCS Discharge Header Flow Sensor CCS-101 Yes - CCS to Normal Residual Heat Removal CCS-301 Yes - System Heat Exchanger (RNS HX) A Flow Sensor CCS to RNS HX B Flow Sensor CCS-302 Yes - CCS to Spent Fuel Pool Cooling CCS-341 Yes - System (SFS) HX A Flow Sensor CCS to SFS HX B Flow Sensor CCS-342 Yes - CCS Surge Tank Level Sensor CCS-130 Yes - CCS Heat Exchanger Inlet Temperature CCS-121 Yes - Sensor CCS Heat Exchanger Outlet CCS-122 Yes - Temperature Sensor CCS Flow to Reactor Coolant Pump CCS-PL-V256A Yes - (RCP) 1 A Valve (Position Indicator) CCS Flow to RCP IB Valve (Position CCS-PL-V256B Yes - Indicator) CCS Flow to RCP 2A Valve (Position CCS-PL-V256C Yes - Indicator) CCS Flow to RCP 2B Valve (Position CCS-PL-V256D Yes - Indicator) Note: Dash (-) indicates not appbcable. O 2.3.1-2 [ WBStingil0USB o:VTAACSVev5Vt020301.wpf:1 b-05vd98
l Certified Design Material COMPONENT COOLING WATER SYSTEM - ==
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1 1 Table 2.3.12 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built CCS conforms with the CCS is as described in the will be performed. the functional arrangement Design Description of this described in the' Design Section 2.3.1. Description of this Section 2.3.1,
- 2. The CCS preserves containment See Certified Design Material, See Certified Design Material, integrity by isolation of the CCS subsection 2.2.1, Containment subsection 2.2.1, Containment lines penetrating the containment. System. System.
- 3. The CCS provides the i) Inspection will be performed for i) A report exists and concludes nonsafety-related functions of the existence of a report that that the UA of each CCS heat transferring heat from the RNS determines the heat transfer exchanger is greater than or equal during shutdown and the spent fuel capability of the CCS heat to 9.4 million Btu /hr 'F.
pool cooling system during all exchangers. l modes of operation to the SWS. ii) Testing will be performed to ii) Each pump of the CCS car. confirm that the CCS can provide provide at least 2520 gpm of cooling water to the RNS HXs cooling water to one RNS IlX while providing cooling water to and at least 720 gpm of cooling A the SFS HXs. water to one SFS HX while {) providing at least 1160 gpm to other users of cooling water, fj
- 4. Controls exist in the MCR to Testing will be performed to Controls in the MCR operate to f cause the pumps identified in actuate the pumps identified in cause pumps listed in j Table 2.3.1-1 to perform the listed Table 2.3.1-1 using controls in the Table 2.3.1-1 to perform the listed functions. MCR. functions.
- 5. Displays of the parameters Inspection will be performed for Displays identified in Table 2.3.1-1 identified in Table 2.3.1-1 can be retrievability of the parameters in can be retrieved in the MCR.
retrieved in the MCR. the MCR. I l l l l l l l l O 2.3.1-3 . W850figh0llSe oNTAACSVev5Vt020301.wpt:1tM0398 o
Certified Design Material l COMPONENT COOLING WATER SYSTEM _
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Revision: 5 = Effective: 5/8/98 " Tame 2.3.13 Component Name Tag No. Component Location CCS Pump A CCS-MP-01A Turbine Euilding CCS Pump B CCS-MP-OlB Turbine Building CCS Heat Exchanger A CCS-ME-Ol A Turbine Building CCS Heat Exchanger B CCS-ME-01B Turbine Building 9 O T Westinghouse omAAcsmsuto203oi.wpu s
Certified Design Material COMPONENT COOLING WATER SYSTEM - Revision: 5 (m) Effective: 5/8/98 SWS r-------- 9 44 lC LETOOWN Hxl (O H TL T MEM C ADS
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_\ ty.S RCOT HX------- j CCS HEAT EXCMANOER A CCS-uE-O'^ CCS PuuP A CCS-MP-01 A p SWS 44
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l Cv$ MINTLOWS MXS RNS PUMPS SEALS l i PSS SAMPLE COOLER t i VWS CHILLERS 1 I li CAS C0S PUMPA2R COMPRESSORS MOTOR 'l 6 ca ch th OIL COOLERS i aNS + ii - Sr$ SrS - ii - RNS hX A M l l ' NX B HX AM l l h MX B CD C3 C3 CD o o e p 1 lFROM CONTAINMEN A 1 ME AT LOA 05 / l Figure 23.1-1
-m Component Cooling Water System x
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i l Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM r"~"- P i (s Revision: 5 - V Effective: 5/8/98 2.3.2 Chemical and Volume Control System 1 l Design Description j i The chemical and volume control system (CVS) provides reactor coolant system (RCS) purification, RCS inventory control and makeup, chemical shim and chemical control, and oxygen control, and provides for auxiliary pressurizer spray. The CVS performs these functions during normal modes of operation including power generation and shutdown. { The CVS is as shown in Figure 2.3.2-1 and the component locations of the CVS are as shown in Table 2.3.2-5. , l
- 1. The functional arrangement of the CVS is as described in the Design Description of this Section 2.3.2.
l
- 2. a) The components identified in Table 2.3.21 as ASME Code Section III are designed and )
constructed in accordance with ASME Code Section III requirem':nts. j l b) ne piping identified in Table 2.3.2-2 as ASME Code Section III is designed and constructed l in accordance with ASME Code Section III requirements. I
\ 3. a) Pressure boundary welds in components identified in Table 2.3.2-1 as ASME Code Section III (d meet ASME Code Section III requirements.
i b) Pressure boundary welds in piping identified in Table 2.3.2-2 as ASME Ccde Section III meet ASME Code Swtion III requirements. i
- 4. a) The components identified in Table 2.3.2-1 as ASME Code Section III retain their pressure )
boundary integrity at their design pressure. i b) The piping identified in Table 2.3.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. The seismic Category I equipment identified in Table 2.3.2-1 can withstand seismic design basis loads without loss of safety function.
- 6. a) The Class IE equipment identified in Table 2.3.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a l design basis accident without loss of safety function for the time required to perform the safety I function, b) The Class IE components identified in Table 2.3.2-1 are powered fram their respective Class IE division.
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Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM r
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Revision: 5 { Effective: 5/8/98 c) Separation is provided between CVS Class lE divisions, and between Class IE divisions and non-Class IE cable.
- 7. He CVS provides the following safety-related functions:
a) The CVS preserves containment integrity by isolation of the CVS lines penetrating the containment. b) The CVS provides termination of an inadvertent RCS boron dilution by isolating deminvalized water from the RCS. c) ne CVS provides isolation of makeup to the RCS.
- 8. He CVS provides the following nonsafety-related functions:
a) The CVS provides makeup water to the RCS. I b) The CVS provides the pressurizer auxiliary spray.
- 9. Safety-related displays in Table 2.3.2-1 can be retrieved in the main control room (MCR).
- 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.3.2-1 to perform active functions.
b) The valves identified in Table 2.3.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS.
- 11. a) The motor-operated and check valves identified in Table 2.3.2-1 perform an active safety-related furnetion to change position as indicated in the table.
b) After a loss of motive power, the remotely operated valves identified in Table 2.3.2-1 assume the indicated loss of motive power position.
- 12. a) Controls exist in the MCR to cause the pumps identified in Table 2.3.2-3 to perform the listed function.
b) The pumps identified in Table 2.3.2-3 start after receiving a signal from the PLS.
- 13. Displays of the parameters identified in Table 2.3.2-3 can be retrieved in the MCR.
I 14. The nonsafety-related piping located inside containment and designated as reactor coolant pressure boundary, as identified in Table 2.3.2-2 (pipe lines with "No" in the ASME Code column), has been designed to withstand a seismic design basis event and maintain structural integrity. O 2.3.2-2 MEMS o:VTAACSVev5Vto20302.wpf;1 t@S0698
1 i Certified Design M:terial CHEMICAL AND VOLUME CONTROL SYSTEM g -b Revision: 5 (G) j _ Effective: S/8/98 i i Inspections, Tests, Analyses, and Acceptance Criteria { Table 2.3.2-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the CVS. l 1 LJ 1 0 l 2.3.2-3 3 W85tingil0US8 o:VTAACSvev5Nt020302.wptit> 050198 1 I 1 ;
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Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM - -" Revision: 5
- Q Effective: 5/8/98 _
Table 2.3.2 2 Line Name Line Number ASME Code Section III CVS Purification Line BTA L001 Yes CVS Purification Line Return BTA LO38 Yes CVS Makeup Containment Penetration Line BBB LO53 Yes
" CVS Supply Line to Regenerative Heat BBD LOO 2 No Exchanger CVS Return Line from Regenerative Heat BBD L018 No r Exchanger BBD LO73 No CVS Line from Regenerative Heat Exchanger to BBD LOO 3 No Letdown Heat Exchanger BBD LO72 No CVS Lines from Letdown Heat Exchanger to BBD LOO 4 No Demin. Tanns BBD LOO 5 No CVS Lines from Demin Tanks to RC Filters BBD LO20 No BBD LO21 No p BBD LO22 No BBD LO29 No BBD LO37 No CVS Lines from RC Filters to Regenerative BBD LO30 No Heat Exchanger BBD LO31 No BBD LO34 No CVS Resin Fill Lines to Demin. Tanks BBD LOO 8 No BBD L013 No BBD LO25 No l
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Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM Revision: 5 :5 Effective: 5/8/98 _
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Table 2.3.2-3 Control .i Equipment Tag No. Display Function CVS Makeup Pump A CVS-MP-OlA Yes Start (Run Status) l CVS Makeup Pump B CVS-MP-01B Yes Start (Run Status) j 1 Letdown Flow Sensor CVS-001 Yes - J l Letdown Flow Sensor CVS-025 Yes - i t CVS Purification Return Line (Position CVS-PL-V081 Yes - Indicator) j Auxiliary Spray Line Isolation Valve CVS-PL-V084 Yes - (Position Indicator) Boric Acid Tank Level Sensor CVS-109 Yes - l Boric Acid Flow Sensor CVS-IIS Yes - Makeup Blend Valve (Position Indicator) CVS-PL-Vil5 Yes - CVS Demineralized Water Isolation Valve CVS-PL-136A Yes - (Position Indicator) CVS Demineralized Water Isolation Valve CVS-PL-136B Yes - i (Position Indicator) Makeup Purap Discharge Flow Sensor CVS-157 Yes - Makeup Flow Control Va've (Position CVS-PL-V157 Yes - Indicator) Note: Dash (-) indicates not applicable. O 2.3.2-8 We@ S8 0:\lTA %CS\rev5\it020302.wpf:1 b-050198
Certified Design Material /G CHEMICAL AND VOLUME CONTROL SYSTEM Revision: 5 y*;j} h Effective: 5/8/98 i*.*C Table 2.3.2-4 Inspections, Tests, Analyses and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. He functional arrangement of Inspection of the as-built system The as-built CVS conforms with the CVE .s as described in the will be perfonned. the functional arrangement as Desigr Description of this described in the Design Sectior, 2.3.2. Description of this Section 2.3.2.
2.a} The components identified Inspection will be conducted of De ASME Code Section III in Table 2.3.2-1 as ASME Code the as-built components as design reports exist for the as-built Su. tion III are designed and documented in the ASME design components identified in canstmeted in accordance with reportr. Table 2.3.2-1 as ASME Code ASME Code Section III Section III. requirements. 2.b) he piping identified in Inspection will be conducted of The ASME Code Section III Table 2.3.2-2 as ASME Code the as-built piping as design repons exist for the as-built Section III is designed and documented in the ASME design piping identified in Table 2.3.2-2 constructed in accordance with reports. as ASME Code Section III. ASME Code Section III requirements. C' 3.a) Pressure boundary welds in Inspection of the as-built A repon exists and concludes that components identified in pressure boundary welds will be the ASME Code Section III Table 2.3.21 as ASME Code performed in accordance with requirements are met for non-Section III meet ASME Code the ASME Code Section III. destructive examination of pressure Section III requirements. boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built A repon exists and concludes that piping identified in Table 2.3.2-2 pressure boundary welds will be the ASME Code Section III as ASME Code Section III meet performed in accordance with requirements are met for non-ASME Code Section III the ASME Code Section III. destructive examination of pressure requirements. boundary welds. 4.a) The compenents identWi-d A hydrostatic test will be A report exists and concludes that in Table 2.3.2-1 as ASME Code performed on the components the results of the hydrostatic test of Section III retain their pressure required by the ASME Code the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.3.2-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. / \ 2.3.2-9 W8Stingh00S8 oNTAACSirev5\lt020302.wpti b-050198 l 2
Certified De:Ign Miterill
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CHEMICAL AND VOLUME CONTROL SYSTEM i i Revision: 5 Effective: 5/8/98 _ Table 2.3.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.3.2-2 as ASME Code performed on the piping required the results of the hydrostatic test of Section III retains its pressure by the ASME Code Section III the piping identified in boundary integrity at its design to be hydrostatically tested. Table 2.3.2-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III.
- 5. The seismic Category I i) Inspection will be performed i) The seismic Category I equipment identified in to verify that the seismic equipment identified in Table 2.3.2-1 can withstand Category I equipment identified Table 2.3.2-1 is located on the seismic design basis loads in Table 2.3.2-1 is located on the Nuclear Islar.d.
without loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis dynamic loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage bounded by the tested or analyzed is seismically bounded by the conditions. tested or analyzed conditions. 6.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.3.2-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.3.2-1 as being qualified environment can withstand the Class IE equipment located in a for a harsh environment can environmental conditions that harsh environment. withstand the environmental would exist before, during, and conditions that would exist before, following a design basis accident during, and following a design without loss of safety function for basis accident without loss of the time required to perform the safety function for the time safety function. required to perform the safety function. 6.b) 'Ihe Class IE components Testing will be performed on the A simulated test signal exists at identified in Table 2.3.2-1 are CVS by providing a simulated the Class IE equipment identified powered from their respective test signal in each Class IE in Table 2.3.2-1 when the assigned Class IE division. division. Class IE division is provided the test signal. 2.3.2-10 Wed@tlS8 oNTAACSirev5\it020302.wpf:1b-050198
Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM EE EE
/ ~~N Revision: 5 ~
~
() Effective: 5/8/98 _ Table 2.3.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 6.c) Separation is provided See Certified Design Material, See Certified Design Material, between CVS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. 7.a) He CVS preserves See Certified Design Material, See Certified Design Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the CVS lines penetrating the System. System. containment. 7.b) The CVS provides See item 10b in this table. See item 10b in this table. termination of an inadvertent RCS boron dilution by isolating demineralized water from the j RCS. 7.c) He CVS provides isolation See item 10b je. this table. See item 10b in this table, of makeup to the RCS. ( 8.a) The CVS provides makeup i) Testing will be performed by i) Each CVS makeup pump water to the RCS. aligning a flow path from each provides a flow rate of greater than ! CVS makeup pump, actuating or equal to 100 gpm. I makeup flow to the RCS at I pressure greater than or equal to 2000 psia, and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid tank. ii) Inspection of the boric acid ii) The volume in the boric acid tank volume will be performed. tank is at least 55,000 gallons between the tank outlet connection and the tank overflow. I iii) Testing will be performed to iii) The total CVS makeup flow to i measure the delivery rate from the RCS is less than or equal to I the DWS to the RCS. Both 200 gpm. 1 CVS makeup pumps will be I operating and the RCS pressure I will be below 6 psig. A i 2.3.2-11 WB@0llSe o:VTAACSVev5Vt020302.wpf:1 b-050198 (
Certified Design Material CHEMICAL AND VOLilME CONTROL SYSTEM E Revision: 5 Effective: 5/8/98 Table 2.3.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 8.b) 'Ihe CVS provides the Testing will be performed by Each CVS makeup pump provides pressurizer auxiliary spray. aligning a flow path from each spray flow to the pressurizer. CVS makeup pump to the pressurizer auxiliary spray and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid tank and with RCS pressure greater than or equal to 2000 psia.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.3.2-1 can be retrievability of the safety-related Table 2.3.2-1 can be retrieved in retrieved in the MCR. displays in the MCR. the MCR.
10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause the remotely operated on the remotely operated valves cause the remotely operated valves valves identified in Table 2.3.2-1 identified in Table 2.3.2-1 using identified in Table 2.3.2-1 to to perform active functions. the controls in the MCR. perform active functions. 10.b) The valves identified in i) Testing will be performed i) The valves identified in Table 2.3.2-1 as having PMS usir.g real or simulated signals Table 2.3.2-1 as having PMS control perform an active safety into the PMS. control perform the active function function after receiving a signal identified in the table after from ths PMS. receiving a signal from the PMS. ii) Testing will be perfonned to ii) These valves close within the demonstrate that the remotely following times after receipt of an operated CVS isolation valves actuation signal: CVS-V090, V091, V136A/B close within the required V090,V091 < 10 sec , response time. V136A/B < 20 sec j 11.a) The motor-operated i) Tests or type tests of i) A test report exists and and check valves identified in motor-operated valves will be concludes that each motor-Table 2.3.2-1 perform an active performed that demonstrate the operated valve changes position safety-related function to change capability of the valve to operate as indicated in Table 2.3.2-1 position as indicated in the table. under its design conditions. under design conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are bounded by the tests or motor-operated valves are type tests. bounded by the tested conditions. 2.3.2-12 W8Stillghouse oNTAACS\rev5\it020302.wpt:1 t>050198
Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM : 1 Revision: 5 (] Q Effective: 5/8/98 Table 2.3.2 4 (cont.) I Inspections, Tests, Analyses, and Acceptance Criteria ! Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1 iii) Tests of the as-installed iii) Each motor-operated valve { motor-operated valves will be changes position as indicated in performed under pre-operational Table 2.3.2-1 under pre-operational , flow, differential pressure, and test conditions. ,, { temperature conditions. l I iv) Exercise testing of the check iv) Each check valve changes valves with active safety position as indicated in functions identified in Table 2.3.2-1. Table 2.3.2-1 will be performed under pre-operational test pressure, temperature and fluid flow conditions. 11.b) After loss of motive power, Testing of the installed valves Upon loss of motive power, each the remotely operated valves will be performed under the remotely operated valve identified identified in Table 2.3.2-1 assume conditions of loss of motive in Table 2.3.2-1 assumes the the indicated loss of motive power, indicated loss of motive power power position, position. ( .sV) ] 12.a) Controls exist in the MCR Testing will be performed to Controls in the MCR cause pumps to cause the pumps identified in actuate the pumps identified in identified in Table 2.3.2-3 to Table 2.3.2-3 to perform the Table 2.3.2-3 using controls in perform the listed function. l listed function. the MCR. l 12.b) He pumps identified in Testing will be performed to ne pumps identified in Table 2.3.2-3 start after receiving confirm starting of the pumps Table 2.3.2-2 start after a signal is a signal from the PLS. identified in Table 2.3.2-3. generated by the PLS.
- 13. Displays of the parameters Inspection will be performed for Displays identified in Table 2.3.2-3 identified in Table 2.3.2-3 can be retrievability of the displays can be retrieved in the MCR.
retrieved in the MCR. identified in Table 2.3.2-3 in the MCR. I 14. The nonsafety-related piping Inspection will be conducted of ne CVS Seismic Analysis located inside containment and the as-built components as Reports exist for the non-safety designated as reactor coolant documented in the CVS Seismic related piping located inside pressure boundary, as identified Analysis Report. containment and designated as in Table 2.3.2-2, has been reactor coolant pressure boundary designed to withstand a seismic as identified in Table 2.3.2-2. design basis event and maintain structural integrity. O v 2.3.2-13 W85tkigh0llSB o:VTAACSvev5Vt020302.wpf:1 b-050698
Certified DeCign Material CHEMICAL AND VOLUME CONTROL SYSTEM Revision: 5 Effective: 5/8/98 _ Table 2.3.2-5 Component Name Tag No. Component Location CVS Makeup Pump A CVS-MP-01A Auxiliary Building CVS Makeup Pump B CVS-MP-OlB Auxiliary Building Boric Acid Tank CVS-MT-02 Yard Regenerative Heat Exchanger CVS-ME-01 Containment Letdown Heat Exchanger CVS-ME-02 Containment Mixed Bed Demineralized A CVS-MV-01A Containment Mixed Bed Demineralized B CVS-MV-OlB Containment Cation Bed Demineralized CVS-MV-02 Containment Reactor Coolant Filter A CVS.MV-03A Containment Reactor Coolant Filter B CVS-MV-03B Containment 9 1 O 2.3.2-14 W W8StingtNHISO oNTAACsvev5sito20302.wpf:1b-oso19e
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Certified Design Material STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM A Revision: 5 V Effective: 5/8/98 2.3.3 Standby Diesel and Auxiliary Boiler Fuel Oil System Design Description The standby diesel and auxiliary boiler fuel oil system (DOS) supplies diesel fuel oil for the onsite standby power system. The diesel fuel oil is supplied by two above-ground fuel oil storage tanks. The DOS also provides fuel oil for the ancillary diesel generators. A single fuel oil storage tank services both ancillary diesel generators. The DOS is as shown in Figure 2.3.3-1 and the component locations of the DOS are as shown in Table 2.3.3-3.
- 1. The functional arrangement of the DOS is as described in the Design Description of this Section 2.3.3.
- 2. The ancillary diesel generator fuel tank can withstand a seismic event.
- 3. 'Ihe DOS provides the following nonsafety-related functions:
a) Each fuel oil storage tank provides for at least 7 days of continuous operation of the associated i standby diesel generator, (q v./ 4 b) Each fuel oil day tank provides for at least four hours of continuous operation of the associated standby diesel engine generator.
)
c) The fuel oil flow rate to the day tank of each standby diesel generator provides for continuous operation of the associated diesel generator, d) The ancillary diesel generator fuel tank is sized to supply power to long-term safety-related post-accident monitoring loads and control room lighting through a regulating transformer and one PCS recirculation pump for a period of 4 days.
- 4. Controls exist in the main control room (MCR) to cause the components identified in Table 2.3.3-1 to perform the listed function.
- 5. Displays of the parameters identified in Table 2.3.3-1 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.3-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the DOS. O 2.3.3-1 W85tingh00S8 oNTAACSirev5\it020303.wpf:1 b-050398 l f i ( .__ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Certified Design Material STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM 7~ - l Revision: 5 Effective: 5/8/98 _ l ! Table 2331 Control Equipment Name Tag No. Display Function l Diesel Fuel Oil Pump 1 A (Motor) DOS-MP-01A Yes Stan l (Run Status) j Diesel Fuel Oil Pump 1B (Motor) DOS-MP-OlB Yes Start (Run Status) Diesel Generator Fuel Oil Day Tank A Level DOS-016A Yes
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Diesel Generator Fuel Oil Day Tank B Level DOS-016B Yes - Note: Dash (-) in& cates not applicable. O O E Westinghouse o:VTAACSVev5WO20303. wpm S 9 j l
Certified Design Material STANDBY DIESEL AND AUXILIARY BolLER FUEL OIL SYSTEM ' == l fa Revision: 5 = l Q Effective: 5/8/98 _ Table 2.3.3-2 Inspections, Tests, Analyses, and Acceptance Criteria 1 Design Commitment Inspections, Tests, Analyses Acceptance Criteria I
- 1. He functional arrangement of Inspection of the as-built system ne as. built DOS conforms with the the DOS is as described in the will be performed. functional arrangement described in i Design Description of this the Design Description of this Section 2.3.3. Section 2.3.3. I
- 2. The ancillary diesel generator Inspection will be performed for A report exists and concludes that fuel tank can withstand a seismic the existence of a report verifying the as-installed ancillary diesel event. that the as-installed ancillary generator fuel tank and its diesel generator fuel tank and its anchorage are designed using anchorage are designed using seismic Category II methods and seismic Category II methods and criteria.
criteria. 3.a) Each fuel oil storage tank Inspection of each fuel oil storage ne volume of each fuel oil storage provides for at least 7 days of tank will be performed. tank is greater than or equal to continuous operation of the 55,000 gallons between the diesel associated standby diesel generator. generator fuel oil day tank supply connection and the auxiliary boiler supply connection.
/ 3.b) Each fuel oil storage day tank Inspection of the fuel oil day tank He volume of each fuel oil day C]/ provides for at least 4 hours of operation of the associated standby will be performed. tank is greater than or equal to 1300 gallons. I diesel generator.
3.c) ne ft el oil flow rate to the Testing will be performed to The flow rate delivered to each day day tank of each standby diesel determine the flow rate. tank is 8 gpm or greater. generator provides for continuous operation of the associated diesel generator. 3.d) ne ancillary diesel generator Inspection of the ancillary diesel The volume of the ancillary diesel fuel tank is sized to supply power generator fuel tank will be generator fuel tank is greater than or to long-term safety-related post performed. equal to 450 gallons. accident monitoring loads and i control room lighting through a regulating transformer and one PCS recirculation pump for four l days. l
- 4. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to ;
cause the components identified in compcnents in Table 2.3.3-1 using cause the components listed in Table l Table 2.3.3-1 to perform the listed controls in the MCR. 2.3.3-1 to perform the listed function. functions.
- 5. Displays of the parameters Inspection will be performed for ne displays identified in identified in Table 2.3.31 can be retrievability of parameters in the Table 2.3.3-1 can be retrieved in the retrieved in the MCR. MCR. MCR.
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'2.3.3-3 )
MIMS8 oNTAACS\rev5\it020303.wpf:1 b-050398 l l
Certified Desicn Material STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM +-m Revision: 5 -
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Effective: 5/8/98 1 . et Table 2.3.3-3 Component Name Tag No. Component Location Diesel Oil Transfer Package A DOS-MS-01A Yard Diesel Oil Transfer Package B DOS-MS-OlB Yard Fuel Oil Storage Tank A DOS-MT-01 A Yard Fuel Oil Storage Tank B DOS-MT-OlB Yard Diesel Generator A Fuel Oil Day Tank DOS-MT-02A Diesel Building Diesel Generator B Fuel Oil Day Tank DOS-MT-02B Diesel Building Ancillary Diesel Fuel Oil Storage Tank DOS-MT-03 Annex Building O O T Westinghouse o:VTAACSVev5VtTOM.wpf:1 8
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Certified Design Material l FIRE FROTECTION SYSTEM - -.
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i /N Revision: 5 " : I () Effective: 5/8/98 1 - ,ee 2.3.4 Fire Protection System Design Description i The fire protection system (FPS) detects and suppresses fires in the plant. The FPS consists of water I distribution systems, automatic and manual suppression systems, a fire detection and alarm system, and l l portable fire extinguishers. The FPS provides tire protection for the nuclear island, the annex building, I the turbine building, the radwaste building and the diesel generator building. The FPS is as shown in Figure 2.3.4-1 and the component locations of the FPS are as shown in Table 2.3.4-3. l
- 1. The functional arrangement of the FPS is as described in the Design Description of this Section 2.3.4.
- 2. The FPS piping identified in Figure 2.3.4-1 remains functional following a safe shutdown earthquake. l
- 3. Tlee FPS provides the safety-related function of preserving containment integrity by isolation of the FPS line penetrating the containment.
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- 4. The FPS provides for manual fire fighting capability in plant areas containing equipment required for safe shutdown. .
- 5. Displays of the parameters identified in Table 2.3.4-1 can be retrieved in the main control room i (MCR).
- 6. The FPS provides nonsafety-related containment spray for severe accident management.
l l 7. The FPS provides two fire water storage tanks, each capable of holding at least 300,000 gallons of I l water. I i 8. Two FPS fire pumps provide at least 2000 gpm each at a total head of at least 300 ft. l l ; I 9. The fuel tank for the diesel-driven fire pump is capable of holding at least 240 gallons. 1 l l l 10. Individual fire detectors in the fire areas that support safe shutdown provide fire detection i i capability and can be used to initiate fire alarms. I i i 11. The FPS seismic standpipe subsystem can be supplied from the FPS fire main by opening the I i normally closed cross-connect valve to the FPS plant fire main. l Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.4-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the FPS. J 2.3.4-1 W85tingh0llSe o:VTAACSWv5\it020304.wpf:1 b-050198 1
C:rtified Design MItzrial FIRE PROTECTION SYSTEM 2 Revision: 5 - Effective: 5/8/98 1 . l-Table 2.3.41 Equipment Name Tag No. Display Control Function Motor-driven Fire Pump FPS-MP-01A Yes (Run Status) Start Diesel-driven Fire Pump FPS-MP-OlB Yes (Run Status) Start Jockey Pump FPS-MP-02 Yes (Run Status) Start O O 2.3.4-2 NNIDM8 0:VTAACSVev5Vt020304.wpf 1b-050198 l l l
Csrtified De:Ign M:teri:1 FIRE PROTECTION SYSTEM PC Revision: 5 " Effective: 5/8/98 _ Table 2.3.4 2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arangement of Inspection of the cs-built system he as-built FPS conforms with the FPS is as desenbed in the will be performed. the functional arrangement Design Description of this described in the Design Section 2.3.4. Description of this Section 2.3.4.
- 2. He FPS piping depicted in i) Inspection will be performed i) The piping depicted in Figure 2.3.4-1 remains functional to verify that the piping depicted Figure 2.3.4-1 is located on following a safe shutdown in Figure 2.3.4-1 is located on the Nuclear Island.
earthquake. the Nuclear Islard. ii) A reconci ation analysis ii) ne as-built piping stress report using the as-designed and as- exists and concludes that the built piping information will be piping remains functional performed, or an analysis of the following a safe shutdown as-built piping will be carthquake. performed.
- 3. The FPS provides the safety- See Certified Design Material, See Certified Design Material, related function of preserving subsection 2.2.1, Containment subsection 2.2.1, Containment containment integrity by isolation System. System.
of the FPS line penetrating the containment.
- 4. He FPS provides for manual i) Inspection of the passive i) ne volume of the PCS tank fire fighting capability in plant containment cooling system above the standpipe feeding the areas containics equ!pment (PCS) storage tank will be FPS and below the overflow is at required for safe shutdown. performed. least 18,000 gal.
ii) Testing will be performed by measuring the water flow rate as ii) Water is simultaneously it is simultaneously discharged discharged from each of the two from the two highest fire. hose highest fire-hose stations at not stations and when the water for less than 75 gpm. the fire is supplied from the PCS storage tank. [ WBStingh0USB 2.3.4-3 oNTAACSVev5Vt020304.wpf:1b 050198
Certified Design Material FIRE PROTECTION SYSTEM i s _- Revision: 5 Effective: 5/8/98 Table 2.3.4-2 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 5. Displays of the parameters Inspection will be performed for The disp'ays identified in Table identified in Table 2.3.4-1 can be retrievability of the parameters in 2.3.4-1 can be retrieved in the retrieved in the MCR. the MCR. MCR.
- 6. The FPS provides nonsafety- Inspection of the containment The FPS has spray headers and related containment spray for spray headers will be performed. nozzles as follows:
severe accident management. At least 44 nozzles at plant elevation of at least 235 feet, and 24 nozzles at plant elevation of at least 250 feet. I 7. The FPS provides two fire Inspection of each fire water The volume of each fire water I water storage tanks, each capable storage tank will be performed. storage tank supplying the FPS is I of holding at least 300,000 at least 300,000 gallons. I gallons of water. I 8. Two FPS fire pumps provide Testing and/or analysis of each The tests and/or analysis concludes I at least 2000 gpm each at a total fire pump will be performed. that each fire pump provides a i head of at least 300 ft. flow rate of at least 2000 gpm at a i total head of at least 300 ft. I 9. The fuel tank for the diesel- Inspection of the diesel-driven The volume of the diesel driven I driven fire pump is capable of fire pump fuel tank will be fire pump feel tank is at least I holding at least 240 gallons. performed. 240 gallons. I 10. Individual fire detectors in Testing will be performed on the The tested individual fire detectors i the fire areas that support safe as-built individual fire detectors respond to simulated fire I shutdown provide fire detection in the fire areas identified in conditions. I capability and can be used to Certified Design Material, I initiate fire alarms. subsection 3.3, Table 3.3-3. I (Individual fire detectors will be I tested using simulated fire I conditions.) I 11. The FPS seismic standpipe Inspection for the existence of a Valve FPS-PL-V050 exists and can I subsystem can be supplied from cross-connect valve from the connect the FPS seismic standpipe I the FPS fire main by opening the FPS seismic standpipe subsystem subsystem to the FPS plant fire I normally closed cross-connect to FPS plant fire main will be main. I valve to the FPS plant fire main, performed. O 2.3.4-4 W Westinghouse oWAACSvev5WY20304.wpu b-050498
{ Certified Design Material FIRE PROTECTION SYSTEM -
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Revision: 5 =i [] V Effective: 5/8/98 1 . ,, Table 2.3.4 2 Component Name Tag No. Location i Motor-driven Fire Ptu.;e FPS-MP-01A Turbine Building l Diesel-driven Fire Pump FPS-MP-OlB Yard Jockey Pump FPS-MP-02 Turbine Building Primary Fire Water Tank FPS-MT-01 A Yard Secondary Fire Water /Clearwell Storage Tank FPS-MT-01B Yard l Fire Pump Diesel Fuel Day Tank FPS-MT-02 Turbine Building 5 O o b , 2.3.4-5 MMUS8 0:'JTAACSvev5\it020304.wpf;1 b-050198 l
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Effective: 5/8/98 2.3.5 Mechanical Handling System Design Description The mechanical handling system (MHS) provides for lifting heavy loads. The MHS equipment can be operated during shutdown and refueling. The component locations of the MHS are as shown in Table 2.3.5-3. I
- 1. The functional arrangement of the MHS is as described in the Design Description of this 1 Section 2.3.5.
I 2. The seismic Category I equipment identified in Table 2.3.5-1 can withstand seismic design basis loads without loss of safety function. I 3. The MHS provides the following safety-related functions: a) The containment polar crane prevents the uncontrolled lowering of a heavy load. b) The equipment hatch hoist prevents the uncontrolled lowering of a heavy load. l 4. The spent fuel shipping cask crane cannot move over the spent fuel pool. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.5-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the MHS. D U@lIS8 oNTAACSirev5\it020305.wpf:1 tM0198 2.3.5-1
Certified Design Material MECHANICAL HANDLING SYSTEM C4
~
Revision: 5 E Effective: 5/8/98 i * . s. I Table 2.3.5-1 ClassIFl Seismic Qual. for Equipment Name Tag No. Cat. I Harsh Envir. Safety Function Containment Polar Crane MHS-MH-01 Yes No/No Avoid uncontrolled lowering of heavy load Equipment Hatch Hoist MHS-MH-05 Yes No/No Avoid uncontrolled lowering of heavy load O, l 0' r = = a use o__.__ =" l I
Certified Design Mitert:1 MECHANICAL HANDLING SYSTEM a Revision: 5 - 3: Effective: 5/8/98 1 et Table 2.3.5 2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. The functional arrangement of Inspection of the as-built system ne as-built MHS is as described I the MHS is as described in the will be performed. in the Design Description of this l Design Description of this Section 2.3.5. l Section 2.3.5. I 2. The seismic Category I i) Inspection will be performed i) ne seismic Category I equipment identified in to verify that the seismic equipment identified in Table 2.3.5-1 can withstand Category I equipment identified Table 2.3.5-1 is located on the seismic design basis loads in Table 2.3.5-1 is located on the Nuclear Island. without loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage bounded by the tested or analyzed is seismically bounded by the conditions. tested or analyzed conditions. l 3.a) ne containment poler crane Load testing of the main and The crane lifts the test load, and prevents the uncontrolled auxiliary hoist" that handle lowers, stops, and holds the test lowering of a heavy load. heavy loads will be performed. loa <1 with the hoist holding brakes. The test load will be at least equal to the weight of the reactor vessel head and I integrated head package. l 3.b) The equipment hatch hoat Testing of the redundant hoist Each hoist holding mechanism prevents the uncontrolled holding mechanisms for the stops and holds the hatch. lowering of a heavy load. main hoist that handles heavy loads will be performed by lowering the hatch at the maximum operating speed. I 4. He spent fuel shipping cask Testing of the spent fuel The spent fuel shipping cask crane crane cannot move over the spent shipping cask crane is does not move over the spent fuel fuel pool, perfonned. pool. s 2.3.5-3 W8dfibilS8 o:VTAACSVev5WO20305.wpf:1 b-050198
Certified Design Material EdCHANICAL HANDLING SYSTEM 3 Revision: 5 2 Effective: 5/8/98 . Table 2.3.5 3 Component Name Tag No. Component Location Containment Polar Crane MHS-MH-01 Containment Equipment Hatch Hoist MHS-MH-05 Containment Spent Fuel Shipping Cask Crane MHS-MH-02 Auxiliary Building O 1 1 O r=- o_.__,m = l l
W\ __ Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM " Revision: 5 (m) v Effective: 5/8/98 - 2.3.6 Normal Residual Heat Removal System He normal residual heat removal system (RNS) removea heat frotr. the core and reactor coolant system (RCS) and provides RCS low temperature over-pressure (LTOP) protection at reduced RCS pressure and temperature conditions after shutdown. %e RNS also povides a meaas for cochng the in-containment refueling water storage tank (IRWST) dudng normal pbnt operation. The RNS is as shown in Figure 2.3.6-1 and the RNS component locations are as showa in Table 2.3.6-5.
- 1. He functional arrangement of the RNS is as described in the Design Description of this Section 2.3.6.
- 2. a) The components identified in Table 2.3.6-1 es ASME Code Section IU are dengned end constmeted in accordance with ASME Code Section III requirements.
b) He piping identified in Table 2.3.6-2 as ASME Code Section III is dedgned and constmeted in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.
m b b) Pressure boundary welds in piping identified in Table 2.3.6-2 as ASME r ods Rection UI meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.3.6-1 as ASME Code Section IU retain their presstcre boundary integrity at their design pressure.
b) The piping identified in Table 2.3.6-7 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.3.6-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.3.6-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
- 6. Each of the as-built lines identified in Table 2.3.6-2 as designed for leak before bmak (LBB) meets the LBB criteria, or an evaluation is performed of the protection froin the dynamic effects of a mpture of the line.
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l 1 ( Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM 4= , Revislan: 5 ) Effective: 618/98
- 7. a) The Class IE equipment identified in Table 2.3.6-1 as being qutlified for a harsh enyvonment can withstand the enviromnental conditions that would exist before, during, and followmg a design basis accident witheat loss of safety futction for the time tequired to perform the safety fM1Clion. )
b) The Cass IE components identified in Table 2.3.6-1 are powered from their respective Class IE division. i
- ) Separation is piovided between RNS Class IE divisions, and between Class IE divisions and I non-Class lE cable. j
- 8. Th: RNS provides the following safety-related functioas:
a) The RNS preserves containment integrity by isolation of the RNS lines penetrating the j containment. b) De RNS prowides a fiow path for long-tenn, post-accidem makeup to the RCS.
- 9. The RNS provides the following nonsafety-rehted functions:
a) he RNS provides low temperature overpressure protection (LTOP) for the RCS dming l shutdown operations. b) ne RNS provides heat removal from the reactor coolant during Amtdown operations. c) The RNS provides low pressure makeup flow from the in-containment refueling water storage I tank (IRWST) to the RCS for scenarios following actuation of the automatic depressurization I system (ADS). d) he RNS provides heat removd from the in-containment refueling wacer storage tank. i
- 10. Safety-related displays identified in Table 2.3.6-1 can be retrieved in the main control room l
(MCR). i , 11. a) Controls exist in the MCR to caase those remotely operated valves identifiM in Table 2.3.6-1 to perform active functions. b) ne valves identified in Table 2.3.61 as having protection and safety monitoting system l l (PMS) control perform active safety functions after receiving a signal from the PMS. l I
- 12. a) The motor-operated and check valves identified in Table 2.3.6-1 perform an active safety- ;
related function to change position as indicated in the table. l b) After loss of motive power, the remotely operated valves identified in Table 2.3.6-1 assume the indicated loss of motive power position. 2.3.s-2 3 Westinghouse oNTAAOSvev5M0203o6.wpt i t>-050398 I
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Certified Design Material NORMAL. RESIDUAL HEAT REMOVAL SYSTEM = - - f^ Revision: 5 r Ts Effective: 5/&S8
- 13. Controls exict in the MCR to cause the pumps identified in Table 2.3.6-3 to perfonn the listed function.
- 14. Displays of the RNS parameters identified in Table 2.3.6-3 can be retrieved in the MCR.
l'tspections, Tests, Analyses, and Acceptance Criteria Tat le 2.3.6-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the RNS. ! l l I O) L 1 A U DE oNTAACSVev5Nt020306.wpf:1 1 1
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Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM "-m m Revision: 5 (j
=E Effective: 5/8/98 i t Table 2.3.6 3 Equipment Name Tag No. Display Control Function RNS Pump 1 A (Motor) RNS-MP-01A Yes Start (Run Status)
RNS Pump IB (Motor) RNS-MP-OlB Yes Start I (Run Status) l RNS Flow Sensor RNS-01A Yes - RNS Flow Sensor RNS-OlB Yes - Note: Dash (-) indicates not applicabic. {~\ O (O 2.3.6-9 M lfigh0tlS8 o:VTAACSVev5Vt020306.wpt:1 b-OS0398 1 i
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM Revision: 5 Effective: 5/8/98 _ Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built RNS conforms with I the RNS is as described in the will be performed. the functional arrangement l Design Description of this described in the Design Section 2.3.6. Descripdon of this Section 2.3.6. , )
2.a) 'Ihe components identified Inspection will be conducted of The ASME Code Section III in Table 2.3.6-1 as ASME Code the as-built components as design reports exist for the as-built Section III are designed and documented in the ASME design components identified in
)
constructed in accordance with reports. Table 2.3.6-1 as ASME Code . ASME Code Section III Section III. j requirements. 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.3.6-2 as ASME Code the as-built piping as design reports exist for the as-built Section III is designed and documented in the ASME design piping identified in Table 2.3.6-2 constructed in accordance with reports. as ASME Code Section III. ASME Code Section III requirements. 3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes that components identified in pressure boundary welds will be the ASME Code Section III Table 2.3.6-1 as ASME Code performed in accordance with requirements are met for non-Section III meet ASME Code the ASME Code Section III. destructive examination of pressure Sectior' III requirements. boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built A repon exists and concludes that piping identified in Table 2.3.6-2 pressure boundary welds will be the ASME Code Section III as ASME Code Section III meet performed in accordance with requirements are met for non-ASME Code Section III the ASME Code Section III. destructive examination of pressure requirements. boundary welds. 4.a) The components identified A hydrostatic test 21125 psi will A report exists and concludes that in Table 2.3.6-1 as ASME Code be performed on the 900 psi the results of the hydrostatic test of Section III retain their pressure design pressure components the components identified in boundary integrity at their design required by the ASME Code Table 2.3.6-1 as ASME Code pressure. Section III to be hydrostatically Section III conform with the tested. requirements of the ASME Code Section III. O l 2.3.6 10 W85tifigh00S8 oMTAACSirev5\it020306 wpt:1tH)S0398
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM ' l A Revision: 5 (j Effective: 5/8/98 i Table 2.3.6-4 (cont.) l Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.b) "Ihe piping identified in Table A hydrostatic test 21125 psi will A report exists and concludes that 2.3.6-2 as ASME Code Section 111 be performed on the 900 psi the results of the hydrostatic test of retains its pressure boundary design pressure piping required by the piping identified in Table 2.3.6-2 integrity at its design pressure. the ASME Code Section III to be as ASME Code Section III conform hydrostatically tested. with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.3.61 can withstand equipment identified in Table 2.3.6-1 is located on the seismic design basis loads without Table 2.3.61 is located on the Nuclear Island. loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. p) V iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage is bounded by the tested or analyzed seismically bounded by the tested conditions. or analyzed conditions. 5.b) Each of the lines identified in Inspection will be performed for A report exists and concludes that Table 2.3.6-2 for which functional the existence of a repon verifying each of the as-built lines identified capability is required is designed to that the as-built piping meets the in Table 2.3.6-2 for which J withstand combined normal and requirements for functional functional capability is required seismic design basis loads without capability. meets the requirements for a loss of its functional capability. functional capability. ;
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation repon exists and identified in Table 2.3.6-2 as the existence of an LBB concludes that the LBB acceptance designed for LBB meets the LBB evaluation repon or an evaluation criteria are met by the as-built RCS criteria, or an evaluation is repon on the protection from piping and piping materials, or a performed of the protection from dynamic effects of a pipe break. pipe break evaluation repon exists the dynamic effects of a rupture of Cenified Design Material, and concludes that protection from the line. Section 3.3, Nuclear Island the dynamic effects of a line break l Buildings, contains the design is provided. I descriptions and inspections, tests, analyses, and acceptance criteria :
for protection from the dynamic effects of pipe rupture. 1 g ; ) L) 2.3.6-11 W8Sdf@00S8 oNTAACSirev5Nt020306.wpf:1 t>-050398 1 l
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM ~ Revision: 5 Effective: 5/8/98 Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment laspections, Tests, Analyses Acceptance Criteria 7.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Tables 2.3.6-1 as combination of type tests and the Class IE equipment identified in being qualified for a harsh analyses will be performed on Table 2.3.6-1 as being qualified for environment can withstand the C'. ass IE equipment located in a a harsh environment can withstand environmental conditions that harsh environment. the environmental conditions that would exist before, during, and would exist before, during, and following a design basis accident following a design basis accident without loss of safety function for without loss of safety function for the time required to perform the the time required to perform the safety function. safety function. 7.b) The Class IE components Testing will be performed on the A simulated test signal exists at the identified in Table 2.3.6-1 are RNS by providing a simulated test Class IE equipment identified in powered from their respective signal in each Class IE division. Table 2.3.6-1 when the assigned Class IE division. Class IE division is provided the test signal. 7.c) Separation is provided See Certified Design Material, See Certified Design Material, between RNS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class lE divisions Buildings. Buildings. and non-Class IE cable. 8.a) He RNS preserves See Certified Design Material, See Certified Design Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the RNS lines penetrating the System. System. containment. 8.b) He RNS provides a flow See item I in this table. See item I in this table. path for long. term, post. accident makeup to the RCS. 9.a) ne RNS provides LTOP for i) Inspections will be conducted i) The rated capacity recorded on the RCS during shutdown on the low temperature the valve vendor code plate is not operations. overpressure prctection relief less than 555 gpm. valve to confirm that the capacity of the vendor code plate tating is greater than or equal to system relief requirements. l ii) Testing and analysis in ii) A report exists and concludes accordance with the ASME Code that the relief valve opens at a Section III will be performed to pressure such that the relief capacity determine set pressure. is not less than 555 gpm at a pressure of 621 psig. l i 2.3.6-12 W85tirigt10llS8 oNTAACSirev5\it020306.wpf:1 b 050398 l } l L __ _ _ )
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM =
,rg Revision: 5 -
=
Q Effective: 5/8/98 .
.u Table 2.3.6-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 9.b) De RNS provides heat i) Inspection will be performed i) A report exists and concludes removal from the reactor coolant for the existence of a report that that the product of the overall heat during shutdown operations. determines the heat removal transfer coefficient and the effective capability of the RNS heat heat transfer area, UA, of each RNS exchangers. heat exchanger is greater than or equal to 2.0 million Btu /hr *F. ii) Testing will be performed to ii) Each RNS pump provides at confirm that the RNS can provide least 900 gpm net flow to the RCS flow through the RNS heat when the hot leg water level is at an exchangers when the pump elevation 15.5 inches 22 inches suction is aligned to the RCS hot above the bottom of the hot leg. leg and the discharge is aligned to both PXS DVI lines with the RCS at atmospheric pressure. iii) Inspection will be performed iii) The RCS cold legs piping of the reactor coolant loop piping. centerline is 17.5 inches t 2 inches f\ above the hot legs piping centerline. 'b iv) Inspection will be performed iv) he RNS pump suction piping , of the RNS pump suction piping. from the hot leg to the pump suction I piping low point does not form a local high point (defined as an upward slope with a vertical rise 4 greater than 3 inches). ) v) Inspection will be performed v) The RNS suction line connected of the RNS pump suction nozzle to the RCS is constructed from 20-connection to the RCS hot leg. inch Schedule 160 pipe. I 9.c) The RNS provides low Testing will be performed to Each RNS pump provides at least pressure makeup flow fro.n the confirm that the RNS can provide 925 gpm net flow to the RCS when IRWST to the RCS for scenarios low pressure makeup flow from the water level above the bottom of following actuation of the ADS. the IRWST to the RCS when the the IRWST is 4 feet 12 inches. pump suction is aligned to the IRWST and the discharge is aligned to both PXS DVI lines with RCS at atmospheric pressure. l
\b 2.3.6-13
[ W85tingh00S8 oNTAACSvev5\it020306.wptibG0398
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM ,=_ Revision: 5 - r Effective: 5/8/98 i*.et Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 9.d) The RNS provides heat Testing will be performed to Each RNS pump provides at least removal from the in-containment confirm that the RNS can provide 925 gpm to the IRWST. refueling water storage tank flow through the RNS heat (IRWST). exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST.
~
- 10. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.3.6-1 can be retrievability of the safety-related Table 2.3.6-1 can be retrieved in the retrieved in the MCR. displays in the MCR. MCR.
I1.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause those remotely operated on the remotely operated valves cause those remotely operr.ted valves identified in Table 2.3.6-1 identified in Table 2.3.6-1 using valves identified in Table 2.3.6-1 to to perform active functions. the controls in the MCR. perform active functions. I1.b) The valves identified in Testing will be performed using The valves identified in Table 2.3.6-1 as having PMS real or simulated signals into the Table 2.3.6-1 as having PMS control control perform active safety PMS. perform the active function functions after receiving a signal identified in the table after receiving from the PMS. a signal from the PMS. O T Westinghouse omAAesvevsvto2030s.wpu 0398
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM
^
=
(y Revision: 5
! ) Effective: 5/8/98 _
v Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria I 12.a) The motor-operated and i) Tests or type tests of motor- i) A test report exists and concludes check valves identified in operated valves will be performed that each motor-operated valve Table 2.3.6-1 perform an active that demonstrate the capability of changes position as indicated in safety-related function to change the valve to operate under its Table 2.3.6-1 under design ) position as indicated in the table. design conditions. conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are bounded by the tested motor-operated valves are conditions. bounded by the tested conditions. t iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under preoperational Table 2.1.2-1 under preoperational flow, differential pressure and test conditions. temperature conditions. 1 O iv) Exercise testing of the check iv) Each check valve changes !
\ ) valves active safety functions position as indicated in identified in Table 2.3.6-1 will be Table 2.3.6-1.
performed under preoperational test pressure, temperature and fluid flow conditions. 12.b) After loss of motive power, Testing of the installed valves will Upon loss of motive power, each the remotely operated valves be performed under the conditions remotely operated valve identified in identified in Table 2.3.6-1 assume ofloss of motive power. Table 2.3.6-1 assumes the indicated the indicated loss of motive power loss of motive power position. position.
- 13. Controls exist in the MCR to Testing will be performed to Controls in the MCR cause pumps cause the pumps identified in actuate the pumps identified in identified in Table 2.3.6-3 to Table 2.3.6-3 to perform the listed Table 2.3,6-3 using controls in the perform the listed action.
function. MCR.
- 14. Displays of the RNS Inspection will be performed for Displays of the RNS parameters parameters identified in retrievability in the MCR of the identified in Table 2.3.6-3 are Table 2.3.6-3 can be retrieved in displays identified in retrieved in the MCR.
the MCR. Table 2.3.6-3. o 2.3.6-15 W85tirighouse oNTAACSirev5\it020306.wpf:1 b-050398 l
l Certified Design Material
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NORMAL RESIDUAL HEAT REMOVAL SYSTEM
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Revision: 5 P Effective: 5/8/98 TaHe 2.3.6-5 Component Name Tag No. Component Location RNS Pump A RNS-MP-01 A Auxiliary Building RNS Pump B RNS-MP-OlB Auxiliary Building RNS Heat Exchanger A RNS-ME-01A Auxiliary Building RNS Heat Exchanger B RNS-ME-OlB Auxiliary Building ; l l l e l 2.3.6-16 o l W85tlD@uS8 o:VTAACSirev!Nt020306.wpf:1 b-050398
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Certified Design Material SPENT FUEL POOL COOLING SYSTEM --t E (~T Revision: 5 V Effective: 5/8/98 _ 2.3.7 Spent Fuel Pool Cooling System Design Description The spent fuel pool cooling system (SFS) removes decay heat from the water in the spent fuel pool and transfers the heat to the component cooling water system during normal modes of operation. He SFS purifies the water in the spent fuel pool, fuel transfer canal, and in-containment refueling water - storage tank during nonnal modes of operation. The SFS is as shown in Figure 2.3.7-1 and the component locations of the SFS are as shown in Table 2.3.7-5. I
- 1. He functional arrangement of the SFS is as described in the Design Description of this l Section 2.3.7.
- 2. The piping identified in Table 2.3.7-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
- 3. Pressure boundary welds in piping identified in Table 2.3.7-2 as AShE Code Section III meet ASME Code Section III requirements.
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- 4. The piping identified in Table 2.3.7-2 as AShE Code Section III retains its pressure boundary integrity at its design pressure.
- 5. The seismic Category I equipment ider:tified in Table 2.3.7-1 can withstand seismic design basis loads without loss of safety function.
- 6. a) The Class IE components identified in Table 2.3.7-1 are powered from their respective Class IE division.
! b) Separation is provided between SFS Class IE divisions, and between Class IE divisions and non-Class 1E cable.
- 7. He SFS provides the following safety-related functions:
a) The SFS preserves containment integrity by isolation of the SFS lines penetrating the containment i b) The SFS provides spent fuel cooling for 7 days by boiling water in the pool and providing makeup water from safety-related sources.
- 8. De SFS provides the nonsafety-related function of removing spent fuel decay heat using pumped flow through a heat exchanger.
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v 2.3.7-1 1 l [ W85tingh00S8 c:VTAACSVev5V020307.wpf:1 t>050198 l
Certified Design Material
-=q SPENT FUEL POOL COOLING SYSTEM Revision: 5 i I
Effective: 5/8/98
- 9. Safety-related displays identified in Table 2.3.7-1 can be retrieved in the main control room (MCR).
- 10. Controls exist in the MCR to cause the pumps identified in Table 2.3.7-3 to perform their listed functions.
- 11. Displays of the SFS parameters identified in Table 2.3.7-3 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.7-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the SFS. O O 2.3.7-2 Wamm Westinghouse o:\lTAACSVev5Vt020307.wpf:1 t>050198 l
Cedified Design Mat: rid SPENT FUEL POOL COOLING SYSTEM Flevision: 5 O Effective: 5/8/98 Table 2.3.71 Class IE/ Seismic Qual. for Equipment Name Tag No. Cat. I Harsh Envir. Safety Related Display Spent Fuel Pool Level Sensor SFS-019A Yes Yes/No Yes Spent Fuel Pool Level Sensor SFS-019B Yes Yes/No Yes [ Spent Fuel Pool Level Sensor SFS-019C Yes Yes/No Yes
! Table 2.3.7 2 Line Name Line Nnmber ASME Code Section III Fuel Transfer Canal Draid LO47 Yes Cask Washdown Pit Drain LO68 Yes Cask Loading Pit Drair
( Transfer Branch Line LG43 LO45 Yes Yes Reactor Cavity Drain LO30 Yes Table 2.3.7 3 Equipment Name Tag No. Display Control Function SFS Pump 1 A SFS-MP-01A Yes Stan (Run Status) SFS Pump IB SFS-MP-OlB Yes Etart .l
, (Run Status)
SFS Flow Sensor SFS-13A Yes - SFS Flow Sensor SFS-13B Yes - s Spent Fuel Pool Temperature Sensor SFS-018 Yes - Mote: Dash (-) indicates not applicable. O r==a- o__. "=
Certified Deolgn Material
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SPENT FUEL POOL COOUNG SYSTEM Revision: 5 - Effective: 5/8/98 Table 2.3.7-4 I Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built SFS conforms with the SFS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design l Section 2.3.7. Description Portion of this '
l Section 2.3.7. , 4
- 2. The piping identified in Inspection will be conducted of The ASME Code Section III l Table 2.3.7-2 as ASME Code the as-built piping as documented design r: ports exist for the as- l Section III is designed and in the ASME design reports. built piping identified in l constructed in accordance with Table 2.3.7-2 as ASME Code ASME Code Section III Section III.
requirements. j
- 3. Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.3.7 2 boundary welds will be performed the ASME Code Section III as ASME Code Section III meet in accordance with the ASME requirements are met for non-ASME Code Section III Code Section III. destructive examination of requirements. pressure boundary welds.
- 4. The piping identified in A hydrostatic test will be A report exists and concludes that
'lable 2.3.7-2 as ASME Code performed on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code Section III to of the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.3.7 2 as ASME Code pressur:. Section III conform with the requirements of the ASME Code Section III.
- 5. The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in' Tatie 2.3.7-1 can withstand equipment identified in Table 2.3.7-1 is located on the seismic design basis loads Table 2.3.7-1 is located on the Nuclear Island.
without loss of safety functions. Nuclear Island. l l ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes l for the existence of a report that the as-built equipment l verifying that the as-installed including anchorage is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or ana!yzed conditions. or analyzed conditions. 2.3.7-4 [ WBSilflghouSB o:\lTAACSVev5\it020307.wpt:1 b-050198 I
Certified Design Material SPENT FUEL POOL COOLING SYSTEM
- Revision: 5 "
<N E Effective: 5/8/98 Table 2.3.7-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 6.a) The Class IE componen t Testing will be performed on the A simulated test signal exists identified in Table 2.3.7-1 are SFS by providing a simulated test at the Class IE components powered from their respective signal in each Class IE division. identified in Table 2.3.7-1 when Class IE division. the assigned Class IE division is l provided the test signal.
)
6.b) Separation is provided See Certified Design Material, See Certified Design Material, between SFS Class lE divisions. Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. 7.a) He SFS preserves contain- See Certified Design Material, See Certified Design Material, ment integrity by isdation of the subsection 2.2.1, Containment subsection 2.2.1, Containment 1 SFS lines penetrating the System. System. I containment. 7.b) The SFS provides spent fuel i) Inspection will be performed to i) He volume of the spent fuel cooling for 7 days by boiling verify that the spent fuel pool pool and fuel transfer canal above water in the pool and providing includes a sufficient volume of the fuel and to the elevation makeup water from safety-related water. 6 feet below the operating deck is (v) sources. greater than or equal to 46,700 gallons. ii) Inspection will be performed ii) The volume of the cask I to verify the cask washdown pit washdown pit is greater than or includes sufficient volume of equal to 30,900 gallons. water. iii) A safety-related flow path iii) See item 1 of this table. exists from the cask washdown pit l to the spent fuel pocl. iv) See Certified Design Material iv) See Certified Design Material subsection 2.2.2 for inspection, subsection 2.2.2 for inspection, testing, and acceptance criteria for testing, and acceptance criteria the makeup water supply line for the makeup water supply line from the passive containment from the PCS water storage tank cooling system (PCS) water to the spent fuel pool. storage tank to the spent fuel pool. 1 [h
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LJ 2.3.7-2 W85tl!1gh00S8 o:VTAACSirev5\it020307.wpf:1 b-050198 l
Certified Design Matedal SPENT FUEL POOL COOLING SYSTEM =%
- Revision
- 5 =
l Effective: 5/8/98 _ Table 2.3.7-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 8. The SFS provides the i) Inspection will be performed i) A repon exists and nonsafety-related function of for the existence of a report that concludes that the heat transfer removing spent fuel decay heat determines the heat removal characteristic, UA, of each SFS using pumped flow through a heat capability of the SFS heat heat exchanger is greater than or exchanger, exchangers. equal to 1.48 million Btu /hr *F.
ii) Testing will be performed to ii) Each SFS pump produces at confirm that each SFS pump least 675 gpm through its heat provides flow through its heat exchanger. exchanger when taking suction from the SFP and returning flow to the SFP.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.3.7-1 can be retrievability of the safety-related in Table 2.3.7-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
- 10. Controls exist in the MCR to Testing will be performed to Controls in the MCR cause cause the pumps identified in actuate the pumps iden'afied in pumps identified in Table 2.3.7-3 Table 2.3.7-3 to perform their Table 2.3.7-3 using centrols in the to perform the listed functions.
listed functions. MCR.
- 11. Displays of the SFS Inspection will be performed for Displays of the SFS parameters parameters identified in retrievability in the MCR of the identified in Table 2.3.7-3 are Table 2.3.7-3 can be retrieved in displays identified in Table 2.3.7-3. retrieved in the MCR.
the MCR. Table 2.3.7 S Component Name Tag No. Compone.ut Location SFS Pump A SFS-MP-01A Auxiliary Building SFS Pump B SFS-MP-OlB Auxiliary Building SFS Heat Exchanger A SFS-ME-01 A Auxiliary Building SFS Heat Exchanger B SFS-ME-OlB Auxiliary Building 2.3.7-6 e{ W85tillgtl00S6 o VTAACS\rev5Vt020307.wpf;1 tt 050198
Certified Design Material SPENT FUEL POOL COOLING SYSTEM - A Revision: 5 " V Effective: 5/8/98 L T~ht-s.i - s I
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Certified Design Material SERVICE WATER SYSTEM " " /m. Revision: 5 () Effective: 5/8/98 2.3.8 Service Water System Design Description The servics water system (SWS) transfers heat from the component cooling water heat exchangers to the atmosphere. The SWS operates during normal modes of plant operation, including startup, power operation (full and partial loads), cooldown, shutdown, and refueling. The SWS is as shown in Figure 2.3.8-1 and the component locations of the SWS are as shown Table 2.3.8-3.
- 1. Tlie functional arrangement of the SWS is as described in the Design Description of this Section 2.3.8.
- 2. The SWS provides the following nonsafety-related functions:
a) 'Ihe SWS provides flow through the component cooling water system (CCS) component cooling water heat exchangers. b) The SWS cooling tower transfers heat from the SWS to the surrounding atmosphere.
- 3. Controls exist in the main control room (MCR) to cause the components identified in
(] V Table 2.3.8-1 to perform the listed function.
- 4. Displays of the parameters identified in Table 2.3.8-1 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.8-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the SWS. (D U i 2.3.8-1 W85t@Me o:VTAACSvev5Mt020308.wpf:t>050398
Certified Design Material SERVICE WATER SYSTEM Revision: 5 9i l Effective: 5/IV98 ! l Table 2.3.8-1 Equipment Name Tag No. Display Control Function Service Water Pump A (Motor) SWS-MP-01A Yes Start (Run Status) Service Water l amp B (Motor) SWS-MP-01B Yes Start (Run Status) , Service Water Cooling Towcr Fan A (Motor) SW 5-MA-01 A Yes Start (Run Status) Service Water Cooling Tower Fan B (Motor) SWS-MA-01A Yes Start (Run Status) Service Water Pump 1A Flow Sensor SWS-004A Yes - Service Water Pump IB Flow Sensor SWS-004B Yes - Service Water Pump A Discharge Valve SWS-PL-V002A Yes Open (Valve Position) Service Water Pump B Discharge Valve SWS-PL-V002B Yes Open (Valve Position) Service Water Pump A Discharge SWS-005A Yes Temperature Sensor Service Water Pump B Dischag SWS-005B Yes - Temperature Sensor Note: Dash (-) indicates not applicable. O r weS* oSe
. _ _ _ =
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Revision: 5 Effective: 5/8/98
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{ Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. He functional arrangement of Inspection of the as-built system He as-built SWS conforms with the SWS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design l
i Section 2.3.8. Description of this Section 2.3.8. ! 2.a) The SWS provides flow Testing will be performed to Each SWS pump can provide at through the CCS component confirm that the SWS can least 6200 gpm of cooling water cooling water heat exchangers. provide cooling water to the through its CCS heat exchanger. CCS heat exchangers. 2.b) The SWS cooling tower Inspection will be performed for A report exists and concludes that transfers heat from the SWS to the the existence of a report that the heat transfer rate of each surrounding atmosphere. determines the heat transfer cooling tower cell is greater than capability of each cooling tower or equal to 86.5 million Btu /hr at cell. a 80*F ambient wet bulb temperature ano a cold water temperature of 88.5'F. 3
/ 3. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to
(]_,/ cause the components identified in components in Table 2.3.8-1 cause the components listed in 3 Table 2.3.8-1 to perfonn the listed using controls in the MCR. Table 2.3.8-1 to perform the f function. listed functions.
- 4. Displays of the parameters Inspection will be performed for He displays identified in identified in Table 2.3.8-1 can be retrievability of parameters in the Table 2.3.8-1 can be retrieved in retrieved in the MCR. MCR. the MCR.
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Certified Design Material SERVICE WATER SYSTEM r- ~~~
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Revision: 5 Effective: 5/8/98 Table 2.3.8-3 Component Name Tag No. Component Location Service Water Pump A SWS-MP-01 A Turbine Building or yard Service Water Pump B SWS-MP-01B Turbine Building or yard ( Service Water Cooling Tower SWS-ME-01 Yard O 1
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Certified Design Material CONTAINMENT HY'DROGEN CONTROL SYSTEM
~ Revision: 5 l
V) Effective: 5/8/98 2.3.9 Containment Hydrogen Control System He containment hydrogen control system (VLS) limits hydrogen gas concentration in containment during accidents. The VLS has catalytic hydrogen recombiners (VLS-MY-E01A, VLS-MY-E01B, VLS-MY-E02 and VLS-MY-E03) that are located inside containment. He VLS has hydrogen igniters located as shown on Table 2.3.9-2.
- 1. The seismic Category I equipment identified in Table 2.3.9-1 can withstand seismic design basis loads without loss of safety function.
- 2. a) The equipment identified in Table 2.3.9-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, dming, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class IE components identified in Table 2.3.9-1 are powered from their respective Class 1E division. c) Separation is provided between VLS Class IE divisions, and between Class IE divisions and Cs non-Class IE cable. U
- 3. The components identified in Table 2.3.9-2 are powered from their respective non-Class IE power group.
- 4. The VLS provides the following safety-related functions:
a) The VLS provides hydrogen monitors for indication of the containment hydrogen concentration. b) The VLS provides passive autocatalytic recombiner (PAR) devices for control of the containment hydrogen concentration during and following a design basis accident.
- 5. The VLS provides the nonsafety-related function to control the containment hydrogen concentration for beyond design basis accidents.
- 6. Safety-related displays identified in Table 2.3.9-1 can be retrieved in the MCR.
- 7. a) Controls exist in the MCR to cause the components identified in Table 2.3.9-2 to perform the listed function.
l b) The components identified in Table 2.3.9-2 perform the listed function after receiving a l [ manual signal from the diverse actuation system (DAS). ! Os j U 2.3.9-1 [ W85tingt100S8 oNTAACSVev5WN0309.wpub-oS0398 l
l Certified Design Material l CONTAINMENT HYDROGEN CONTROL SYSTEM a Revision "'
' ~
Effective: 5/8/98 i*.et Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.9-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the VLS. O l Wed@ne o:vTAAcsvevsyt020309.wpf:1 50 9
Certified Dee:gn Material CONTAINMENT HYDROGEN CONTROL SYSTEM i =F 73 Revision: 5 = 2 (Y Effective: 5/8/98 i . e
=
1 Table 2.3.91 ASME Class 1El Code Qual for Safety-Section Seismic Harsh Related Equipment Name Tag No. IU Cat. I Envir. Display Catalytic Hydrogen Recombiner A VLS-MY-E01 A No Yes NA/Yes - l Catalytic Hydrogen Recombiner B VLS-MY-E01B No Yes NA/Yes - IRWST Catalytic Hydrogen VLS-MY-E02 No Yes NA/Yes - Recombiner f CVS Compartment Catalytic VLS-MY-E03 No Yes NA/Yes - Hydrogen Recombiner Containment Hydrogen Monitor VLS-001 No Yes Yes/Yes Yes Containment Hydrogen Monitor VLS-002 No Yes Yes/Yes Yes Containment Hydrogen Monitor VLS-003 No Yes Yes/Yes Yes Note: Dash (-) indicates not applicabic. O k i j l l I i l l 1 i i h '\ I 2.3.9-3 I T Westirighouse o:VTAACSVev5Mt020309.wptit@0398 i l l 1
l Certified Design Material l CONTAINMENT HYDROGEN CONTROL SYSTEM Revision: 5 Effective: 5/8/98 _ Table 2.3.9-2 Power Tag Group Room Equipment Name Number Function Number Location No. Hydrogen Igniter 01 VLS-EH-01 Energize 1 Tunnel connection loop compartments 11204 Hydrogen Igniter 02 VLS-EH-02 Energize 2 Tunnel connection loop compartments 11204 Hydrogen Igniter 03 VLS-EH-03 Energize 1 Tunnel connection loop compartments 11204 Hydrogen Igniter 04 VLS-EH-04 Energize 2 Tunnel connection loop compartmems 11204 Hydrogen Igniter 05 VLS EH-05 Energize 1 Loop compartment 02 11402 Hydrogen Igniter 06 VLS-EH-06 Energize 2 Loop compartment 02 11502 Hydrogen Igniter 07 VLS-EH-07 Energize 2 Loop compartment 02 11402 Hydrogen Igniter 08 VLS-EH-08 Energize 1 Loop compartment 02 .11502 Hydrogen Igniter 09 VLS-EH-09 Energize 1 In-containment refueling water storage !!305 tank (IRWST) dydrogen Igniter 10 VLS-EH-10 Energize 2 IRWST 11305 Hydrogen Igniter 11 VLS-EH-11 Energize 2 Loop compartment 01 1140I Hydrogen Igniter 12 VLS-EH-12 Energize 1 Loop compartment 01 11501 Hydrogen Igniter 13 VLS-EH-13 Energize 1 Loop compartment 01 11401 Hydrogen Igniter 14 VLS-EH-14 Energize 2 Loop compartment 01 11501 l Hydrogen Igniter 15 VLS-EH-15 Energize 2 IRWST 11305 Hydrogen Igniter 16 VLS-EH-16 Energize 1 IRWST 11305 Hydrogen Igniter 17 VLS-EH-17 Energize 2 Northeast valve room 11207 i Hydrogen Igniter 18 VLS-EH-18 Energize 1 Northeast accumulator room 11207 Hydrogen Igniter 19 VLS-EH-19 Energize 2 East valve room 11208 Hydrogen Igniter 20 VLS-EH-20 Energize 2 Southeast accumulator room 11206 Hydrogen Igniter 21 VLS-EH-21 Energize 1 Sortheast valve room i1206 Hydrogen Igniter 22 VLS-EH-22 Energize 1 Lower compartment area (core makeup 11400 tank [CMT] and valve area) Hydrogen Igniter 23 VLS-EH-23 Energize 2 Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 24 VLS-EH-24 Energize 2 Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 25 VLS-EH-25 Energize 2 Lower compartment area (CMT and i1400 valve area) Hydrogen Igniter 26 VLS-EH-26 Energize 2 Lower compartment area (CMT and 11400 valve area) O 2.3.9-4 W W8Silligt10USB o:VTAACS\rev5\it020309.wpf:1 b-050398
Certified Design Material CONTAINMENT HYDROGEN CONTROL SYSTEM i ~ Revision: 5
- i (o)
LJ Effective: 5/8/98
=
Table 2.3.9-2 (cont.) Power . Tag Group Room Equipment Name Number Function Number Location No. < Hydrogen Igniter 27 VLS-EH-27 Energize 1 Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 28 VLS-EH-28 Energize 1 Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 29 VLS-EH-29 Energize ! Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 30 VLS-EH-30 Energize 2 Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 31 VLS-EH-31 Energize i Lower compartment area (CMT and 11400 valve ar'ea) l Hydrogen Igniter 32 VLS-EH-32 Energize 1 Lower compartment area (CMT and 11400 valve area) Hydrogen Igniter 33 VLS-EH-33 Energize 2 North CVS equipment room 11209 Hydrogen Igniter 34 VLS EH-34 Energize 1 North CVS equipment room 11209 Hydrogen Igniter 35 VLS-EH-35 Energize 1 IRWST 11305 ('] V Hydrogen Igniter 36 VLS-EH-36 Energize 2 IRWST 11305 Hydrogen Igniter 37 VLS-EH-37 Energize 1 IRWST 11305 Hydrogen Igniter 38 VLS-EH-38 Energize 2 IRWST 11305 Hydrogen Igniter 39 VLS-EH-39 Energize 1 Upper compartment lower region i1500 Hydrogen Igniter 40 VLS-EH-40 Energize 2 Upper compartment lower region 11500 Hydrogen Igniter 41 VLS-EH-41 Energize 2 Upper compartment lower region 11500 Hydrogen Igniter 42 VLS-EH-42 Energize 1 Upper compartment lower region 11500 Hydrogen Igniter 43 VLS-EH-43 Energize 1 Upper compartment lower region 11500 Hydrogen Igniter 44 VLS-EH-44 Energize 1 Upper compartment lower region 11500 Hydrogen Igniter 45 VLS-EH-45 Energize 2 Upper compartment lower region 11500 Hydrogen Igniter 46 VLS-EH-46 Energize 2 Upper compartment lower region 11500 Hydrogen Igniter 47 VLS-EH-47 Energize 1 Upper compartment lower region 11500 Hydrogen Igniter 48 VLS-EH-48 Energize 2 Upper compartment lower region 11500 Hydrogen Igniter 49 VLS-EH-49 Energize 1 Pressurizer compartment 11503 Hydrogen Igniter 50 VLS-EH-50 Energize 2 Pressurizer compartment i1503 Hydrogen Igniter 51 VLS EH-51 Energize 1 Upper compartment mid-region 11500 Hydrogen Igniter 52 VLS-EH-52 Energize 2 Upper compartment mid-region 11500 m Hydrogen Igniter 53 VLS-EH-53 Energize 2 Upper compartment mid-region 11500
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Certified Design Material CONTAINMENT HYDROGEN CONTROL SYSTEM F I "~" Revision: 5 Effective: 5/8/98 . Table 2.3.9 2 (cont.) Power Tag Group Room Equipment Name Number Function Number Location No. Hydrogen Igniter 54 VLS-EH 54 Energize 1 Upper compartment mid-region 11500 Hydrogen Igniter 55 VLS-EH-55 Energize 1 Refueling cavity 11504 Hydrogen Igniter 56 VLS-EH-56 Energize 2 Refueling cavity 115M Hydrogen Igniter 57 VLS-EH-57 Energize 2 Refueling cavity 1I5M Hydrogen Igniter 58 VLS-EH-58 Energize 1 Refueling cavity 11504 Hydrogen Igniter 59 VLS-EH-59 Energize 2 Pressurizer compartment 11503 Hydrogen Igniter 60 VLS-EH-60 Energize 1 Pressurizer compartment 11503 Hydrogen Igniter 61 VLS-EH-61 Energize i Upper compartment-upper region 11500 Hydrogen Ignit:r 62 VLS-EH-62 Energize 2 Upper compartment-upper region 11500 Hydrogen Igniter 63 VLS-EH-63 Energize 1 Upper compartment-upper region 11500 Hydrogen Igniter 64 VLS-EH-64 Energize 2 Upper compartment-upper region 11500 0 O w = = a uSe o _ .v _ . =
Certified Design Material CONTAINMENT HYDROGEN CONTROL SYSTEM T It Revision: 5 = f (n) Effective: 5/8/98 1 .. Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The seismic Category I i) Inspection will be performed i) The seismic Category I equipment identified in to verify that the seismic equipment identified in Table 2.3.9-1 can withstand Category I equipment identified Table 2.3.91 is located on the seismic design basis loads in Table 2.3.9-1 is located on the Nuclear Island.
without loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage bounded by the tested or analyzed is seismically bounded by the conditions. p i 1 tested or analyzed conditions. V 2.a) The equipment identified in Type tests, analyses, or a A report exists and concludes that Table 2.3.9-1 as being qualified combination of type tests and the equipment identified in for a harsh environment can analyses will be performed on Table 2.3.9-1 as being qualified for withstand the environmental equipment located in a harsh a harsh environment can withstand conditions that would exist environment. the environmental conditions that before, during, and following a would exist before, during, and design basis accident without loss following a design basis accident of safety function for the time without loss of safety function for required to perform the safety the time required to perform the function, safety function. 2.b) The Class IE components Testing will be performed by A simulated test signal exists at identified in Table 2.3.9-1 are providing a simulated test signal the Class IE equipment identified powered from their respective in each Class IE division. in Table 2.3.9-1 when the assigned Class IE division. Class IE division is provided the test signal. 2.c) Separation is provided See Certified Design Material, See Certified Design Material, between VLS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. J and non-Class IE cable. l i 1 1 A (v I j 2.3.9-7 W85tilighouse oAITAACS\rev5Vt020309.wpf:1 b-050398 t 1 1 1 l I
Certified Design Material CONTAINMENT HYDROGEN CONTROL SYSTEM m;_ Revision: 5 -
=i Effective: 5/8/98 i*.
Table 2.3.9 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 3. He components identified in Testing will be performed by A simulated test signal exists at Table 2.3.9-2 are powered from providing a simulated test signal the equipment identified in their respective non-Class IE in each noa-Class IE power Table 2.3.9-2 when the assigned power group. group. non-Class IE power group is provided the test signal.
4.a) The VLS provides hydrogen Inspection for the existence of Three hydrogen monitors powered monitors for indication of the three Class IE hydrogen by a Class IE power source are containment hydrogen monitors inside containment will provided inside containment. concentration. be perfonned. 4.b) ne VLS provides PAR i) Inspection for the existence i) Two PAR devices are provided devices for control of the of two PAR devices inside inside containment within the containment hydrogen containment will be performed. upper compartment between concentration during and elevations 150 and 175 ft and with following a design basis accident. PAR centerline greater than 10 ft ii) Type tests, analyses, or a from the containment shell. combination of type tests and analyses will be performed on ii) A report exists and concludes the PARS. that the PAR depletion rate for each installed PAR is greater than or equal to I scfm of hydrogen at a prevailing concentration of 3 volume-percent thr a test conducted at atmospb7ic pressure
+2 psi and an ambient temperature of 120.
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i Certified Design Material
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CONTAINMENT HYDROGEN CONTROL SYSTEM = i p) t s._ Revision: 5 Effective: 5/8/98 E
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Table 2.3.9-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 5. He VLS provides the i) Inspection for the number of i) At least 64 hydrogen igniters nonsafety-related function to igniters will be performed. are provided inside containment at control the containment hydrogen the locations specified in concentration for beyond design Table 2.3.9-2.
basis accidents. ii) Operability testing will be ii) ne surface temperature of the performed on the igniters. igniter exceeds 1700*F. iii) An inspection of the as-built iii) The minimum distance containment internal structures between the primary openings will be performed. through the ceilings of the passive core cooling system valve / accumulator rooms (11206,11207) and the containment shell is at least 19 feet. Primary openings are those that constitute 98% of the opening area. Other openings f7 through the ceilings of these rooms Q must be r.t least 3 feet from the containment shell. iv) An inspection will be iv) The discharge from each of performed of the as-built IRWST these IRWST vents is oriented vents that are located in the roof generally away from the of the IRWST along the side of containment shell. the IRWST next to the containment shell.
- 6. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.3.9-1 can be retrievability of the safety-related Table 2.3.9-1 can be retrieved in retrieved in the MCR. displays in the MCR. the MCR.
7.a) Controls exist in the MCR Testing will be performed on the Controls in the MCR operate to to cause the components igniters using the controls in the energize the igniters. identified in Table 2.3.9-2 to MCR. perform the listed function. 7.b) The components identified Testing will be performed on the The igniters energize after l in Table 2.3.9-2 perform the igniters using the DAS controls. receiving a signal from DAS. ! listed function after receiving manual a signal from DAS. 1 1
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Certified Design Material l l l LIQUID RADWASTE SYSTEM fr l n Revision: 5 -
- l Effective: 5/8/98 1 e 2.3.10 Liquid Radwaste System Design Description The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater.
The WLS has components which receive and store radioactive or potentially radioactive liquid waste. Rese are the reactor coolant drain tank, the containment sump, the effluent holdup tanks and the waste holdup tanks. The WLS components store and process the waste during normal operation and during anticipated operational occurrences. Monitoring of the liquid waste is performed prior to discharge. The WLS is as shown in Figure 2.3.10-1 and the component locations of the WLS are as shown in Table 2.3.10-5.
- 1. The functional arrangement of the WLS is as described in the Design Description of this Section 2.3.10.
- 2. a) The components identified in Table 2.3.10-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
( n. V) b) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.3-10-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3-10-2 as ASME Code Section III meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.3.10-1 as ASME Code Section III retain their pressure l boundary integrity at their design pressure.
b) The piping identified in Table 2.3.10-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.3.10-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.3.10-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its l functional capability. l ln lv 2.3.101 T Westinghouse o:VTAACSvev5\it020310.wpf;1t> 050498 l 1 i
Certified Design Material
=
LIQUID RADWASTE SYSTEM j Revision: 5
- s l
I Effective: 5/8/98 i
- 6. The WLS provides the following safety-related functions:
a) The WLS preserves containment integrity by isolation of the WLS lines penetrating the containment. b) Check valves in drain lines to the containment sump limit cross flooding of compartments.
- 7. The WLS provides the nonsafety-related functions of:
a) Detecting leaks within containment to the containment sump. b) Controlling releases of radioactive materials in liquid effluents.
- 8. Controls exist in the main control room (MCR) to cause the remotely operated valve identified in Table 2.3.10-3 to perform its active function.
- 9. The check valves identified in Table 2.3.10-1 perform an active safety-related function to change position as indicated in the table.
I 10. Displays of the parameters identified in Table 2.3.10-3 can be retrieved in the MCR. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.104 specifies the inspections, tests, analyses, and associated acceptance criteria for the WLS. O w ** - .____.=
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Certified Design Material LIQUID RADWASTE SYSTEM == Flevision: 5 = Effective: 5/8/98 Table 2.3.10 2 Line Name Line No. ASME Section III Functional Capability Required WLS Drain from PXS LO62 Yes Yes Contpartment A WLS Drain from PXS LO63 Yes Yes Compartment B , WLS Drain from CVS LO61 Yes Yes Compartment Table 2.3.10-3 Equipment Name Tag No. Display Control Function l WLS Effluent Discharge Iso!ation WLS-PL-V223 - Close l Valve i Reactor Coolant Drain Tank WLS-002 Yes - l Level O 2.3.10-4 [ W85tingh0USB c:VTAACSVev5WO20310.wpf:1 t> 050698
Certified Design Material i l l l LIQUID RADWASTE SYSTEM ===
, Revision: 5 F E (qw) Effective: 5/8/98 i e l
Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria l j Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- l. The functional arrangement of Inspection of the as-built system The as-built WLS conforms with !
the WLS is as described in the will be performed. the functional arrangement as { Design Description of this described in the Design Section 2.3.10. Description of this Section 2.3.10. 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.3.10-1 as ASME Code the as-built components as design report exists for the as Section III are designed and documented in th- ASME design built components identified in constructed in accordance with reports. Table 2.3.10-1 as ASME Code ASME Code Section III Section III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.3.10-2 as ASME Code the as-built piping as documented design repons exist for the as-Section III is designed and in the ASME design reports. built piping identified in constructed in accordance with Table 2.3.10-2 as ASME Code ASME Code Section III Section III. requt'rements.
/m 3.a) Pressure boundary welds in V) components identified in Inspection of the as-built pressure boundary welds will be A report exists and concludes that the ASME Code Section III Table 2.3.10-1 as ASME Code performed in accordance with the requirements are met for non-Section III meet ASME Code ASME Code Section III. destructive examination of Section III requirements. pressure boundary welds.
3.b) Pressure boundary welds in Inspection of the as-built pressure "A report exists and concludes that piping identified in Table 2.3.10-2 boundary welds will be the ASME Code Section III I as ASME Code Section III meet performed in accordance with the requirements are met for non-ASME Code Section III ASME Code Section III. destructive examination of requirements. pressure boundary welds. 4.a) The components identified in A hydrostatic test will be A report exists and concludes that Table 2.3.10-1 as ASME Code performed on the components the results of the hydrostatic test Section III retain their pressure required by the ASME Code of the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.3.10-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. l 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.3.10-2 as ASME Code performed on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code Section III to of the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.3.10-2 as ASME Code pressure. Section III conform with the req.tirements of the ASME Code a Section III.
\v) 2.3.10-5 3 W8Stiligh0tlSe o:VTAACSVev5Mt020310.wpti tr050498
Certified Design Material LIQUID RADWASTE SYSTEM s.-"~ E ~ Revision: 5 Effective: 5/8/98 ! l Table 2.3.10-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.3.10-1 can .vithstand equipment identified in Table 2.3.10-1 is located on the seismic design basis loads Table 2.3.10-1 is located on the Nuclear Island. without loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be perfonned iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or analyzed conditions. or analyzed conditions. 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that in Table 2.3.10-2 for which the existence of a report venfying each of the as-built lines functional capability is required is that the as-built piping meets the identified in Table 2.3.10-2 for designed to withstand combined requirements for functional which functional capability is normal and seismic design basis capability, required meets the requirements loads without a loss of its for functional capability. functional capability. 6.a) The WLS preserves See Certified Design Material, See Certified Design Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the WLS lines penetrating the System. System. containment. 6.b) Check valves in drain lines Refer to item 9 in this table. Refer to item 9 in this table. to the containment sump limit cross flooding of compartments. O 2.3.10-6 [ W8Sfiflghouse o:VTAACSVev5\it020310.wpt i b-050498
Certified Design Material LIQUID RADWASTE SYSTEM ~ /7 Revision: 5 - {j Effective: 5/8/98 _ Table 2.3.10-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.a) The WLS provides the i) Inspection will be performed i) Nonsafety-related displays of nonsafety-related function of for retrievability of the displays of WLS containment sump level detecting leaks within containment sump level channels channels WLS-034 and WLS-035 containment to the containment WLS-034 and WLS-035 in the can be retrieved in the MCR. sump. MCR. ii) Testing will be performed by ii) A repon exists and concludes adding water to the sump and that sump level channels observing display of sump level. WLS-034 and WLS-035 can detect a change of 1.75 0.1 inches. 7.b) The WLS provides the Tests will be performed to A simulated high radiation signal nonsafety-related function of confirm that a simulated high causes the discharge control controlling releases of radioactive radiation signal from the discharge isolation valve materials in liquid effluents. radiation monitor, WLS-229, WLS-PL-V223 to close. causes the discharge isolation valve WLS-PL-V223 to close. < g
) 8. Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate to cause the remotely operated valve on the remotely operated valve cause the remotely operated valve identified in Table 2.3.10-3 to listed in Table 2.3.10-3 using to perform its active function.
perform its active function. controls in the MCR.
- 9. The check valves identified Exercise testing of the check Each check valve changes in Table 2.3.10-1 perform an valves with active safety functions position as indicated on active safety-related function to identified in Table 2.3.10-1 will Table 2.3.10-1.
change position as indicated in be performed under pre-the table. operational test pressure, temperature and flow conditions. I 10. Displays of the parameters Inspection will be performed for Displays identified in I identified in Table 2.3.10-3 can retrievability of the displays Table 2.3.10-3 can be retrieved in i be retrieved in the MCR. identified in Table 2.3.10-3 in the the MCR. I MCR. r~"N
\
l 2.3.10-7 [ W8Stillgtl0ilS8 o:VTAACSirev5WO20310.wpf:1b 050698
Certified Design Material l l LIQUID RADWASTE SYSTEM f=J I Revision: 5 5 Effective: 5/8/98 i . t Table 2.3.10 5 Component Name Tag No. Component Location l WLS Reactor Coolant Drain Tank WLS-MT-01 Containment WLS-MT-02 Containment WLS Containment Sump WLS Degasifier Column WLS-MV-01 Auxiliary Building WLS Effluent Holdup Tanks WLS-MT-05A Auxiliary Building WLS-MT-05B WLS Waste IIoldup Tanks WLS-MT-06A Auxiliary Building WLS-MT-06B WLS Waste Pre-Filter WLS-MV-06 Auxiliary Building WLS Ion Exchangers WLS-MV-03 Auxiliary Building WLS-MV-04A WLS-MV-OtB WLS-MV-04C WLS Waste After-Filter WLS-MV-07 Auxiliary Building WLS Monitor Tanks WLS-MT-07A Auxiliary Building WLS-MT-07B WLS-MT-07C O i M8 o:VTAACSVev5Vt020310.wpf:1 9 1 ( l
Csrtified Design Mat:ri:1 LIQUID RADWASTE SYSTEM " =* Revision: 5 T Effective: 5/8/98
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ls )s is (* [F l* 3 E E Figure 2.3.101 Liquid Radwaste System [ W85tingh00S8 2.3.10-9 oNTAACSvev5Vt020310.wpt1b-050498
Csrtified Dezign Mit:rit! GASEOUS RADWASTE SYSTEM * .:::: Revision: 5 ~ i Effective: 5C38 ,e s 2.3.11 Gaseous Radwaste System Design Description The gaseot., radwaste system (WGS) receives, processes, and discharges the radioactive waste gases I received within acceptable off-site release limits dudng normal modes of plant operation including " l power generation, shutdown and refueling. The WGS is as shown in Figure 2.3.11-1 and the component locations of the WGS are as shown in Table 2.3.11-3. 1. He functional arrangement of the WGS is as desexibed in the Design Description of this Section 2.3.11.
- 2. The seismic Category I equipment identified in Table 2.3.11-1 can withstand seismic design basis loads without loss of its structural integrity function.
- 3. The WGS provides the nonsafety-related functions of:
a) Processing radioactive gases prior to discharge. b) Controlling the releases of radioactive materials in gaseous effluents. I c) The WGS is purged with nitrogen on indication of high oxygen levels in the system. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.11-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the WGS. E8MM8 c:VTAACSVev5Vt020311.wpf;1 " 198
Certified Design Material GASEOUS RADWASTE SYSTEM -=
=
j Revision: 5 = Effective: 5/8/98 i e i Table 2.3.11 1 Seismic Equipment Name Tag No. Category 1 WGS Activated Carbon Delay Bed A WGS-MV-02A Yes WGS Activated Carbon Delay Bed B WGS-MV-02B Yes WGS Discharge Isolation Valve WGS PL-V051 No O l l l l l 1 O IND# o:VTAACSVmGit020311.wpf:1 9
Certified Design Material GASEOUS RADWASTE SYSTEM PT.:: (] Revision: 5 "
=i (a/ Effective: 5/8/98 1 , t Table 2.3.112 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-buik system The as-built WGS conforms with the WGS is as described in the will be performed, the functional arrangement as Design Description of this described in the Design Section 2.3.11. Description of this Section 2.3.11.
- 2. The seismic Category I i) Inspection will be performed i) The seismic Category I equipment identified in to verify that the seismic equipment identified in Table 2.3.11-1 can withstand Category I equipment ide.ntified Table 2.3.11-1 is located on the seismic design basis loads without in Table 2.3.11-1 is located on Nuclear Island.
loss of its structural integrity the Nuclear Island. function. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic ) equipment will be performed. design basis loads without loss of I its safety function. iii) Inspection will be performed iii) A report exists and concludes [ j for the existence of a report that the as-installed equipment V verifying that the as-installed including anchorage is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or analyzed conditions. or analyzed conditions. 3.a) The WGS provides the Inspection will be performed to A report exists and concludes that I nonsafety-related function of verify the contained volume of the contained 5 olume in each of processing radioactive gases prior each of the activated carbon delay the activated carbon delay beds, to discharge. beds, WGS-MV02A and WGS-MV02A and WGS-MV02B. WGS-MV02B, is at least 80 ft3. 3.b) The WGS provides the Tests will be performed to A simulated high radiation signal nonsafety-related function of confirm that the presence of a causes the discharge control controlling the releases of simulated high radiation signal isolation valve WGS-PL-V051 to radioactive materials in gaseous from the discharge radiation close. effluents. monitor, WGS-017, causes the discharge control isolation valve WGS-PL-V051 to close. v 2.3.11-3 WBStiflgh0LIS8 oNTAACSvev5Vt020311.wpf:1b 050153
l Certified Design Material GASEOUS RADWASTE SYSTEM -_ Revision: 5 = Effective: 5/8/98 1 . e e. l Table 2.3.112 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria
. Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 3.c) The WGS is purged with Tests wd} be performed to A simulated high oxygen level I nitrogen on indication of high confirm that the presence of a signal causes the nitrogen purge I oxygen levels in the system. simulated high oxygen level valve (WGS-PL-V002) to open i signal from tiie oxygen monitors and the WLS degasifier vacuum I (WGS-025A, -025B) causes pumps (WLS-MP-03A, -03B) to l the nitrogen purge valve stop.
l (WGS-PL-V002) to open and the I WLS degasifier vacuum pumps I (WLS-MP-03A, -03B) to stop. O O 2.3.11-4 [ W85tinghouse o:VTAACSVev5Vt020311.wpf:1 b-050398
Ccrtified Design Mit: rill GASEOUS RADWASTE SYSTEM Revision: 5 ;r M O Effective: 5/8/98 1 - ee E Table 2.3.113 Equipment Name Tag No. Component Location WGS Gas Cooler WGS-ME-01 Auxiliary Building WGS Moisture Separator WGS-MV-03 Auxiliary Building WGS Activated Carbon Delay Bed A WGS-MV-02A Auxiliary Building WGS Activated Carbon Delay Bed B WGS-MV-02B Auxiliary Building O O M 2.3.11 5 oNTAACSVev5Nt020311.wpf:1tH60198
Certified Design Mit:rizi GASEOUS RADWASTE SYSTEM _ y Revision: 5 Effective: 5/8/98 I PLANT VENT
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Certified Design Material SOLID RADWASTE SYSTEM T~ ~"'i; em Revision: 5 EE Effective: 5/8/98 1 .ee 2.3.12 Solid Radwaste System Design Description he solid radwaste system (WSS) receives, collects and stores the solid radioactive wastes received i prior to their processing and packaging by mobile equipment for shipment off-site. l The component locations of the WSS are as shown in Table 2.3.12-2.
- 1. He functional arrangement of the WSS is as described in the Design Desedption of this Section 2.3.12. l
- 2. The WSS provides the nonsafety-related function of storing radioactive spent resins prior to 1 processing or shipment. I n
I i V 2.3.12-1 MIMM o:VTAACSVev5Nt020312.wpf:1 b-050198 i
Certified Design Material SOLID RADWASTE SYSTEM i Revision: 5 Effective: 5/8/98 Table 2.3.12-1 Inspections, Tests, Analyses, and Acceptance Criteria Design Conun:tment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built WSS is as described the WSS is as described in the will be performed. in the Design Description of this Design Description of this Section 2.3.12.
Section 2.3.12. .. I
- 2. The WSS provides the Inspection will be performed to A report exists and concludes thtt nonsafety-related function of verify that the volume of each of {
the volume of each of the spent i storing radioactive solids prior to the spent resin tanks, resin tanks, WSS-MV01A and processing or shipment. WSS MV01A and WSS-MV01E, is at least 250 ft3. j WSS-MV01B, is at 1 ast 250 ft3. l l l l Table 2.3.12 2 l Component Name Tag No. Component Location WSS Spent Resin Tank A WSS-MV-01A Auxiliary Building WSS Spent Resin Tank B WSS-MV-OlB Auxiliary Building l 1 l \ i O 2.3.12-2 W8Silfigh00S8 o:VTAACSVev5Vt020312.wpf:1 t>050198 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~
[1;i l Certified Design Materhl
._ PRIMARY SAMPt. LNG GYSTEM
(~N Revision: 5 () Effectivo: 5/Q8_ l 2.3.13 Primary Sampilng System The primary sampling system collects samples of fluids in the reactor coolant system (RCS) and the containment atmosphere daring normal operations and following an accident. I The PSS is as shown in Figum 2.3.13-1. The PSS Grab Sampling Unit (PSS-MS-01)is lccated in the L i Auxiliary Building. l' l. The functional arrangement of the PSS is as described in the Design Description of this Section 2.3.13.
- 2. The components identified in Table 2.3.13-1 as ASME Code Section m are designed and constructed 1 in accordance with ASME Code Secdon m requirements. l
- 3. Pressure boundary welds in componerats identified in Table 2.3 13-1 as ASME Code Section E meet ASME Code Section m requirements.
- 4. The components identified in Table 2.3.13-1 as ASME Code Section m retain their pressure boundary integrity at their design pressure.
- 5. The seismic Category I equipment identified in Table 2.3.13-1 can withstand seismic design basis loads without loss of safety function.
Q l h 6. a) The Class IE equipmein identified in Table 2.3.13-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of their safety functien, for the time required to perform the safety function. b) The Class IE components identified in Table 2.3.13-1 are powered from their respective Class iI' division. c) Separation is provided between PSS Class IE divisions, and between Class 1E divisions and non-Class 1E divisions.
)
- 7. The PSS provides the safety-related function of preserving containment integrity by isolation of the PSS lines penetrating the containment.
l
- 8. The PSS provides the nonsafety-related function of providing the capability of obtaining post-accident ;
reactor coolant and containment atmosphere samples. i
- 9. Safety-related displays identified in Table 2.3.13-1 can be retrieved in the MCR.
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Certified Design Material PRIMARY SAMPLING SYSTEM _
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- Revision: 5 -
Effective: 5/8/98 l l
- 10. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.3.13-1 to perform active functions.
b) The valves identified in Table 2.3.13-1 as having protection and safety monitoring system (PMS) control perform an active function after receiving a signal from the PMS.
- 11. a) The check valves identified in Table 2.3.13-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.3.13-1 assume the indicated loss of motive power position.
- 12. Controls exist in the MCR to cause the valves identified in Table 2.3.13-2 to perform the listed function.
Inspections, Tests, Analyses,and Acceptance Criteria Table 2.3.13-3 specifies the inspections, tests, analyses, and associated acceptance criteria for the PSS. O O w =- _____ =
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Certified Da-Ign M:.terial PRIMARY SAMPt.ING SYSTEM Revision: 5 Effective: 5/8/98 Table 2.3.13-2 Equipment Name Tag No. Co,itrol Function Reactor Coolant System (RCS) PSS-PI V001A Transfer Open/ Transfer Closed Sample Isolation Valve A RCS Sample Isolation Valve B PSS-PL-V001B Transfer Oper/Fransfer Closed l O O Wesurighouse 2.3.13-4 o:VTAACSvev5Vt020313.wp6:1b-050198
Certified Design Material PRIMARY SAMPLING SYSTEM - A Revision: 5 ' *
) Effective: 5/8/98 Table 2.3.13-3 Inspections, Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built PSS is as described in the PSS is as described in the will be performed. the Design Description of this Design Description of this Section 2.3.13.
Section 2.3.13.
- 2. The components identified in Inspection will be conducted of The ASME Code Section III design Table 2.3.13-1 as ASME Code the as-built components as reports exist for the as-built SectionIll are designed and documented in the ASME design components identified in constructed in accordance with reports. Table 2.3.13-1 as ASME C ,de ASME Code SectionIII Section III.
requirements.
- 3. Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that components identified in boundary welds will be performed the ASME Code Section III Table 2.3.13-1 as ASME Code in accordance with the ASME requirements are met for non-SectionIII meet ASME Code Code Section III. destructive examination of pressure Section III requirements. boundary welds.
- 4. The components identified in
!p) Table 2.3.13-1 as ASME Code A hydrostatic test will be performed on the components A report exists and concludes that the results of the hydrostatic test of 'd Section III retain their pressure required by the ASME Code the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.3.13-1 as ASME Code pressure, tested. Section III conform with the requirements of the ASME Code Section III.
- 5. The seismic Category I I) Inspection will be performed to I) The seismic Category I equipment equipment identified in verify that the seismic Category I identified in Table 2.3.13-1 is Table 2.3.13-1 can withstand equipment and valves identified located on the Nuclear Island.
seismic design basis loads without in Table 2.3.13-1 are located on loss ofits safety function. the Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes i combination of type tests and that the seismic Category I l analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of l { safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically l equipmentincluding anchorage is bounded by the tested or analyzed seismically bounded by the tested conditions. or analyzed conditions.
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b W65tiligt100S6 2.3.13-5 o:VTAACSvev5Mt020313.wp6:1b-050198 r L________._.___ --
Certified Design Material PRIMARY SAMPLING SYSTEM Revision: 5 Effective: 5/8/98 Table 2.3.13-3 (cont.) Inspections, Tests, Analyses,and Acceptance Criteria Design Commitment Inspections. Tests, Analyses Acceptance Cdteria 6.a) 'Ihe Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Tables 2.3.13-1 as combination of type tests and the Class IE equipment identified in being qualified for a harsh analyses will be performed on Table 2.3.13-1 as being qualified environment can withstand the Class IE equipment located in a for a harsh environment can environmental conditions that harsh environment. withstand the environmental would exist before, during, and conditions that would exist before, l following a design basis accident during, and following a dedgn basis l without loss of their safety accident without loss ofits safety function, for the time required to function for the time required to perform the safety function. perfonn the safety function. 6.b) The Class IE components Testing will be performed on the A simulated test signal exists at the identified in Table 2.3.13-1 are PSS by providing a simulated test Class IE equipment identified in i powered from their respective signal in each Class IE division. Table 2.3.13-1 when the assigned l Class IE division. Class 1E division is provided the test signal. 6.c) Separation is provided See Certified Design Material, See Certified Design Material, j between PSS Class IE divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE divisions.
- 7. The PSS provides the safety. See Certified Design Material, See Certified Design Material, related function of preserving subsection 2.2.1, Containment subsection 2.2.1, Containment containment integrity by isolation System. System.
of the PSS lines penetrating the containment.
- 8. The PSS provides the Testing will be performed to A sample is drawn from the reactor nonsafety-related function of obtain samples of the reactor coolant and the containment providing the capability of coolant and containment atmosphere.
obtaining post-accident reactor atmosphere. coolant and containment atmosphere samples.
- 9. Safety-related displays Inspection will be performed for The safety-related displays identified in Table 2.3.13-1 can be xtrievability of the safety-related identified in Table 2.3.13-1 can be retrieved in the MCR. ;iisplays in the MCR. retrieved in the MCR.
10.a) Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate to cause those remotely operated on the remotely operated valves cause those remotely operated valves identified in Table 2.3.13-1 identified in Table 2.3.13-1 using valves identified in Table 2.3.13-1 to perform active functions. the controls in the MCR. to perform active functions. O 2.3.13-6 W85ti!1gh0llSB o:VTAACSvev5Vt020313.wp6:1 b-050198 l
Certified Design Material i l PRIMARY SAMPLING SYSTEM [ '_E ()
/'-~N Flevision: 5 Effective: 5/8/98 Table 2.3.13-3 (cont.)
l Inspections Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 10.b) The valves identified in Testing will be performed on The remotely operated valves Table 2.3.13-1 as having PMS remotely operated valves listed in identified in Table 2.3.13-1 as having control perform an active function Table 2.3.13-1 using real or PMS control perform the active after receiving a signal from the simulated signals into the PMS. function identified in the table after PMS. receiving a signal from the PMS. 11.a) The check valves identified Exercise testing of the check Each check valve changes position I in Table 2.3.13-1 perform an valves with active safety functions as indicated in Table 2.3.13-1. active safety-related function to identified in Table 2.3.13-1 will change position as indicated in the be performed under ] table. preoperational test pressure, temperature and fluid flow conditions. I1.b) After loss of motive power, Testing of the installed valves Upon loss of motive power, each the remotely operated valves will be performed under the remotely operated valve identified I identified in Table 2.3.13-1 conditions ofloss of motive in Table 2.3.13-1 assumes the ) assume the indicated loss of power. indicated loss of motive power motive power position. position. V 12. Controls exist in the MCR to Testing will be performed on the Controls in the MCR cause valves cause the valves identified in components in Table 2.3.13-2 identified in Table 2.3.13-2 to Table 2.3.13-2 to perform the using controls in the MCR. perform the listed functions. listed function. f p) L 2.3.13-7 MSdflgt100S8 o:\lTAACSirev5\it020313.wp6:1 b-050198
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Certified De:Ign M;tirill DEMINERALIZED WATER TRANSFER AND STORAGE SYSTEM
~'
Revision: 5 O Effective: 5/8/98
~
2.3.14 Demineralized Water Transfer and Storage System Design Description
\
The demineralized water transfer and storage system (DWS) receives water from the demineralized water treatment system (DTS), and pmvides a reservoir of demineralized water to supply the condensate storage tank and for distribution throughout the plant. Demineralized water is processed in the DWS to remove dissolved oxygen. In addition to supplying water for makeup of systems which require pure water, the demineralized water is used to sluice spent radioactive resins from the ion .. exchange vessels in the chemical and volume control system (CVS), the spent fuel pool cooling system (SFS), and the liquid radwaste system (WLS) to the solid radwaste system (WSS). He component locations of the DWS are as shown in Table 2.3.14-3. 1. The functional arrangement of the DWS is as described in the Design Description of this Section 2.3.14. 2. He DWS provides the safety-related function of preserving containment integrity by isolation of the DWS lines penetrating the containment. 3. The DWS condensate storage tank (CST) provides the nonsafety-related function of water supply to the FWS startup feedwater pumps.
- 4. Displays of the parameters identified in Table 2.3.14-1 can be retrieved in the main control room (MCR).
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.14-2 specifies the inspections, tests, analyses, and associated acceptance criteria for tl - DWS.
- e. -
Table 2.3.14-1 Equipment Name Tag No. Display Control Function Condensate Storage Tank Water Level DWS-006 Yes - Note: Dash (-) indicates not applicabic. D W85tiligt10USB 2.3.14-1 o.vrAACSVev5Vt020314.wpf:1 b-050398
Certified Design Material DEMINERALIZED WATER TRANSFER AND STORAGE SYSTEM s Revision: 5 + Effective: 5/8/98 Table 2.3.14 2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i
- 1. The functional arrangement of Inspection of the as-built system The as-built DWS conforms with the DWS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.3.14. Description of this Section 2.3.14.
- 2. The DWS provides the safety. See Certified Material, See Certified Material, I related function of preserving subsection 2.2.1, Containment subsection 2.2.1, Containment containment integrity by isolation System. System.
of the DWS lines penetrating the containment.
- 3. He DWS CST provides the hispection of the DWS CST will ne volume of the CST is greater nonsafety-related function of water be performed. than or equal to 200,000 gallons supply to the FWS startup between the tank overflow and i feedwater tanks. the startup feedwater pumps supply connection.
- 4. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.2.14-1 can be retrievability or parameters in the Table 2.3.14-1 can be retrieved in retrieved in the MCR. MCR. the MCR.
O 2.3.14-2 W8SIllighouse oNTAACSVev5Vt020314.wpf:1 t450398
Certified Design Material DEMINERALIZED WATER TRANSFER AND STORAGE SYSTEM . - - - O Revision: 5 s ::: Effective: 5/8/98 1 . ,, Table 2.3.14-3 Component Name Tag No. Component Location Demineralized Water Storage Tank DWS-MS-01 Annex Building Degasification System Package Condensate Storage Tank DWS-MS-02 Turbine Building Degasification System Package Demineralized Water Storage Tank DWS-MT-01 Yard Condensate Storage Tank DWS-MT-02 Yard l O i i l l l O I L) M III N US8 c:VTAACSVev5Mt020314.wpt:1 0398 1 1
Certified Design Material COMPRESSED AND INSTRUMENT AIR SYSTEM =! I Revision: 5 4 I (m) Effective: 5/8/98 i.. I 2.3.15 Compressed and Instrument Air System Design Description The compressed and instmment air system (CAS) consists of three subsystems; instrument air, service 3 air, and high-pressure air. The instrument air subsystem supplies compressed air for air-operated l valves and dampers. The service air subsystem supplies compressed air at outlets throughout the plant to power air-operated tools and is used as a motive force for air-powered pumps. The service air subsystem is also utilized as a supply source for breathing air. The high-pressure air subsystem supplies air to the main control room emergency habitability system (VES), the generator breaker package, and fire fighting apparatus recharge station. The CAS is required for normal operation and startup of the plant. The component locations of the CAS are as shown in Table 2.3.15-3.
- 1. The functional arrangement of the CAS is as described in the Design Description of this Section 2.3.15.
- 2. The CAS provides the safety-related function of preserving containment integrity by isolation of the CAS lines penetrating the containment.
V) t
- 3. Displays of the parameters identified in Table 2.3.15-1 can be retrieved in the main control room (MCR).
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.15-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the CAS. Table 2.3.15-1 l Equipment Name Tag No. Display Control Function I. Instrument Air Pressure CAS-Oli Yes , Note: Dash (-) indicates not applicable. q 2.3.15-1 l T Westinghouse o:VTAACSVrSit020315.wptib-oS0398
Certified Design Material COMPRESSED AND INSTRUMENT AIR SYSTEM ;* ' * " ~ Revision: 5 -. Effective: 5/8/98 _ Table 2.3.15-2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built CAS conforms with the CAS is as described in the will be performed, the functional arrangement as Design Description of this described in the Design Section 2.3.15. Description of this Section 2.3.15.
- 2. The CAS provides the safety- See Cenified Design Material, See Cenified Design Material, related function of preserving subsection 2.2.1, Containment subsection 2.2.1, Containment containment integrity by isolation System. System.
of the CAS lines penetrating the containment.
- 3. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.3.15-1 can be retrievability of parameters in the Table 2.3.15-1 can be retrieved in retrieved in the MCR. MCR. the MCR.
O i 2.3.15-2 e! i W85till@tlS8 o:\lTAACS\rev5Vt020315.wpf:1b-050398
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Certified Design Material COMPRESSED AND INSTRUMENT AIR SYSTEM _Te"~ r~T Revision: 5 " 2
- l. ) Effective: 5/8/98 k e.
Table 2.3.15 3 Component Name Tag No. Component Location Instrument Air Compressor Package A CAS-MS-OlA Turbine Building Instrument Air Compressor Package B CAS-MS-OlB Turbine Building Instrument Air Dryer Package A CAS-MS-02A Turbine Building Instrument Air Dryer Package B CAS-MS-02B Turbine Building Service Air Compressor Package A CAS-MS-03A Turbine Building Service Air Compressor Package B CAS-MS-03B Turbine Building Service Air Dryer Package A CAS-MS-04A Turbine Building Service Air Dryer Package B CAS-MS-04B Turbine Building - 1 High Pressure Air Compressor and Filter CAS-MS-05 Turbine Building Package Instrument air Receiver A CAS-MT-01 A Turbine Building (] Instrument Air Receiver B CAS-MT-01B Turbine Building Service Air Receiver CAS-MT-02 Turbine Building l l l vb r 2.3.15-3 W8Stillgh00S8 o:vTAACSVev5Mt020315.wpt:1t>O50698
Certified Design Material POTABLL' WATER SYSTEM - - - "
,q Revision: 5 -
(g Effeciaa 3/8/98 i e J 1 2.3.16 Potable Water System j l No entry for this system. l \ i I l ) i I
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l l k 1 4 1 0 I l t i O ! 2.3.16-1 3 Westiflgh00S8 o:VTAACSVev5Vt020316.wpf:050398 i
Certified Design Material WASTE WATER SYSTEM . =_ Revision: 5 _ O
- ~
Effective: 5/8/98 2.3.17 Waste Water System No entry for this system. O O o l l 2.3.17-1 I W Westinghouse oWAACSVevWt02mumpf.05M98
Certified Design Material PLANT GAS SYSTEM _: _ Revision: 5 O Effective: 5/8/98 2.3.18 Plant Gas System i See Section 3.3 for information on the plant gas system. i O j l f 2.3.1 S1 W== Westinghouse o:\lTAACS\rev5'Jt020318.wpf:050698 l
Certified Design Material COMMUNICATION SYSTEM :=
,o Revision: 5 -
() Effective: 5/8/98 i e 2.3.19 Communication System Design Description l-ne communication system (EFS) provides intraplant communications during normal, maintenance, transient, fire, and accident conditions, including loss of offsite power.
- 1. a) The EFS has handsets, amplifiers, loudspeakers, and siren tone generators connected as a telephone /page system.
b) The EFS has sound-powered equipment connected as a system.
- 2. The EFS provides the following nonsafety-related functions:
a) he EFS telephone /page system provides intraplant, station-to-station communications and area broadcasting between the main control room (MCR) and the locations listed in Table 2.3.19-1. b) The EFS provides sound-powered communications between the MCR, the RSW, the Division A, B, C, D de equipment rooms (Rooms 12201/12203/12205/12207), the Division A, B, C, D { I&C rooms (Rooms 12301/12302/12304/12305), and the diesel generator building without extemal power.
)
j G t Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.19-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the EFS. l i l l
\
d 2.3.19-1 UhE o:\lTAACS\rev5\it020319.wpf.1 t>050398 l
Certified Design Material COMMUNICATION SYSTEM Revision: 5 Effective: 5/8/98 - Table 2.3.19-1 Communication Equipment Location Fuel Handling Area 12562 Division A, B, C, D de Equipment Rooms 12201/12203/12205/12207 Division A, B, C, D I&C Rooms 12301/12302/12304/12305 Maintenance Floor Staging Area 12351 Containment Maintenance Floor 11300 Containment Operating Deck -11500 0 O w ==== . _ _ . _ =
Certified Design M:tirirl-COMMUNICATION SYSTEM - Revision: 5 - Effective: 5/8/98 - .et Table 2.3.19-2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1.a) The EFS has handsets, Inspection of the as-built system The as-built EFS has handsets, amplifiers, loudspeakers, and will be perfonned. amplifiers, loudspeakers, and siren siren tone generators connected as tone generators connected as a a telephone /page system. telephone /page system. 1.b) Le EFS has sound-powered Inspwtion of the as-built system The as-built EFS has sound-equipment connected as a system. will be performed. powered equipment connected as a system. 2.a) He EFS telephone /page An inspection and test will be Telephone /page equipment is system provides intraplr.nt, performed on the telephone /page installed and voice transmission station-to-station communications communication equipment. and reception from the MCR are and area broadcasting between the accomplished. MCR and the locations listed in Table 2.3.19-1. 2.b) EFS provides sound- An inspection and test will be Sound-powered equipment is powered communications between performed of the sound-powered installed and voice transmission
] the MCR, the RSW, the Division A, B, C, D de equipment rooms communication equipment. and reception are accomplished.
(Rooms 12201/12203/12205/ 12207), the Division A, B, C, D I&C rooms (Rooms 12301/12302/ 12304/12305), and the diesel generator building without external power. 2.3.19-3 UIIMO oNTAACS\rev5Nt020319.wpf-1 b-050398
Certifi:d Dezign M:t: rial TURBINE BUILDING CLOSED COOLING WATER SYSTEM --
==
0 Revision: 5 Effective: 5/8/98 ig 2.3.20 Turbine Building Closed Cooling Water System No entry for this system. O O W= Westinghouse 222&1 o:VTAACS\rev5'noentry.wpf:1b6598
Certified Dezign Mztzrial SECONDARY SAMPLING SYSTEM C Z: , O Revision: 5 Effective: 5/8/98 1 1 t 23.21 Secondary Sampling System No entry for this system. O Id!UNM8 2.3.21-1 o.VTAACS\ revs % entry.wpf.1 b-050598
Certified Design M;terial CONTAINMENT LEAK RATE TEST SYSTEM mumme:= O Revision: 5 (d Effective: 5/8/98 _ 23.22 Containment Leak Rate Test System No entry. Covered in Section 2.2.1, Containment System. I O DE o:VTAACSvev5hoentry.wpf;1 A 98
4 Certified Design Material i I
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Certified Design Material DEMINERALIZED WATER TREATMENT SYSTEM _=z Revision: 5 O Effective: 5/8/98 i . E 2.3.24 Demineralized Water Treatment System No entry for this system. O O - .. 2.3.24-1 [ W85tingh0USB 0:VTAACSVev5\noentry.wpMb-050598 t
Certified Design M5erial l GRAVITY AND ROOF DRAIN COLLECTION SYSTEM = "s j e Revision: 5 - 5 Effective: 5/8/98 1 2.3.25 Gravity and Roof Drain Collection System l l No entry for this system. i O l I I O 2.3.25-1 3 W8Stingh00SB o:VTAACSVev5Voentry.wpf:1b-050398 s. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ a
( } f Certified Design Miterial
=- .
O Flevision: 5 Effective: 5/8/98 i 2.3.26 This section intentionally blanh l I
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l 1 1 l 1 { O I O 2.3.26-1 W85tingh0USB oNTAACSVev5Vx> entry.wpt1b450598
l l Certified DeIign Mat: rill l l SANITARY DRAli4 AGE SYSTEM == 4: Revision: 5 l '( Effective: 5/8/98 1 2.3.27 Sanitary Drainage System i No entry for this system. 1 I ( l I l i l l l 2.3.27-1 l W65tirighouse o:VTAACSVev5Voentry.wpf:1b-050398 l l
F Certified Design Material TURBINE ISLAND VENTS, DRAINS, AND RELIEF SYSTEM
/~ Revision: 5
) '\ Effective: 5/8/98 2.3.28 Turbine Island Vents, Drains, and Relief System No entry for this system. O l l I i y 2.3.28-1 W85tillgfl0LIS8 oNTAACSvev5\noentry.wpf:1 b-050598 l
i Certified Design Material l RADIOACTIVE WASTE DRAIN SYSTEM w Revision: 5 (]/ l Effective: 5/8/98 l 2.3.29 Radioactive Waste Drain System I I Design Description. I 1 The radioactive waste drain system (WRS) collects radioactive and potentially radioactive liquid I wastes from equipment and floor drains during normal operation, startup, shutdown, and refueling. 1 The liquid wastes are then transferred to appropriate processing and disposal systems. l l Nonradioactive wastes are collected by the waste water system (WWS). The WRS is as shown in i Figure 2.3.29-1. I I 1. The functional arrangement of the WRS is as described in the Design Description of this l Section 2.3.29. l l 2. The WRS collects liquid wastes from the equipment and floor drainage of the radioactive portions I of the auxiliary building, annex building, and radwaste building and directs these wastes to a WRS 1 sump or WLS waste holdup tanks located in the auxiliary building. l l 3. 'Ihe WRS collects chemical wastes from the auxiliary building chemical laboratory drains and the I decontamination solution drains in the annex building and directs these wastes to the chemical I waste tank of the liquid radwaste system. I v 2.3.29-1 W85tiligh00S8 o:VTAACSVev5Mt020329.wpf:1 tH)S0698
Certified Design Material RADIOACTIVE WASTE DRAIN SYSTEM .=s.; Revision: 5 - ji Effective: 5/8/98 1 . e l l Table 2.3.29-1 l Inspection, Tests, Analyses and Acceptance Criteria l l Design Commitment Inspection, Tests, Analyses Acceptance Criteria l 1. The functional arrangement Inspection of the as-built The as-build WRS conforms I of the WRS is as described in system will be performed. with the functional I the Design Description of this arrangement as described in l Section 2.3.29. the Design Description of this I Section 2.3.29. I 2. The WRS collects liquid A test is performed by pouring The water poured into these I wastes from the equipment water into the equipment and drains is collected either in the I and floor drainage of the floor drains in the radioactive auxiliary building radioactive I radioactive portions of the portions of the auxiliary drains sump or the WLS waste I auxiliary building, annex building, annex building, and holdup tanks. I building, and radwaste radwaste building. I building and directs these I wastes to a WRS sump or l WLS waste holdup tanks I located in the auxiliary I building. I 3. The WRS collects chemical A test is performed by pouring The water poured into these I wastes from the auxiliary water into the auxiliary drains is collected in the I building chemical laboratory building chemical laboratory chemical waste tank of the ! I drains and the decontamination and the decontamination liquid radwaste system. I I solution drains in the annex solution drains in the annex l building and directs these building. i l wastes to the chemical waste I tank of the liquid radwaste I system. l O 2.3.29-2 W85tiligh0USB c:VTAACSVev5Vt020329.wpf;1 b-050698
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Certified Design Material MAIN AND STARTUP FEEDWATER SYSTEM .-i_
~ / Revision: 5 .
Q] Effective: 5/8/98 i. M) 2.4.1 Main and Startup Feedwater System 1 See Section 2.2.4 for information on the main feedwater system. Design Description 1he startup feedwater system supplies feedwater to the steam generators during plant startup, hot standby and shutdown conditions, and during transients in the event of main feedwater system unavailability, l 1. The functional arrangement of the startup feedwater system is as described in the Design i l Description of this Section 2.4.1.
)
i
- 2. The FWS provides the following nonsafety-related functions:
The FWS provides startup feedwater flow from the condensate storage tank (CST) to the steam generator system (SGS) for heat removal from the RCS.
- 3. Controls exist in the main control room (MCR) to cause the components identified in Table 2.4.1-1 to perform the listed function. l
(']
'v
- 4. Displays of the parameters identified in Table 2.4.1-1 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.4.12 specifies the inspections, tests, analyses, and associated acceptance criteria for the FWS. l l l O U 2.4.1-1 DIDE8 oNTAACSVev5Vt02o401.wpf:1 b-oS0698
Cartified Design Mit:rlil MAIN AND STARTUP FEEDWATER SYSTEM -t Revision: 5 = 3 Effective: 5/8/98 .
.ee Table 2.4.11 Equipment Name Tag No. Display Control Function Startup Feedwater Pump A (Motor) FWS-MP-03A Yes Start (Run Status)
Startup Feedwater Pump B (Motor) FWS-MP-03B Yes Start (Run Status) Startup Feedwater Pump A Isolation Valve FWS-PL-V013A Yes Open (Valve Position) Startup Feedwater Pump B Isolation Valve FWS-PleV013B Yes Open (Valve Position) s O O 2.4.1-2 [ WBSil!1gh0US8 o:VTAACSVev5M020401.wpf;1 b-050398
Certified Design Material l MAIN AND STARTUP FEEDWATER SYSTEM mu fm Revision: 5 m = (v) Effective: 5/8/98 i.,ei Table 2.4.12 I Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. he functional arrangement of Inspection of the as-built system The as-built startup feedwater the startup feedwater system is as will be perfonned. systert conforms with the described in the Design functional arrangement as Description of this Section 2.4.1.
described in the Design , Description of this Section 2.4.1.
- 2. The FWS provides startup Testing will be performed to Each FWS startup feedwater feedwater flow from the CST to confirm that each of the startup pump provides a flow rate greater the SGS for heat removal from feedwater pumps can provide than or equal to 190 gpm to each the RCS. water from the CST to both steam steam generator system at a I generators. steam generator secondary side I pressure of at least 1003 psia.
- 3. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to cause the components identified components in Table 2.4.1-1 using cause the components listed in in Table 2.4.1 1 to petform the controls in the MCR. Table 2.4.1-1 to perform the listed function. listed functions.
- 4. Displays of the parameters Inspection will be performed for he displays identified in
[N (,) identified in Table 2.4.1-1 can be retrievability of parameters in the Table 2.4.1-1 can be retrieved in retrieved in the MCR. MCR. the MCR.
=
Table 2.4.13 Component Name Tag No. Component Location Startup Feedwater Pump A FWS-MP-03A Turbine Building Startup Feedwater Pump B FWS-MP-03B Turbine Building o v 2.4.1-3 [ W8Silflgt100S8 c:VTAACSVev5\it020401.wpf;1 t>-050398 l
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i l Certified Design Material MAIN TtJRBINE SYSTEM i O Reviskyn: 5 E i () Effective: 5/8/98 ; 2.4.2 Main Turbine System t Design Description l t i The main turbine system (MTS) is designed for electric power production consistent with the 4 l capabuity of the reactor and the reactor coolant system. The component locations of the MTS are as shown in Tabis 2.4.2-2.
- 1. The functionaj arrangement of the MfS is as described in the Design Description of 'his Section 2.4.2.
I 2. a) Controls exist in the MCR to trip the main turbine-generator. ! l 1 i l b) The main tuttine-generator trips after receiving a signal frorn the PMS. I l 1 I c) The main turbine-generator trips after receiving a signal from the DAS.
)
l Inspections, Tests, Analyses, and Acceptance Criteria 1 1 i Table 2.4.2-1 specifies the inspections, tasts, analyses, and associated acceptame crivaia for the MTS. ! C' N)% - TcMe 2.4.21 s
-inspections Tests, Analyses,and Acceptance Criteria n_ , _
l Dedgn Commitment Inspcetions, Test, Arnlyses Acceptance Criteria
- 1. The func:icnal arrangement of Inspection of the as-built syst m The as-built MTS conforms with 4 the MTS is as described in the will be performed. the compoir,er.ts functional l Design Description of this arrangement as described in tne {
Section 2.4.2. Design Description of this ) Section 2.4.2. l l 2 a) Controls exist in the MCR Testing will be performed on the Controls in the MCR operate to l 1 to trip the main turtsne-generator. aain turbine-generator using trip the main turbine-generator. { l controls in die MCR. l l 2.b) The main turbine-generator Testing will be performed using The main turbine-generator trips' I trips after receiving a signal from real or simulated signals into the afv.r receiving a signal from the l I the PMS. PMS. PMS. 1 1 2.c) The main turbine-generator Testing will be performed using The main turbine-generator trips l l l trips after receiving a signal from real or simulated signals into the after receiving a signal from the 1 l l the DAS. DAS. DAS. i ___ < 4
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Certified Doolgn Matcrial MAIN 'iURBINE SYSTET* EM. ! Rwision: 5 = 1 Effective: 5/8/98 k e I Table 2A.2-2 4 - Comr)nent Name Tag No. Component Location l HP Turbine MTS-MG-01 Turbine Building l LP Turbine A MTS.MG-02A Turbine Building l T.P Yurbine B MTS 'MG-02B Turbine Building l Gh,nd Scare Condenser GSS-ME-01 Turbine Building I Gland Condelser Yapor Exhauster I A GSS-MA-01 A Turbine Building 3 Gland Condenser Vapor Exhauster IB _ GCS-MA-01B Turbine Building l Mec.{anical OverspecJ TripJ,kvice - Turbine Building I , Electrice overspeed Trip Device -- Turbine Building O EhiamGluMAE s 2.4.2-2 I N D748 o VTAACSVr5VtC20402.wpt'050196
Certified De:Ign M;terial
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MAIN STEAM SYSTEM =- Revision: 5 O Eifective: 5/8/98 2.4.3 Main Steam System No entry for this system. I 2.4.3-1 D Ill N US8 o:VTAACSVev5\it020403.wpf;050398
Certified Design Material STEAM GENERATOR BLOWDOWN SYSTEM ; 7; (' Revision: 5 Effective: 5/8/98
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2.4.4 Steam Generr.ior Blowdown System No entry. Containment isolation function covered in Sections 2.2.1, Containment System and 2.2.4, Steam Generator System. No entry. Steam generator isolation function covered in Section 2.2.4, Steam Generator System. l I l c l i i O 2.4.4-1 W85tiligh00S8 c:\lTAACSirev4\noentry.wpf;1 b4)S0598 l
Certified Design M;terial CONDENSER AIR REMOVAL SYSTEM ,_=: .
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Q Effective: 5/8,98 1 . t 2.4.5 Condenser Air Removal System No entry. Covered in Section 3.5, Radiation Monitoring. (Note: Monitor is TDS-RE001.) i l l 1 l l O 2.4.5-1 W850@US8 oNTAACSVev4Voentr/.wpf:1 t>O50598
l Certified Design Material CONDENSATE SYSTEM r=? /3 Revision: 5 ! C) Effective: 5/8/98 2.4.6 Condensate System Design Description The condensate system (CDS) provides feedwater at the required temperature, pressure, and flow rate to the deaerator. Condensate is pumped from the main condenser hotwell by the condensate pumps I and passes through the low-pressure feedwater heaters to the deaerator, ne circulating water system , I (CWS) removes heat from tne condenser. I The CDS operates during plant startup and power operations (full and part loads). The component locations of the CDS are as shown in Table 2.4.6-3.
- 1. The functional arrangement of the CDS is as described in the Design Description of this )
Section 2.4.6.
- 2. Displays of the parameters identified in Table 2.4.6-1 can be retrieved in the main control room (MCR).
Inspections, Tests, Analyses, and Acceptance Criteria [L Table 2.4.6-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the CDS. Table 2.4.61 Equipment Name Tag No. Display Condenser Backpressure CDS-056A Yes Condenser Backpressure CDS-056B Yes Table 2.4.6-2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. He functional arrangement of Inspection of the as-built system The as-built CDS conforms with I the CDS is as described in the will be perfonned. the functional arrangement as Design Description of this described in the Design Section 2.4.6. Description of Section 2.4.6.
- 2. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.4.6-1 can be retrievability of the parameters Table 2.4.6-1 can be retrieved in retrieved in the MCR. in the MCR. the MCR.
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Certified Design Material
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CONDENSATE SYSTEM Revision: 5 Effective: 5/8/98 l l Table 2.4.6-3 Component Name Tag No. Component Location Feedwater Heater I A CDS-ME-01 A Turbine Building Feedwater Heater IB CDS-ME-OlB Turbine Building Feedwater Heater 2A CDS-ME-02A Turbine Building Feedwater Heater 2B CDS-ME-02B Turbine Building Feedwater Heater 3 CDS-ME-03 Turbine Building Feedwater Heater 4 CDS-ME-04 Turbine Building Deaerator Feedwater Heater and Storage Tank CDS-ME-05 Turbine Building Main Condenser Shell A CDS-ME-06A Turbine Building Main Condenser Shell B CDS-ME-06B Turbine Building Condensate Pump A CDS-MP-01 A Turbine Building Condensate Pump B CDS-MP-OlB Turbine Building Condensate Pump C CDS-MP-01C Turbine Building
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Certified Design Materi:1 CIRCULATING WATER SYSTEM p-7; ,O Revision: 5 Effective: 5/8/98 i et EE i 2.4.7 This section intentionally blank. { O 2.4.7-1 T 'i'stinghouse oNTAACShev4Woentry.wpf:1b 050198
i Certified Design Materi:1 1 AUXILIARY STEAM SUPPLY SYSTEM ;=: - l ( Revision: 5 = = ( Effective: 5/8/98 1 .ee 2.4.8 Auxiliary Steam Supply System No entry for this system. J O (J l l l l 1 L) 2.4.8-1 [ W85tingh00S8 o:VBACSvev4Vantry.wpf:1b-050598
Certified De2ign Material CONDENSER TUBE CLEANING SYSTEM ~ ~ - + (~ Revision: 5 - i \ Effective: 5/8/98 2.4.9 Condenser Tube Cleaning System No entry for this system. O O l 2.4.9-1 Westinghouse o:VTAACSvev4W eentry.wpf:1 b-050598 i
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Certified De:Ign Materill TURBINE ISLAND CHEMICAL FEED SYSTEM y-t; T Revision: 5 (V
- I Effective: 5/8/98 -
.s I 2.4.10 Turbine Island Chemical Feed System No entry for this system, l
1 Oa i I I 2.4.101 Westingh00S8 o:VTAACSvev4Voontry.wpf:1 b-050598
i Certified Design Material CONDENSATE POLISHING SYSTEM ' Revision: 5 N ? (Q j Effective: 5/8/98 1 ,e 2.4.11 Condensate Polishing System No entry for this system. 5 l I l 1 l l O 2.4.11-1 [ W65tiligh0US0 oNTAACS\rev4Voentry.wpf;1 b-050598 i
Csrtified Datign Matssirl GLAND SEAL SYSTEM m :m: Revision: 5 , 2:
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Effective: 5/8/98 _ 2.4.12 Gland Seal System No entry. Covered in Section 2.4.2, Main Turbine System. O l W 2.4.12-1 m Westinghouse o:\lTAACS\rev4hoentry.wpf. l b 050598
Certified Design Matsris! GENERATOR HYDROGEN AND CO2 SYSTEM _ =- Revision: 5 O Effective: 5/8/98 2.4.13 Generator Hydrogen and CO2System No entry for this system. i O O [ Westi.':ghouse a:yTAACSVev4Voentry.wpf:* 98
Certified Design Material HEATER DRAIN SYSTEM - l l O Revision: 5 Effective: 5/8/98 _ 2.4.14 Heater Drain System No entry for this system. O O [ W85tingh00S8 2.4.14-1 o:VTAACSVev4hoentry.wpf:1 t>O50598
1 Certified Design Material l HYDROGEN SEAL OIL SYSTEM m '"~ ' ,(~ Revision: 5 r ~Et Effective: 5/8/98 l
- 2.4.15 Hydrogen Seal Oil System l
l No entry for this system. I l i 4 1 l O l l l l l O 2A.15-1 T Westinghouse WAACSvev4Vmentry.wpt1W98 1
Certified Design Material /~ MAIN TURBINE AND GENERATOR LUBE OIL SYSTEM Revision: 5
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y ()T Effective: 5/8/98 2.4.16 Main Turbine and Generator Lebe Oil System No entry for this system. i O o U 2A.1s.1 T Westinghouse oNTAACSVev4Voentry.Mtib-oS0598
Certified Design Materlat DIVERSE ACTUATION SYSTEM Revision: 5
!q v/ Effective: 5/8/98 2.5.1 Diverse Actuation System Design Description The diverse actuation system (DAS) initiates reactor trip, actuatas selected functions, and provides plant information to the operator.
The component locations of the DAS are as shown in Table 2.5.1-5.
- 1. The functional arrangement of the DAS is es described in the Design Description of this Section 2.5.1.
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- 2. The DAS provides the following nonsafety-related functions- I l
a) The DAS provides an automatic reactor trip on low wide-range steam generator water level or 'I on low pressurizer water level separate from the PMS. b) ne DAS provides automatic actuation of selected functions, as identified in Table 2.5.1-1, separate from the PMS. ; 1 c) The DAS provides manual initiation of reactor trip and selected functiorr,, as identified in ! O V Table 2.5.12, separate from the PMS. These manual initiation functions are implemented in a manner that bypass the control room multiplexer and the signal processing equipment of the I DAS. d) The DAS provides main control room (MCR) displays of selected plant parameters, as identified in Table 2.5.1-3, separate from the PMS.
- 3. The DAS has the following features:
a) De signal processing hardware of the DAS uses input modules, output modules, and microprocessor boards that are different than those used in the PMS. b) The display hardware of the DAS uses a different display device than that used in the PMS. c) Software used in the DAS uses an operating system and a programming language that are different than those used in the PMS. d) The DAS has electrical surge withstand capability (SWC), and can withstand the . electromagnetic interference (EMI), radio frequency (RFI), and electrostrtie discharge (ESD) l conditions that exist in the plant, e) The sensors identified on Table 2.5.1-3 are used for DAS input. 2.5.11 i D US8 c:VTAACSVev5\it020501.wpf:1 tWO398 f I I
Certified Design Material DIVERSE ACTUATION SYSTEM ~ " ~ " Revision: 5 - Effective: 5/8/98 i e f) The DAS is powered by non-Class IE uninterruptible power supplies that are independent and separate from the power supplies which power the PMS. g) The DAS signal processing cabinets are provided with the capability for channel testing without actuating the controlled components. b) The DAS equipment can withstand the room ambient temperature and humidity conditions that exist a the plant locations in which the DAS equipment is instalied.
- 4. The DAS hardware and software is developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages.
a) Design requirements phase b) System definition phase c) Hardware and software development phase d) System test phase e) Installation phase The planned design process also provides for the use of commercial off-the-sh-lf hardware and software. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.5.1-4 specifies the inspections, tests, analyses, and associated acceptance criterie for the DAS. l l l O 2.5.12 l [ W85tiflgf10USB oNTAACS\revC\lt020501.wpf:1 b-050398 1 i
Certified Design Material DIVERSE ACTUATION SYSTEM ;r-Z Revision: 5 ' ii (3 k Effective: 5/8/98 (w.J) Table 2.5.11 Functions AutomaticMiy Actuated by the DAS
- 1. Turbine Trip on Low Wide-range Steam Generator Water Level or Low Pressurizer Water Level
- 2. Passive Residual Heat Removal (PRHR) Actuation and in-containment Refueling Water Storage Tank (IRWST) Gutter Isolation on Low Wide-range Steam Generator Water Level or on High Hot leg Temperature
- 3. Core Makeup Tank (CMT) Actuation and Trip All Reactor Coolant Pumps on Low Pressurizer Water Level
- 4. Isolation of Selected Containment Penetrations and Initiation of Passive Containment Cooling System (PCS) on High Containment Temperature Table 2.5.12 Functions Manually Actuated by the DAS i i
- 1. Reactor and Turbine Trip l rN
) 2. PRHR Actaation and IRWST Gutter Isolation
- 3. CMT Actuation an.1 Trip All Reactor Coolant Pumps 1
- 4. First-stage Automatic Depressurization System (ADS) Valve Actuation !
- 5. Second-suge ADS Valve Actuation
- 6. Third-stage ADS Valve Actuation
- 7. Fourth-stage ADS Valve Actuation
- 8. PCS Actuation
- 9. Isolation of Selected Containment Penetrations
- 10. Containment Hydrogen Ignitor Actuation
- 11. IRWSTInjection Actuation j 12. Containment Recirculation Actuation
- 13. Actuate IRWST Drain to Containment r5 2.5.13 oNTAACSvev5Vt020501.wpf:1 tW50398 WBSdfl$100Se i-
Certified Design Material DIVERSE ACTUATION SYSTEM J=6 = Revision: 5 - Effective: 5/8/98 1 . e Table 2.5.1-3 DAS Sensors and Displays Equipment Name Tag Number Reactor Coolant System (RCS) Hot Leg Temperature RCS-300A i l RCS Hot Leg Temperature RCS-300B l l Steam Generator 1 Wide-range Level SGS-044 '* Steam Generator 1 Wide-range Level SGS-045 l Steam Generator 2 Wide-range Level SGS-046 j Steam Generator 2 Wide-range Level SGS-047 Pressurizer Water Level RCS-305A P4essurizer Water Level RCS-305B Containment Temperature VCS-053A Containment Temperature VCS-053B Core Exit Temperature IIS-006 Core Exit Temperature IIS-011 Core Exit Temperature IIS-028 Core Exit Tempe}}