ML20216B521
| ML20216B521 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 04/06/1998 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20216B508 | List: |
| References | |
| GW-GL-030, GW-GL-030-R04, GW-GL-30, GW-GL-30-R4, NUDOCS 9804130492 | |
| Download: ML20216B521 (550) | |
Text
{{#Wiki_filter:figli o Simplified Passive Advanced Light Water Reactor Plant Program AP600 CERTIFIED DESIGN MATERIAL Prepared for U.S. Department of Energy San Francisco Operations Office DE-AC03-90SF18495 i Revision 4 i April 6,1998
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AP600 DOCUrviENT COVER SHEET AP600 CENTRAL FILE USE ONLY: TDC: IDS: 1 S Form 58202G(5/94) RFS#: RFS ITEM #: j i ASSIGNED T Q
\/ APbO0 DOCUMENT NO. REVISION NO.
GW-GL-030 4 Page 1 of 1 l WORK BREAKDOWN #: 3.2.5 I ALTERNATE DOCUMENT NUMBER: ( DESIGN AGENT ORGANIZATION: l TITLE: AP600 Certified Design Material 1 DCP #/REV, INCORPORATED IN THIS DOCUMENT ATTACHMENTS: REVISION: CALCULATION / ANALYSIS
REFERENCE:
l ELECTRONIC FILENAME ELECTRONIC FILE FORMAT ELECTRONIC FILE DESCRIPTION Wordperfect (C) WESTINGHOUSE ELECTRIC COMPANY 1998 ; i WESTINGHOUSE PROPRIETARY CLASS 2 l This document contains information propnetary to Westinghouse Electne Company; it is submitted in confidence and is to be used solely for the ' purpose for which it is furnished and retumed upon request. The document and such information is not to be reproduced, transmitted, d or used otherwise in whole or in part without prior wntten authorcation of Westinghouse Electne Company, Energy Systems Business Unit, subject to the legends contained hereof. ! VESTINGHOUSE PROPRIETARY CLASS 2C The document is the property of and contains Propnetary Information owned by Westinghouse Electric Company and/or its subcontractors anl ' supplers. It is transmitted to you in confidence and trust, and you agree to treat this document in stnct accordance with the terms and condit of the agreement under which it was provided to you. X WESTINGHOUSE CLASS 3 (NON PROPRIETARY) COMPLETE 1 IF WORK PERFORMED UNDER DESIGN CERTIFICATION OR COMPLETE 2 IF WORK UNDER FOAKE. 1 DOE DESIGN CERTIFICATION PROGRAM / GOVERNMENT LIMITED RIGHTS STATEMENT [See page 2] Copyright statement A license is reserved to the U.S. Govemment under contract DE-ACO3-90SF18495. X DOE CONTRACT DELIVERABLES (DELIVERED DATA) j Subject to speerhed exceptions, disclosure of this data is restricted until September 30,1995 or Design Cert &ation under DOE contract DE-ACO3-90SF18495, whichever is later. EPRI CONFIDENTIAL: NOTICE: 1X 2 3 4 5 CATEGORY: AlB_C_D_E_ r_ 2 ARC FOAKE P 10 GRAM / ARC LIMITED RIGHTS STATEMENT (See page 21
~""~ Copynght statement. A license is reserved to the U.S. Govemment under contract DE-FCO2-NE34267 and subcontrac ARC CONTRACT DELIVERABLES (CONTRACT DATA)
Subject to specifed exceptions, disclosure of this data is ristncted under ARC Subcontract ARC-93-3 SC-001. ORIGINATOR blGNATURE/DAT E Eugene J. Piplica , f APPHOVAL DATE 5[9f APbQQ RE5PON51BLE MANAGER 5tG ATURE' f Brian A.McIntyre 0 [
' Approval of the responsibie manager signifes that document is complete, all requirgpfftvews are complete, tibetfbniche is released for use.
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AP600 DOCUMENT COVER SHEET Page2 Form 58202G(s/94) LIMITED RIGHTS STATEMENTS DOE GOVERNMENT LIMITED RIGHTS STATEM7NT (A) These data are submitted with hmeted nghts under govemment contract No. DE-AC03-90SF18495. These data rnay be reproduced and used by the govemment with the express kmrtaten that they will not, without wntten permsson of the contractor, be used for purposes of manufacturer nor dadosed outside the govemment; except that the govemment may desdose these data outsde the govemment for the following pumoses, if any, provided that the govemment makes such dadosure subject to prohibiton against further use and dsclosure: (1) This "Propnetary Data" may be disclosed for evaluaten purposes under the restnctons above. ) (11) The *Propnetary Data" may be disclosed to the Electnc Power Research Institute (EPRI), electnc utility representatives and their direct consultants, exduding d. rect commercial competitors, and the DOE Natonal Laboratones under the prohibit ons and restnctions above. (B) This notice shall be marked on any reproduction of these data, in whole of in part. ARC LIMITED RIGHTS STATEMENT: This propnetary data, fumished under Subcontract Number ARC-g3 3-SC-001 with ARC may be duplicated and used by the govemment and ARC, subject to the hmatations of Article H-17.F. of that subcontract, with the express hmitatens that the propnetary data may not be dsclosed outside the govemment or ARC, or ARC's Class 1 & 3 members at EPR! or be used for purposes of manufacture without pnor permsson of the Subcontractor, except that further dsclosure or use may be made solely for the following purposes: This propnetary data may be dsdosed to other than commercial competitors of Subcontractor for eva!uation purposes of this subcontract under the restnction that the propnetary data be retained in confdence and not be further dsdosed, and subject to the terms of a nondsclosure agreement between the Subcontractor and that organizaton, exduding DOE and its contractors. DEFINITIONS CONTRACTIDELIVERED DATA b Consists of documents (e g. specifications, drawings, reports) which are generated under the DOE or ARC Contracts which contain no background proprietary data. EPRI CONFIDENTIALITY / OBLIGATIONNOTICES NOTICE 1: The data in this document a subject to no confdentiality obhgations. NOTICE 2: The data in this document is propnetary and confdential to Westinghouse Electnc Company and/or its Contractors. It is forwarded to recipient under an obhgation of Confdena and Trust for hmited purposes only. Any use, dsclosure to unauthorized persons, or copying of this document or parts thereof is prohibited except as agreed to in advance by the Electric Power Research institute (EPRI) and Westinghouse Electne Company. Recipient of ths data has a duty to inquire of EPRI and/or Westinghouse ss to the uses of the information contained herein that are permitted. NOTICE 3: The data in the document is propietary and confdentalto Westinghouse Electric Company and/or its Contractors. It is forwarded to recspient under an obhgaton of Confdence and Trust for use only in evaluation tasks specifically authorized by the Electric Power Research Institute (EPRI). Any use, disdosure to untuthonzed persons, or copying this document or parts thereof is prohibited except as agreed to in advance by EPRI and Westinghouse Electnc Company. Recipient of the data has a duty to inquire of EPRI and/or Westinghouse as to the usm of the informaton contained herein that are permitted. The document and any copies or excerpts thereof that may have been generated are tc se retumed to Westinghouse, directly or through EPRI, when requested to do so. NOTICE 4: The dats in ths document is propnetary and conf 4 ental to Westinghouse Electne Company and/or its Contractors. It is being revealed in confidence and trust only to Ernployees of EPRI and to mrtain contractors of EPRI for hmited eval';ation tasks authonzed by EPRI. Any use, disclosure to unauthonzed persons, or copying of this document or parts thereofis prohibited. This Document and any copies or 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 propnetary and confdential to Westinghouse Electnc Company and/or its Contractors. Access to this data is given in Confdena and Trust only at Westinghouse facihtes for hmited evaluaton tasks assigned by EPRI. Any use, dsdosure to unauthonzed persons, or copying of this document or parts thereof is prohibited. Neither ths document nor any excerpts therefrom are to be removed from Westinghouse facihtres. EPRI CONFIDENTIALITY / OBLIGATION CATEGORIES CATEGORY "A" & (See Delivered Data) Conssts of CONTRACTOR Foreground Data that is contained in an issued reported. CATEGORY "B" e (See Delivered Data) Consists of t.;ONTRACTOR Foreground Data that is not contained in an issued report, exmpt for computer programs. CATEGORY "C" & Consists of CONTRACTOR Background Data except for computer programs. CATEGORY "D" & Conssts of computer programs deveoped in the course of performing the Work. CATEGORY "E" & Conssts of computer programs developed pnor to the Effective Date or after the Effe@ve Date but outsde the scope of the Work. CATEGORY "F" O Consists of adminstratue plans and administrative reports, O APSGC. COVER Doc
1 O Certified Design Material Revision 4 Change Page Instructions Please remove all sections currently in your Certified Design Material volume and replace with the attached revised sections. Retain and reinsert the tabs. O i O instruc.r4.wpf
Certified Design Material TABLE OF CONTENTS '== A Revision: 4
- E h Effective: 4/6/98 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 < l.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 1 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 4 2.2.1 Containment System 2.2.1-1 l 2.2.2 Passive Containment Cooling System 2.2.2-1 2.2.3 Passive Core Cooling System 2.2.3-1 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 l 2.3.5 Mechanical Handling System 2.3.5-1 2.3.6 Nonnal Residual Heat Removal System 2.3.6-1 2.3.7 Spent Fuel Cooling System 2.3.7-1 l 2.3.8 Service Water System 2.3.8-1 l 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 2.2.12 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 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
,e3 2.3.21 Secondary Sampline System 2.3.21-1 3 Westinghouse onpaoonAAesvev4vmw.wpub.o40
Certified Design Material TABLE OF CONTENTS ==~ = Revision: 4 Effective: 4/6/98 ! I 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 2.3.24 Demineralized Water Treatment System 2.3.24-1 2.3.25 This section intentionally blank 2.3.25-1 2.3.26 This section intentionally blank 2.3.26-1 2.3.27 This section intentionally blank 2.3 f3-1 2.3.28 Turbine Island Vents. Drains. and Relief System 2.3. 6-1 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. 2.4.3 Main Steam System 2.4..,- 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 Circulatine Water System 2.4.7-1 2.4.8 Auxiliary Steam Suptily System 2.4.8-1 74.9 Condenser Tube Cleaninn 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 Hydrocen and CO System 2.4.13-1 2 2.4.14 Heater Drain System 2.4.14-1 2.4.15 Hydrocen 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 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 2.5.8 This section intentionally blank 2.5.8-1 2.5.9 Seismic Monitorine System 2.5.9-1 2.5.10 Main Turbine Control and Diam,9stic 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 rm -e ,____:
f 1 Certified Design Material TABLE OF CONTENTS = r3 Revision: 4 = ltj Effective: 4/6/98 _ . l I TABLE OF CONTENTS (cont.) 1 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 2.6.7 St,ecial Process Heat Tracine System ___ 2.6.7-1 2.6.8 This 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 This section int ntionally blank 2.6.11-1 2.6.12 Excitation and Voltage Reculation 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 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 2.7.7-1 [)3
\. 2.7.8 Radwaste Buildine 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 2.7.11 Hot Water Heatine System 2.7.11-1 3.0 NON-SYSTEM BASED DESIGN DESCRIPTIONS AND ITAAC 3.1 Emergency Response Facilities 3.1-1 3.2 Human Factors Engineering 3.2 1 l 3.3 Buildings 3.3-1 l 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
- Underlined sections - title only, no entry for Design Certification.
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Certified Design Material TABLE OF CONTENTS xc (3 Revision: 4 = Ei () Effective: 4/6/98 1 . ,e LIST OF FIGURES Figure Title Page 2.1.2-1 Reactor Coolant System 2.1.2-30 2.1.3-1 Reactor Upper Intemals Rod Guide Arrangement 2.1.3-11 2.1.3-2 Rod Cluster Control and Drive Rod Arrangement 2.1.3-12 2.1.3-3 Reactor Vessel Arrangement 2.1.3-13 2.2.1-1 Containment System 2.2.1-15 2.2.2-1 Passive Containment Cooling System 2.2.2-?5 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 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 J 2.3.13-1 Primary Sampling System 2.3.13-8 2.4.1-1 ]
;V') 2.5.2-1 Main and Startup Feedwater System Protection and Safety Monitoring System 2.4.1-4 2.5.2-19 2.6.1-1 Main ac Power System 2.6.1-11 2.6.2-1 Non-Class IE de and Uninterruptible Power Supply System 2.6.2-4
- 2.6.3-1 Class IE de and Unin% aptible Power Supply System
' 2.6.3-16 2.7.1-1 Nuclear Island Noaracioactive Ventilation System 2.7.1-11 2.7.2-1 Central Chilled Water System 2.7.2-5
- 2.7.3-1 Annex / Auxiliary Building Nonradioactive Ventilation System 2.7.3-5 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) 3.2 11 3.3-1 Section A-A with Building Levels 3.3-33 3.3-2 Section B-B with Building Levels 3.3-35 3.3-3 NI Plan View Level 1 3.3-37 3.3-4 NI Plan View Level 2 3.3-39 3.3-5 NI Plan View Level 2.1 3.7-41 3.3-6 NI Plan View Level 3 3.3-43 3.3-7 N1 Plan View Level 4 3.3-45 3.3-8 NI Plan View Level 5 3.3-47 3.3-9 NI Plan View Level 6 3.3-49 3.3 10 NI Plan View Level 7 3.3-51 3.3-11 Annex Building Plan View Level 1 3.3-53 3.3-12 Annex Building Plan View Level 2 3.3-55 3.3-13 Annex Building Plan View Level 3 3.3-57 3.3-14 Nuclear Island Structures Dimension at Elevation Level 1 3.3-59 b
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Certified Decign Material TABLE OF CONTENTS = Revision: 4
- Effective: 4/6/98 LIST OF FIGURES (cont.) )
Figure Title Page 3.3-15 Legend 3.3-61 5.0-1 Horizontal Design Response Spectra Safe Shutdown Eanhquake 5.0-4 5.0-2 Venical Design Response Spectra Safe Shutdown Eanhquake 5.0-5 O O 3 Westinghouse o:wpsowTAAesvev4stntmtr.wpfso40 s
Certified Design Material l
~
INTRODUCTION ==
/ Revision: 4 Q] Effective: 4/6/98 1 l
1.0 Introduction 1.1 Definitions 1 The following definitions apply to tenus used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC). , l 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 structures, systems, or components. i As-built means the physical properties of a structure, system, or component following the completion cf its installation or construction activities at its final location at the plant site. j Cable means an electrical conductor with or without insulation, or a combination of insulated electrical conductors. Design Commitment means that ponion of the design description that is verified by ITAAC. l l Design Description means that portion of the design that is certified. I Division (for electrical systems or electrical equipment) is the designation applied to a pren safety-related system or set of components that is physically, electrically, and functionally independent from other redundant sets of components. , i l Functional Arrangement means the physical arrangement of structures, systems, and components to i provide the service for which the structure or system is intended, and which is described in the design 1 description. ' I Functional Capability (of a line) means the line maintains the ability to transfer fluid through the line i i 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 based on visual observation or physical examination that compare the structure, system, or component l condition to one or more design commitments. Examples include walkdowns, configuration checks, l measurements of dimensions, or nondestructive examinations. Inspect for Retrievability of a display means to visually observe that the specified information (N appears on a monitor when summoned by the operator. l 1.0-1 Westirighouse o:WTAACSvev4Vt0101wpf:040398 t_
Certified Design Material INTRODUCTION 7-Revision: 4 == Effective: 4/6/98 _ L, is the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J. I Nominal means a dimension or size used to designate a name whereby such dimension or size may i 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 I function, for the time required to perform the safety function. Equipment identified in the Design i Description as being Qualified for Harsh Environment includes the: 1 I a. equipment itself I b. sensors, switches and lubricants that are an integral part of the equipment I c. electricai components connected to the equipment (wiring, cabling and terminations) i I Items b and c are Qualified for Harsh Environment only when they are necessary to support operation I of the equipment to meet its safety-related function listed in the Design Description table and to the i 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 suberitical 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 remain 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 transducer, 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 conditions. Test means the actuation, operation, or establishment of specified conditions to evaluate the perfonnance or integrity of as-built structures, 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 structures, systems, or components. UA of a heat exchanger means the product of the heat transfer coefficient and the surface area. O W65tiflgh00S8 o:\ap600VTAACSVev4\it0101.wpf 9 i
Certified Design Material INTRODUCTION c (~T Revision: 4 ' 5
'Q Effective: 4M/98 1.2 General Provisions The fonowing general provisions are applicable to the design descriptions and associated ITAAC.
Treatment of Individual items I i The 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 or accompanying figures. If an inspections, tests, or analyses (ITA) requirement does not specify the temperature or other conditions under which a test must be run, then the test conditions are not constrained. When the term " operate," " operates," or " operation" is used with respect to an item discussed in the ) acceptance critena, it refers & the actuation and running of the item. When the term " exist," " exists," ' 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 (] LJ The ITAACs are provided in tables with the following three-column format: l Design Inspections, Acceptance Commitment Tests, Analyses Criteria Each design commitment in the left-hand column of the ITAAC tables has an associated ITA requirement specified in the middle column of the tables. The identification of a separate ITA entry for each design commitment shall not be construed to l 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 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 by 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 performed 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 pan of the activities that are required to be performed under 10 CFR Pan 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. m 1.0-3 [ WBSti!Eh0USB o$ap600VTAACSVev4Vt0101.wpf:040398
Certified DesEn Material INTRODUCTION p~ Revision: 4 = Effective: 4/6/98 Discussion of Matten 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 upon off-normal conditions). Such discussions shall not be constmed 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 In many but not all cases, the design descriptions in Section 2 include one or more figures. The figures may represent a functional diagram, general structural representation, or another general illustration. For instrumentation and control (I&C) systems, figures may also represent aspects of the relevant logic of the system or pan tf the system. Unless specified explicitly, the figures are not indicative of the scale, location, dimeneons, shape, or spatial relationships of as-built structures, 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 thennal power for the AP600 certified design is 1933 megawatts thermal (MWt). l l O W = Westinghouse o:\ap600\lT AACSirev4\it0101.wpf.o40398
Certified Design Material INTRODUCTION - a (qj
, Revision: 4 Effective: 4/6/98 E
t 1.3 Figure Legend The conventions used in this section are for figures described in the design description. He figure legend is provided for information and is not part of the Certified Design Material. VALVES Volve C)<] Check Volve M._ Relief Volve $I l 3 1 (V VALVE OPERATORS l Operator Of Unspecified Type Motor Operator h Solenoid Operator Pneumatic / Hydraulic Operator h Pneumatic Operator f Squib Volve C
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Certified Design Material INTRODUCTION - - - -' ' Revision: 4 Effective: 4/6/98 _ WECHANICAl. EQUIPMENT l Centrifugal Purnp
]
l Purnp Type Not Specifed Tonk Centrifugal Fan h Axial Fon X Heat Exchanger Vent
]
Orain F D Pipe Cop
]
Blind flange ll 1.0-6 E8N D E8 c:\ap600VTAACSVev4\it0101.wpf:040398
Certified Dezign Material INTRODUCTION = - ( Revision: 4 = - ( Effective: 4M/98 DAMPERS Gravity Or Wonually Operated Domper Remotely Operated Damper ELECIRICAL EQUIPWENT , l Battery @ Circuit Breaker n Disconnect Switch / isolation I Transformer
- 0 Heater lWl l
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Certified Design Material INTRODUCTION m" - Revision: 4 == Effective: 4Xd98 - WISCELLANEOUS A component that is part of the Component Name i system functional arrangement shown Component Tog No. ' on the figure and is included ,ni the design commitments for the system. A component that is part of the Component Namel system functional arrangement shown -- on the figure. L_ Component Tag No.J _ A system or component of another system [System or Component Name]_,_ 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 .iot part of the system functional --g EM ONYM arrangement shown on the figure. ASME CODE CLASS 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 AsME CODE SECDON M CMSSl L2 NI
- x N :
NOTES:
- 1. The header, "ASME Code Section 1:1 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.
Indicates Non-ASME Code Section 111 0 1.0-8 WB We o:\ap600\lTAACS\rev4ilt0101.wpt040398
Certified Design Material INTRODUCTION = = Revision: 4 b] Effective: 4/6/98 1.4 List of Acronyms and Abbreviations
'Ihe acronyms presentet in this section are used in the Certified Design Material. The acronyms are provided for information and are not part of the Certified Design Material.
ac Altemating 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 i CAV Cumulative Absolute Velocity CCS Component Cooling Water System i CDM Certified Design Material I CDS Condensate System CFR Code of Federal Regulations CIV Containment Isolation Valve CL Cold Leg CMT Core Makeup Tank O CNS Containment System i COL Combined Operating License CRDM Control Rod Drive Mechanism CST Condensate Storage Tank CVS Chemical and Volume Control System DAC Design Acceptance Criteria l 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 l DPU Distributed Processing Unit D-RAP Design Reliability Assurance Program i DTS Demineralized Water Treatment System DVI Direct Vessel Injection DWS Demineralized Water Transfer and Storage System ECS Main ac Power System EDS Non-Class 1E de and Unintenuptible Power Supply System i EFS Communication System i EGS Grounding and Lightening Protection System ELS Plant Lighting System EMI Electromagnetic Interference (N ERF Emergency Response Facility o) [ W85tl!)gh0USB o:bp600VTAACSvev4Vt0101.wpf: 98
Certified Design Material INTRODUCTION r Revision: 4 Effective: 4/6/98 List of Acronyms and Abbreviations (cont.) l 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 IE de and Uninterruptible Power Supply System IIS In-core Instrumentation System ILRT Integrated Leak Rate Test IHP Integrated Head Package in Inches 1/O Input / Output 1 I&C Instrumentation and Control ! IRC Inside Reactor Containment IRWST In-containment Refueling Water Storage Tank ISI Inservice Inspection IST Inservice Testing l l ITA Inspections, Tests, Analyses l ITAAC Inspections, Tests, Analyses, and Acceptance Criteria l LBB Leak Before Break LTOP Low Temperature Overpressure Protection MBtu Million British Thermal Units MCC Motor Control Center MCR Main Control Room MHS Mechanical Handling System i MMIS Man-machine Interface System O 1.0-10 [ WBStllighouse o:\ap600VTAACSvev4Vt0101.wpf:o40398
Certified Design Material INTRODUCTION - (] Revision: 4 = V Effective: 4/6/98 List of Acronyms and Abbreviations (cont.) MOV Motor-operated Valve MSIV Main Steam Isolation Valve MSLB Main Steam Line Break MSS Main Steam System i MTS Main Turbine System MW Megawatt MWe Megawatt Electric MWt Megawatt Thermal N/A Not Applicable NDE Nondestmetive Examination NI Nuclear Island NSSS Nuclear Steam Supply System OCS Operation and Control Centers System ORC Outside Reactor Containment ORE Occupational Radiation Exposure i OSA Operational Sequence Analyses OSC Operations Support Center PAR Passive Autocatalytic Recombiner l PCCAWS Passive Containment Cooling Ancillary Water Storage Tank f)
'd l PCWS PCCWST Passive Containment Cooling Water Storage Passive Containment Cooling Water Storage Tank PCS Passive Containment Cooling System P&ID Piping and Instmment Diagram i PGS Plant Gas System pH Potential of Hydrogen PLS Plant Control System I PMS Protection and Safety Monitoring System i PORV Power-operated Relief Valve I PRA Probabilistic Risk Assessment PRHR Passive Residual Heat Removal psia Pounds per Square Inch Absolute j PSS Primary Sampling System .
PXS Passive Core Cooling System PWR Pressurized Water Reactor RAP Reliability Assurance Program RAT Reserve Auxiliary Transfonner RCDT Reactor Coolant Drain Tank RCP Reactor Coolant Pump l RCPB Reactor Coolant Pressure Boundary ; I RCS Reactor Coolant System ' RFI Radio Frequency Interference RM Refueling Machine RMS Radiation Monitoring System L/I 1.0-11 l [ W85tilighouse o:\ap600\lTAACS\rev4Vt0101.wpt:o40398 l , u !
Certified Design Material INTRODUCTION N5 Revision: 4 - 4 Effective: 4Mi/98 i e List of Acronyms and Abbreviations (cont.) RNS Normal Residual Heat Removal System i 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 i SJS Seismic Monitoring System i SMS Special Monitoring System SSAP, Standard Safety Analysis Repon SSUs Stmetures, Systems, and Components SSE Safe Shutdown Eanhquake i SWC Surge Withstand Capability SWS Service Water System TID Total Integrated Dose TSC Technical Suppon Center UAT Unit Auxiliary Transfomier UBC Uniform Building Code UPS Uninterruptible Power Supply V Volt i VAS Radiologically Controlled Area Ventilation System VBS Nuclear Island Nonradioactive Ventilation System I VCS Containment Recirculation Cooling System VES Main Control Room Emergency Habitability System i VFS Containment Air Filtration System i 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 i WGS Gaseous Radwaste System WLS Liquid Radwaste System I WSS Solid Radwaste System ZOS Onsite Standby Power System O T Westinghouse o:\ap600\lTAACS\rev4\it0101.wpf:04 39
Certified Design Material l FUEL HANDLING AND REFUELING SYSTEM ~ (] Revision: 4 =
' _)
( Effective: 4/6/98 { 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. The refueling machine (RM) and the fuel I transfer tube are operated during refueling mode. The fuel handling machine (FHM) and the new and I spent fuel storage racks are operated during normal modes of plant operation, including startup, power I operation, cooldown, shutdown and refueling. 1 l l The component locations of the FHS are as shown in Table 2.1.1-2. I 1. The FHS has the RM, the FHM, and the new and spent fuel storage racks.
- 2. The FHS preserves containment integrity by isolation of the fuel transfer tube penetrating containment.
- 3. The RM and FHM gripper assemblies are designed to prevent opening while the weight of the fuel assembly is suspended from the gripper.
- 4. The lift height of the RM and FHM masts is limited such that the minimum required depth of !
O water shielding is maintained. O
- 5. The RM and FHM are designed to maintain their load carrying and structuralintegrity functions during a safe shutdown earthquake. l 1
- 6. The new and spent fuel storage racks maintain the effective neutron multiplication factor less than l the required limits during normal operation, design basis seismic events, and design basis dropped fuel assembly accidents.
I i Inspections, Tests, Analyses, and Acceptance Criteria Table 2.1.1-1 specifies the inspections, tests, analyses, and associated acceptance criteria for the FHS. l "A v 2.1.1-1 W85tliigh00S8 c:VTAACSvevet020101.wpt:032798 l i E
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I Certified Design MCterial I I FUEL HANDLING AND REFUELING SYSTEM _ Revision: 4 Effective: 4/6/98 - Table 2.1.1-1 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The FHS has the refueling Inspection of the system will be The 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.
- 2. The FHS prewrves See Certified Design Material, See Certified Design Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the fuel transfer tube System. System.
penetrating containment.
- 3. The RM and FHM gripper The RM and FHM will be tested The 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.
- 4. The lift height of the RM and The RM and FHM will be tested The bottom of the dummy fuel FHM masts is limited such that by attempting to raise a dummy assembly cannot be raised higher the minimum required depth of fuel assembly. than plant elevation of 109 ft, water shielding is maintained. 8 in.
- 5. 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 mtegnty functions. l O [ WJ5tiflgh00SB o:VTAACSVev4Vt020101.wpf 9
( Certified Design Material FUEL HANDLING AND REFUELING SYSTEM T=I
/~' Revision: 4 3~ E
()N Effective: 4/6/98 i ,ee Table 2.1.1 1 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 6. 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 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 p 0.95. G 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 .ssembly loads and maintain the calculated effective neutron multiplication factor less than 0.95. I J 2.1.1-3 l 3 Westiflgh00Se oNTAACSvev4Vt020101.wpf.032798
1 I I Certified Design Mcterial FUEL HANDLING AND REFUELING SYSTEM EEMEE Revision: 4 *
- I Effective: 4/6/98 i .et l Table 2.1.12 l Component Name Tag No. Component Location l Refueling Machine FHS-FH-01 Containment I Fuel Handling Machine FHS-FH-02 Auxiliary Building l Spent Fuel Storage Racks FHS-FS-20 Auxiliary Building l New Fuel Storage Racks FHS-FS-01 Auxiliary Building l Fuel Transfer Tube FHS-FT-01 Auxiliary Building / Containment O
O 2.1.1-4 W85tiflgh00Se o:VTAACSVev4Vt020101.wpf:032998
- - . _ _ - . - _ - a
J I Certified Design Mat: rial ! l I REACTOR COOLANT SYSTEM - A () Revision: 4 ' " Effective: 4/6/98 2.1.2 Reactor Coolant System { I Design Description j i 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 and
)
j l four canned motor reactor coolant pumps (RCPs). t l i The RCS is as shoven in Figure 2.1.2-1 and the component locations of the RCS are as shown in I Table 2.1.2-5. ] I 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 III are designed and .
constructed in accordance with ASME Code Section 111 requirements. I l
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b) The piping identified in Table 2.1.2-2 as ASME Code Section IIIis designed and constructed in j accordance with ASME Code Section III requirements. '
- 3. a) Pressure boundary welds in components identified in Table 2.1.2-1 as ASME Code Section III !
meet ASME Code Section III requirements. () b) Pressure boundary welds in piping identified in Table 2.1.2-2 as ASME Code Section 111 meet ASME Code Section III requirements. 1
- 4. a) The components identified in Table 2.1.2-1 as ASME Code Section III retain their pressure ;
boundary integrity at their design pressure. i b) The piping identified in Table 2.1.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure. 1 1 5. a) The seismic Category I equipment identified in Table 2.1.21 can withstand seismic design basis j loads without loss of safety function. ; I b) Each of the lines identified in Table 2.1.2-2 for which functional capability is required is designed I 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 2.1.2-2 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 l the line. l I
O 3 W85tingh00S8 0:VTAACSVev4Vt0212a wp6:1b b8
REACTOI: COOLANT dYSTEM 7-T~ Revision: 4 - Effective: 4/6/98 *
- 8.
- 7. a) The Class 1E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmen*.al conditions that would exist before, during, and following a design basis accident without loss of safety function for die time required to perform the safety function.
b) The Class 1E components identified in Table 2.1.2-1 are powered from their respective Class IE division. I c) Separation is provided between RCS Class IE divisions. and between Class 1E divisions and non-Class IE cable.
- 8. The RCS provides the following safety-related functions:
a) The pressurizer safety valves provide overpressure protection in accordance with Section 111 of the ASME Boiler and Pressure Vessel Code. I b) The pressurizer safety valves operate with low flow at pressures near the valve set pressure. I c) The reactor coolant pumps (RCPs) have a rotating inertia to provide RCS flow coastdown on loss of power to the pumps. I d) Each RCP flywheel assembly can withstand a design overspeed condition. I e) The RCS provMes automatic depressurization during design basi: events. I 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. I 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).
11.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functions. 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 as having diverse actuation system (DAS) control perform an active safety function after receiving a signal from DAS. O T Westinghouse oWAACSvev4WO212a.wp6d 0
Certified Design Material REACTOR COOLANT faYSTEM Es" - r~ N. Revision: 4 ~ Effective: 4/6/98 1 12. a) The automatic depressurization valves identified in Table 2.1.2-1 perform an active safety-related function to change position as indicated in the table. b) Afterloss of motive power, the remotely operated valves identified in Table 2.1.2-1 assume the indicated loss of motise pow'r 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 :n 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.
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Certified Design Material REACTOR COOLANT SYSTEM - Revision: 4 9 5 lO y,) Effective: 4/6/98 1 -
.ee Table 2.1.2-2 ASME Code Leak Before Functional Capability Line Name Line Number Section III Break Required Hot Legs RCS-LOOlA Yes Yes Yes RCS-L001B 1'
Cold legs RCS-LOO 2A Yes Yes Yes RCS-LOO 2B RCS-LOO 2C RCS-LOO 2D ! Pressurizer Surge Line RCS-IA03 i Yes Yes Yes j ADS Inlet Headers RCS-LOO 4A/B Yes Yes Yes RCS 1406A/B RCS-LO30A/B RCS-LO20A/B Safety Valve Inlet Piping RCS-LOOSA Yes Yes Yes , RCS-LOO 5B l Safety Valve Discharge RCS-IA50A/B Yes No Yes Piping RCS-LOS1 A/B # 1 s l ADS First-stage Valve RCS-LO10A/B Yes No Yes i i Inlet Piping RCS-LOl1 A/B
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ADS Second-stage Valve RCS-LO21 A/B Yes Yes Yes Inlet Piping RCS-LO22A/B RCS-1423A/B ADS Third-stage Vale RCS-1A31 A/B Yes Yes Yes l Inlet Piping RCS-LO32A/B RCS-LO33A/B ADS Outlet Piping RCS-LO12A/B Yes No Yes RCS-LO23A/B RCS-LO33A/B RCS-LO34A/B RCS-LD61A/B RCS-LO63A/B RCS LO64A/B RCS-L200A/B ! PXS-L130A/B l ADS Fourth-stage Inlet RCS-Ll33A/B Yes Yes Yes i Piping RCS-L135A/B l RCS-Ll36A/B RCS-L137A/B Pressurizu my Piping RCS-L110A/B Yes No No RCS-L212A/B RCS-L213 RCS-L215 (-
's.s 2.1.2-17
[ W85tiligt10tlS8 oNTAACSVevt40212a.wp6:1b-040198 L
Certified Design Material REACTOR COOLANT SYSTEM TE
" E Revision: 4 Effective: 4/6/98 1 *.ee Table 2.1.2-3 Equipment Tag No. Display Control Function RCP 1 A Breaker (Status) ECS-ES-51 Yes -
RCP 1 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-EH-03 Yes On/Off Pressurizer Heaters RCS-EH-04A Yes On/Off Pressurizer Heaters RCS-EH44B Yes On/Off Pressurizer Heaters RCS-BH-04C Yes On/Off Pressurizer Heaters RCS-EH-04D 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-VO(MC ' .. - l (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 apphcable. h l l i 9 [ W8Stingh00S8 oNTAAcsvev4'ato212a.wps:1 o'019 4 l l
Certified Design M;terial REACTOR COOLANT SYSTEM = f Revision: 4 ~ y Effective: W6/98 i 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-PI 150A Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PI-150B Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PI 150C Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-150D Yes - (Position Indication) l l Note: Dash (.) indicates not apphcable. o l O V 2.1.2-19 W6Sti@6 o:VTAACSVev4Vt0212a.wp6:1b-040198 L
Certified Design Material l REACTOR COOLANT SYSTEM "- l
= E Revision: 4 Effective: 4/6/98 1 - ee i
Table 2.1.2-4 ! Inspections. Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 1. 'Ihe functional arrangement of Inspection of the as-built system The as-built RCS is as described in l 1 the RCS is as described in the will be performed. the Design Description of this i l Design Description of this Section 2.1.2. I Section 2.1.2. 2.a) The 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 Section III Sectic, III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME code Section III design Table 2.1.2-2 as ASME Code the as-built components as reports exist for the as-built piping Section III is designed and documented in the ASME design identified in Table 2.1.2-2 as ASME constructed in accordance with reports. Code Section' .. 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 Section III requirements. Section III reouirements. boundarv welds. 3.b) Pressure boundary welds in 'nspection 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. J l l 1 l [ WeStiflghotise o:vTAAcsvevWt0212a.wp6:1tN04019 _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _A
Certif'>d Design Material REACTOR COOLANT SYSTEM ' ~ ~
- E Revision: 4
( Effective: 4/6/98 i - I Table 2.1.2-4 (cont.) Inspections. Tests, Analyses,and Acceptance Criter y Design Conunitment 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 IIIto be hydrostatically Table 2.1.2-1 as ASME Code pressure. tested. Section IIIconform with the requirements of the ASME Code Section III. 4.b) The piping idenufied in Table A hydrostatic test will be A report exists and concludes that l 2.1.2-2 as ASME Code Section 111 performed on the piping required the results of the hydrostatic test of retains its pressure boundary by the ASME Code Section III to the piping identified in Table 2.1.2- , integrity at its design pressure. be hydrostatically tested. 2 as ASME Code SectionIII { conform with the requirements of the ASME Code Section III. I 5.a) The seismic Category I i) Inspection will be perfonned 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 basisloads without in Table 2.1.2-1 are located on Nuclear Island. loss of safety function. the Nuclear Island. b Q 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, i or analyzed conditions. l 5.b) Each of the lines identified in Inspection will be performed for A report exists and concludes that j i Table 2.1.2-2 for which functional the existence of a report verifying each of the as-built lines identified I capability is required is designed that the as-built piping meets the in Table 2.1.2-2 for which I to withstand combined normal and requirements for functional functional capability is required I seismic design basis loads without capability. meets the requirements for
'I a loss ofits functional capabilitv. functional capability.
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i Certified Design M terial ; I
* =
REACTOR COOLANT SYSTEM ^ Revision: 4 E l Effective: 4/6/98 Table 2.1.2-4 (cont.) Inspections. Tests, Analyses, and Acceptance Criteria i 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 l 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 dynamic 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 1E 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 accident 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. 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 simuleen Class IE equipment identified in powered from their respective signal in each Class 1E divi:un. Table 2.1.2-1 when the assigned Class IE division. Class 1E division is provided the test signal. 7.c) Separation is provided See Cenified 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 1E 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 wndor 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. 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 tiressure. O W6Stiflghouse o:VTAACSvev49t0212a wp6:1 403 1 1 __-]
1 1 l Certified Design Material l REACTOR COOLANT SYSTEM "" A Revision: 4 T Effective: 4M/98 i l l Table 2.1.2-4 (cont.) Inspections. Tests. Analyses, and Acceptance Criteria Design Commitment Inspections. Tests. Analyses Acceptance Criteria I 8.b) The pressurizer safety valves Tests or type tests are performed A report exists and concludes that I operate with low flow at pressures to correlate flo v through the the safety valves operate in a stable I near the valve set pressure. safety valves as a function ofinlet manner with a leakage rate greater l pressure, or equal to 0.35 lbm/sec at a l l pressure below the valve full-open i I pressure. I 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-ft2 . coastdown on loss of power to the pumps. I 8.d) Each RCP flywheel assembly Shop testing of each RCP Each RCP flywheel assembly has l 1 can withstand a design overspeed flywheel assembly will be passed an overspeed condition of no I condition. performed at the vendor facility at less than 125% of operating speed. I overspeed conditions. l 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 i basis events. conducted to determine the total through the sparger with all valves piping flow resistance of each of each ADS group open is ! F ADS valve group connected to s 2.46E-6 ft/gpm 2, 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 l injection flowinto the RCS j l discharging through the ADS i l valves. l l Inspections and associated analysis of the piping flow paths ; from the discharge of the ADS l I ' valve groups connected to the pressurizer (i.e., ADS Stages 1-3) to the spargers will be conducted to verify the line routings are consistent with the line routings used for desip flow resistance calculations. p V 2.1.2-23 [ W8Stil4tl0ilS6 o:VTAACSVev4Vt0212a.wp6:1t440198
Certified Design Material REACTOR COOLANT SYSTEM N Rcvision: 4 Effective: 4/6/98 - 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. each hot leg) will be conducted to verify the line routing is consistent with the line souting used for design flow resistance calculations. I iii) Inspections of each fourth- iii) The flow area through each I stage ADS valve will be fourth-stage ADS valve is 2 38 in2 , I conducted to determine the flow I area through each valve. 1 I iv) Type tests and analysis will iv) A report exists and concludes be performed to determine the that the effective flow area through i effective flow area through each each stage 1 ADS valve a 4.6 ia2 I stage 1,2,3 ADS valve. and each stage 2,3 ADS valve is 1 2 21 in2, I I v) Inspections of the elevation of v) The minimum elevation of the I the ADS stage 4 valve discharge bottom inside surface of the outlet I will be conducted. of these valves is greater than plant i elevation 110 feet. I I vi) Inspections of the ADS stage vi) The discharge of the ADS stage 1 4 valve discharge will be 4 valves is directed into the steam I conducted. generator compartments. I l vii) Inspection of each ADS vii) The flow area through the holes I sparger will be conducted to in each ADS sparger is a 274 in'. I determine the flow area through I the sparger holes. ! I viii) The centerline of the i viii) Inspection of the elevation connection of the sparger arms to 1 of each ADS sparger will be the sparger hub is s 11.5 feet below j i conducted. the IRWST overflow level. j l 8.f)The RCS provides emergency Inspections of the reactor vessel A report exists and concludes that I letdown during design basis head vent valves and inlet and the capacity of the reactor vessel I events. outlet piping will be conducted. head vent is sufficient to pass not I less than 8.2 lbm/sec at 1250 psia in I the RCS. O W8dl1$10USB 0:VTAACSvev4Vt0212a.wp6:1 4019
Certified Design M terial _ REACTOR COOLANT SYSTEM
/T Revision: 4 "
b Effective: 4/6/98 _ Table 2.1.2-4 (cont.) Inspections. Tests. Analyses,and Acceptance Criteria Design Commitment Inspections. Tests. Analyses Acceptance Criteria 9.a) The RCS provides circulation Testing and analysis to measure The calculated post-fuel load RCS I of coolant to remove heat from the RCS flow with four reactor flow rate is 2193,200 rpm. core. coolant pumps operating at no-load RCS pressure and temperature conditions will be performed. Analyses to convert the measured pre-fuelload flow I I will be performed. This analysis I accounts for flow measurement I 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.
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y! l 9.c) The pressurizer heaters trip Testing will be performed to The pressurizer heaters identified in I after a signal is generated by the confirm trip of the pressurizer Table 2.1.2-3 trip after a signalis l PMS. heaters identified in generated by the PMS. 1 Table 2.1.2-3.
- 10. Safety-related disp!ays Inspection will be performed for Safety-related displays identified in identified in Table 2.1.2-1 can be retrievabihty of the safety-related Table 2.1.2-1 can be retrieved in the retrieved in the MCR. displays in the MCR. MCR.
I1.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 electrical leads 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 l m'
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Certified Design M:terial FIEACTOR COOLANT SYSTEM e = .= Revision: 4 E Effective: 4Ed98 1 -
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Table 2.1.2 4 (cont.) Inspections Tests, Analyses,and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 11.b) The valves identified in i) Testing will be performed on i) The 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 j from the PMS. 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 PMS control perform the using real or simulated signals active function identified in the into the PMS. table after receiving a signal from PMS. I iii) Testing will be performed to iii) These valves open within the i demonstrate that remotely following times after receipt of an 1 operated RCS isolation valves actuation signal: 1 RCS-V001 A/B, V002A/B, l V003A/B open within the V001A/B < 30 sec l required response times. V002A/B V003A/B < 80 see 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) The other remotely operated ii) Testing will be performed on valves identified in Table 2.1.2-1 as the other remotely operated having DAS control perform the valves identified in Table 2.1.2-1 active function identified in the using real or simulated signals table after receiving a signal from into the DAS. DAS. O Wed@WS8 oNTAACS\rev4 Nit 0212a.wp6:1 019 i
l l Certified Design Material REACTOR COOLANT SYSTEM TF ( Revision: 4 = = l Q] Effective: 4/6/98 1 *
. ee l
Table 2.1.2-4 (cont.) Inst. ctions, Tests. Analyses,and Acceptance Criteria Design Commitment in.,pedicas, Tests, Analyses Acceptance Criteria l 12.a) The automatic i) Tests or type tests of motor- i) A test report exists and concludes I depressurization valves identified operated valves will be perfonned 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. I iii) Tests of the as-installed iii) Each motor-operated valve I notor-operated valves will be changes position as indicated in I performed under pre-operational Table 2.1.2-1 under pre-operational I flow, differential pressure and test conditions. I temperature conditions. I i i iv) Tests or type tests of squib iv) A test report exists and r O V l I valves will be performed that demonstrate the capability of the concludes that each squib valve changes position as indicated in I valve to operate under its design Table 2.1.2-1 under design I conditions. conditions. I l v) Inspection will be performed v) A report exists and concludes i for the existence of a report that the as-installed squib valves are i verifying that the as installed bounded by the tests or type tests. I squib valves are bounded by the I tests or type tests. , I i vi) See item 8.e.iin this table. vi) See item 8.c.i in this table. The I ADS stage 1-3 valve flow I resistances are verified to be i consistent with the ADS stage 1-3 l path flow resistances. I I vii) See item 8.e.iiin this table. vii) See item 8.c.ii in this table. i i The ADS stage 4 valve flow I resistances are verified to be I consistent with the ADS stage 4 I path flow resistances. l I l fi o t 2.1.2-27 N0dIMEO c:VTAACSvev4Vt0212a.wp6:1b-040198 l l u
Certified Design M:terial REACTOR COOLANT SYSTEM =- -tE Revision: 4 ' Effective: 4/6/98 Table 2.1.2-4 (cont.) Inspections. Tests, Analyses,and Acceptance Criteria r Design Commitment Inspections, Tests Analyses Acceptance Criteria i viii) See item 8.e.iiiin this table. viii) See item 8.c.iiiin this table. I I ix) See item 8.e.iv in this table. ix) See item 8.c.iv in this table. I 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 i 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.
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Certified Design Material i REACTOR COOLANT SYSTEM --
- Rt. vision: 4 O
- Effective: 4/6/98 m-I Table 2.1.2-5 i Component Name Tag No. Component Location i Steam Generator 1- RCS-MB-01 Containment i Steam Generator 2 RCS-MB-02 Containment l Reactor Coolant Pump 1 A RCS-MP-01A Containment l Reactor Coolant Pump IB RCS-MP-OlB Containment i Reactor Coolant Pump 2A RCS-MP-02A Containment l Reactor Coolant Pump 2B RCS-MP-02B Containment l Pressurizer RCS-MV-02 Containment
- 1. ADS Sparger A PXS-MW-01A Containment i ADS Sparger B PXS-MW-OlB Containment O
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Certified Design Material REACTOR SYSTEM Z-tm /N Revision: 4 -
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Effective: 4/6/98 1 - ee 2.1.3 Reactor System Design Description i The reactor system (RXS) generates heat by a controlled nuclear reaction and transfers the heat I generated to the reactor coolant, provides a banier that prevents the release of fission products to the I atmosphere and a means to insert negative reactivity into the reactor core. I The RXS is operated during normal modes of plant operation, including startup, power operation, I cooldown, shutdown and refueling. l 'Ihe component locations of the RXS are as shown in Table 2.1.3-3. I I 1. The RXS components are identified in Table 2.1.3-1. I I 2. a) 'Ihe reactor upper internals rod guide arrangement is as shown in Figure 2.1.3-1. 1 I b) The rod cluster con:rol and drive rod arrangement is as shown in Figure 2.1.3-2. I I c) The reactor vessel arrangement is as shown in Figure 2.1.3-3. v} I 3. The 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], I incore instrument guide tubes) components identified in Table 2.1.3-1 as ASME Code Section III retain their pressure boundary integnty 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 nozzle limits the blowdown of the reactor coolant system (RCS) I following the break of a direct vessel injection line. I 9. a) The 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 o Class 1E division. 2.1.3-1 [ W85tiligh0USB . o:VTAACSVev4\it020103.wpf:040398
Certified Design Material i REACTOR SYSTEM = - - Revision: 4 .5 , I Effective: 4/6/98 c) Separation is provided between RXS Class IE divisions, and between Class IE divisions and non-Class IE cable. I 10. The reactor lower intemals assembly is equipped with holders for at least eight capsules for storing I 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 l control room (MCR). Inspections, Tests, Analysis, and Acceptance Criteria Table 2.1.3-2 specifies the inspections, tests, analysis, and associated acceptance criteria for the RXS. O 1 l 9 3 Westinghouse oNTAACSVev4Vto20103 wpf OI9
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REACTOR SYSTEM EEt Revision: 4
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Effective: 4/6/98 _ Table 2.1.3 2 { Inspections, Tests, Analysis, and Acceptance Criteria I Design Commitment Inspections, Tests, Analysis Acceptance Criteria
- 1. The RXS components are Inspection of the as-built system The as-built RXS has the identified in Table 2.1.3-1. will be performed. components identified in Table 2.1.3-1.
I 2. The reactor upper internals rod Inspection of the as-built system The as-built RXS will I guide arrangement is as shown in will be performed. accommodate the fuel assembly l Figure 2.3.1 1. and control rod drive mechanism
! pattern shown in Figure 2.3.1-1.
I 2.b) he rod cluster control and Inspection of the as-built system The as-built RXS will I drive rod arrangement is as will be performed. accommodate the rod cluster I shown in Figure 2.1.3-2. control and drive rod arrangement I shown in Figure 2.1.3-2. I 2.c) The reactor vessel Inspection of the as-built system The as-built RXS will l arrangement is as shown in will be performed. accommodate the reactor vessel l Figure 2.I.3-3. arrangement shown in i Figure 2.1.3-3. I 3. The components identified in Inspection will be conducted of The ASME Code Section III Table 2.1.31 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 2.1.3-1 as ASME Code ASME Code Section III Section III. requirements. I 4. Pressure boundary welds in Inspection of as-built pressure A report exists and concludes that 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. 1 5. The pressure boundary A hydrostatic test will be A report exists and concludes that I components (RV, CRDMs. incore performed on the components of the results of the hydrostatic test I instrument guide tubes) retain the RXS required by the ASME of the pressure boundary I their pressure boundary integrity Code Section III to be components (RV, CRDM's, I at their design pressure. hydrostatically tested. incore instrument guide tubes) conform with the requirements of the ASME Code Section III. O 2.1.3-6 W85tkighotise o:VTAACSvev4\it020103.wpf:033198 _____-______m
Cettified Design Material REACTOR SYSTEM mn (N Revision: 4 " y/ Effective: 4/6/98 I Table 2.1.3-2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections, Tests, Analysis Acceptance Criteria I 6. The seismic Category I i) Inspection will be perfonned 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 2.1.31 is located on the seismic design basis loads without Table 2.1.3-1 is located on the Nuclear Island. loss of saty 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. f} V or analyzed conditions. I 7. The reactor internals will i) A vibration type test will be i) A report exists and concludes I withstand the effects of flow conducted on the AP600 prototype that the prototype reactor I induced vibration. reactor internals. internals have no observable l J damage or loose parts as a result I of the vibration type test. I I ii) A pre-test inspection, a flow ii) The as-built reactor internals I test and a post-test inspection will have no observable damage or i be conducted on le as-built loose parts. I reactor internals. I 8. The reactor vessel direct An inspection will be conducted The throat area of the direct I l vessel injection nozzle limits the to verify the flow area of the flow vessel injection line nozzle flow l l blowdown of the RCS following limiting venturi within each direct limiting venturi is less than or I the break of a direct vessel vessel injection nozzle. equal to 12.57 in2, I injection line. A I (J 2.1.3-7 Westiflghollse oNTAACS\rev4\it020103.wpf;033198
Certified Design Material REACTOR SYSTEM EE i Revision: 4 Ei Effective: 4/6/98 l 1 Table 2.1.3-2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections, Tests, Analysis Acceptance Criteria l 9.a) 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 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 function. 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 Cisss IE equipment identified in powered from their respective cach 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 1E cable. I 10. 'Ihe reactor lower internals Inspection of the reactor lower At least eight capsules are in the l assembly is equipped with holders internals assembly for the reactor lower internals assembly. I for at least eight capsules for presence of capsules will be i storing material surveillance performed. I specimens l 11. 'Ihe RPV beltline material Testing of the Charpy V-Notch A report exists and concludes that I 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. I 12. Safety-related displays of the Inspection will be performed for Safety-related displays identified parameters identified in retrievability 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 2.1.3-8 W85tiflgh00S8 o:VTAACSVev4Vt020103.wpt033198 1
Certified Design Material REACTOR SYSTEM f^N, Revision: 4 = () Effective: 4/6/98 I Table 2.1.3-3 i Component Name Tag No. Component Location i RV RXS-MV-01 Containment 1 1 Reactor Upper Internals Assembly RX-MI-01 Containment l Reactor Lower Internals Assembly RXS-MI-02 Containment i Fuel Assemblies (145 locations) RXS FA- Containment i A04/A05/A06/A07/A08/A09/ l A10/B03/B04/B05/B06/B07/ l B08/B09/B10/B11/C02/C03/ l C04/C05/C06/C07/C08/C09/ l C10/Cl1/Cl2/D01/D02/D03/ 1 D04/D05/D06/D07/D08/D09/ 1 D10/D11/D12/D13/E01E02/ l E03E04E05E06/E07E08/ l E09E10/EllE12/E13/F01/ I F02/F03/F04/F05/F06/F07/F08/ I F09/F10/Fil/F12/F13/G01/ I G02/G03/G04/G05/G06/G07/ g i G08/G09/G10/Gil/G12/G13/ ("g) i H01/H02/H03/H04/H05/H06/ l H07/H08/H09/H10/Hil/H12/ I H13/J01/J02/J03/J04/J05/J06/ l J07/J08/J09/Jl0/Jl1/J12/J13/ I K01/K02/K03/K04/K05/K06/ I K07/K08/K09/K10/K11/K12/ l K13/LO2/LO3/LO4/LOS/LO6/ l LO7/LO8/LO9/L10/L11/L12/ 1 M03/M04/M05/M06/M07/ l M08/M09/M10/M11/N04/N05/ l N06/N07/N08/N09/N10 i Rod Cluster Control Assemblies RXS-FR- Containment I (RCCAs) (minimum 45 locations) B04/B06/B08/B10/C05/ I C07/C09/D02/D04/D06/D08/ l D10/D12E03E11/F02/F04/ l F06/F08/F12/G03/G07/Gil/ I H02/H04/H06/H08/H10/H12/ I J03/Jl1/K02/K04/K06/K08/ I K10/K12/LOS/LO7/M04/M06/ l M08/M10
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Certified Design Material REACTOR SYSTEM 7~~"g Revision: 4 ~
=
Effective: 4/6/98 i Table 2.1.3-3 I Component Name Tag No. Component Location i Control Rod Drive Mechanisms RXS-MV- Ca.tainment I (CRDMs)(61 Locations) 11 A07/11B04/11B06/11B08/ I 11B10/11C03/ llc 05/IIC07/ l llc 09/llCll/llD02/llDM/ l llD06/llD08/11D10/llD12/ I 11E03/11E05/11E07/11E09/ I 1lEl1/1IF02/1IF04/1IF06/ I IIF08/llF10/IlF12/11001/ l 11G03/11G05/11G07/11G09/ I 11011/1IG13/11H02/11H04/ I IIH06/11H08/lIH10/11H12/ l 11J03/11J05/11J07/11J09/ l 11Jl1/11K02/11K04/11K06/ l 11K08/llK10/IIK12/IILO3/ l 1ILOS/lILO7/11LO9/11L11/ I 11M04/11M06/11M08/l1M10/ l 1IN07 I Incore Instrument Guide Tubes (38 IIS-JT- Containment i Core Locations) G01 through G38 l Source Range Detectors (4) RXS-JE-NE001 A/NE001B/ Containment i NE001C/NE001D l Intermediate Range Detectors (4) RXS-JE-NE002A/NE002B/ Containment
! NE002C/NE002D 1 Power Range Detectors Lower (4) RXS-JE-NE003A/NE003B/ Containment I NE003C/NE003D I Power Range Detectors - Upper (4) RXS-JE-NEONA/NE004B/ Containment i NE004C/NE004D _
j O 2.1.3-10 W Westinghouse o:vrAACSvevtJt020103.wpf:033198 l
Certified Design Material REACTOR SYSTEM "- - ("%, Revision: 4 V Effective: 4/6/98 MM MM M M E RB B EEEEEE MMM E E EE EEE E EE EE M M M o o .MM MMM M_ E MMM M M MMM M M MNN MM MEE E M RCD GUIDE LOCATIONS i l FUEL ASSEMBLY PATTERN I Figure 2.1.3-1 1 Reactor Upper Internals Rod Guide Arrangement
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Certified Design Materi:1 REACTOR SYSTEM Z=E (% (,) Revision: 4 = 5 Effective: 4/6/98 1 ,e,
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Certified Design Material l CONTAINMENT SYSTEM =5
/^s Revision: 4 l
Effective: 4/6/98 2.2.1 Containment System Design Description The containment system (CNS) is the collection of boundaries that separates the containment I atmosphere from the outside environment during design basis accidents. l The CNS is as shown in Figure 2.2.1-1 and the component locations of the CNS are as shown in I Table 2.2.1-4. I 1. The functional arrangement of the CNS and associated systems is as described in the Design l Description of this Section 2.2.1.
- 2. a) The components identified in Table 2.2.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.1-2 as ASME Code Section III is designed and constmeted 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.
I i V b) Pressure boundary welds in piping identified in Table 2.2.1-2 as ASME Code Section III meet i 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) The 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.
I 6. a) 'Ihe 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 function for the time required to perform the safety function.
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I b) The Class IE components identified in Table 2.2.1-1 are powered from their respective l Class IE division. c) Separation is provided between CNS Class IE divisions, and between Class IE divisions and non-Class IE cable. ("T> w! i 2.2.1-1 WBSilI@0US8 o:\lTAACSirev4;it020201.wpf 1 t> 040298
Certified Design Materi:1 CONTAINMENT SYSTEM 21:m Revision: 4 = Effective: 4/6/98 _ l 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. I 8. Containment electrical penetration assemblies are protected against cunents that are greater than the continuous ratings. l 9. Safety-related displays identified in Table 2.2.1-1 can be retrieved in the main control room (MCR). I 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 protection 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. I 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. 1 O T Westingh00Se o:vTAAcsvev49to20201.wpf;1 2 __ a
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Certified Design Material CONTAINMENT SYSTEM = b
, s Revision: 4 :
i ) Effective: 4/6/98 Table 2.2.I.2 l l l ASME Code l Line Name Line Number Section III l Instrument Air In CAS-PL-L0l6 Yes l Service Air In CAS-PL-L204 Yes l Component Cooling Water Supply to Containment CCS-PL-L201 Yes l Component Cooling Water Outlet from Containment CCS-PL-L207 Yes ) l Demineralized Water In DWS-PL-L245 Yes l l Fire Protection Supply to Containment FPS-PL-L107 Yes ! l 1 Spent Fuel Pool Cooling Discharge SFS-PL-L0l7 Yes l l Spent Fuel Pool Cooling Suction from Containment SFS-PL-LO38 Yes l Containment Purge Inlet to Containment VFS-PL-L104, L105, L106 Yes l Containment Purge Discharge from Containment VFS-PL-L203, L204, L205 Yes G l Fan Cooler Supply Line to Containment VWS-PL-LO32 Yes > l Fan Cooler Return Line from Containment VWS-PL-LOSS Yes l RCDT Gas Out WLS-PL-LO22 Yes l Waste Sump Out WLS-PL-LO73 Yes l ['*g i i N,l 2.2.1-9 Westirighouse o:VTAACS\rev4Vt020201.wpf:1 b-040298 L
Certified Design Material CONTAINMENT SYSTEM --- Flevision: 4 Effective: 4/6/98 Table 2.2.I 3 Inspections, Tesu, 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 I the CNS and associated systems will be performed. 'ae functional arrangement as I is as described in the Design described in the Design l Deteription 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) The 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 constructed in accordance with Table 2.2.1-2 as ASME 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. destmetive examination of requirements. pressure boundary welds. O 2.2.1-10 Westirighouse o:VTAACSirev4\it020201.wpf:1 b-040298
Certified Design Material CONTAINMENT SYSTEM == fG Revision: 4 - () Effective: 4/6/98 Table 2.2.1-3 (cont.) Inspections, Tests, Analyses, and Acceptance 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 2.2.1-1 as ASME Code will be performed on the concludes that the results of the 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 with the requirements of the ASME Code Section III. ii) Impact testing will be ii) A report exists and concludes performed on the containment and that the containment and pressure-retaining penetration pressure-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. 4.b) The piping identified in A hydrostatic or pressure test will A report exists and concludes that 'u'; ( Table 2.2.1-2 as ASME Code 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 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 l 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. C\ V 2.2.1-11 [ W8Stiflgt100S6 0:MT AACSvev4Mt020201.wpf:1 t>-040298 l l l i
Certified Design Material CONTAINMENT SYSTEM =---- Revision: 4 - " Effective: 4/6/98 1 .et Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 6.a) The Class 1E 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 IE 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 function. I 6.b) The Class lE components Testing will be performed by A simulated test signal exists at identified in Table 2.2.1-1 are providing a simulated test signal the Class lE equipment identified powered from their respective in each Class 1E division. in Table 2.2.1-1 when the Class IE division. assigned Class 1E division is provided the test signal. I 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 l and between Class IE divisions Buildings. Buildings. and non-Class IE cable. I 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 l barrier against the release of ii) Testing will be performed to ii) The containment purge I fission products to the demonstrate that remotely isolation valves close within I atmosphere. operated containment isolation 20 seconds and all other l valves close within the required containment isolation valves close I response times. within 60 seconds upon receipt of l \ an actuation signal. l l O 2.2.1-12 T Westinghouse omAAcsvev4Vt020201.wpf:1 b-040298
Certified Design Material CONTAINMENT SYSTEM ~CL ( Revision: 4 E (3) Effective: 4/6/98 1 - a Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria I 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 maximum penetrations are protected against ratings. current of the circuits does not currents which are greater than exceed the continuous rating of their continuous ratings. the containment electrical penetration assembly, or (2) that the circuits have redundant protection devices in series and that the redundant current protection devices are coordinated with the containment electrical penetration assembly's rated short circuit thermal capacity data and prevent current from exceeding the continuous current rating of (3 the containment electrical penetration assembly. I 9. Safety-related displays Inspection will be performed for Safety-related displays ;dentified 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. I 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 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. the controls in the MCR. perform active safety functions. I 10.b) he 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 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 PMS. I 10.c) He valves identified 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 control perform the function after receiving a signal simulated signals into the DAS. active function identified in the from DAS. table after receiving a signal from DAS. .'O Q )'
' 2.2.1-13 W85tiflghouse o:VTAACSVev4Vt020201.wpf:1 b-040298
Certified Design Material CONTAINMENT SYSTEM - t=3 EE Revision: 4 Effective: 4/6/98 _ Table 2.2.1-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 11.a) The motor-operated and i) Tests or type tests of motor- i) A test report exists and l 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 ccncludes 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. I iii) Tests of the as-installed iii) Each motor-operated valve l motor-operated valves will be changes position as indicated in l performed under preoperational Table 2.2.1-1 under pre-I flow, differential pressure, and operational test conditions. l l temperature conditions. I iv) Exercise testing of the check iv) Each check valve changes
! valves with active safety functions position as inideated in Table l identified in Table 2.2.1-1 will be 2.2.1-1.
I performed under preoperational I test pressure, temperature and I fluid flow conditions. I 11.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 powcr. in Table 2.2.1 1 assumes the the indicated loss of motive indicated loss of motive power power position. position. l Table 2.2,1-4 Component Name Tag.No. Component Location l l Containment Vessel CNS-MV-01 Shield Building 1 0 2.2.1-14 3 WB5tillghouse oNTAACSvev49t020201.wpt i b-040298
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Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM - (N Revision: 4 Q) Effective: 4/6/98 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. l De PCS is as shown in Figure 2.2.2-1 and the component locations of the PCS are as shown in l Table 2.2.2-4. I 1. The functional arrangement of the PCS is as described in the Design Description of this i Section 2.2.2.
- 2. a) The components identified in Table 2.2.2-1 as ASME Code Section III are designed and l constmeted in accordance with ASME Code Section III requirements. !
l b) The piping identified in Table 2.2.2-2 as AShE Code Section III is designed and constmeted in accordance with ASME Code Section III requirements. l
- 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.
b b) Pressure boundary welds in piping identified in Table 2.2.2-2 as ASME Code Section III meet AShE Code Section III requirements.
- 4. a) The components identified in Table 2.2.2-1 as ASME Code Section III 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. 1 5. a) The seismic Category I equipment identified in Table 2.2.2-1 can withstand seismic design basis loads without loss of safety function. i, I b) Each of the lines identified in Table 2.2.2-2 for which functional capability is required is I designed to withstand combined normal and seismic design basis loads without a loss of its functional capabihty. 1 l l l c) 'Itie passive containment cooling ancillary water storage tank (PCCAWST) can withstand a ) 1 I seismic event. 1 6. a) he 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 g3 function. N] 2.2.2 1 [ WeStingh00S8 oNTAACSvev4Vt020202.wpf:040398
l Certified Design Material l PASSIVE CONTAINMENT COOLING SYSTEM 7~ Revision: 4 E Effective: 4/6/98 _ 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 lE divisions, and between Class IE divisions and non-Class IE cable. I 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 sh^11 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. I e) The PCS provides a flow path Gr long-term makeup to the passive containment cooling water i storage tank (PCCWSTL f) The PCS provides for long-term makeup from the PCCWST to the spent fuel pool. I 8. The PCS provides the following nonsafety-related functions: I 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. I 9. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the main control room (MCR). I 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 2.2.21 as having protection and safe.ty 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 w = = a use _.__ ::
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM n-z (S Revision: 4 (,) Effective: 4/6/98 h .e-i 11. a) The motor-operated and check valves identified in Table 2.2.2-1 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 2.2.2-1 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. ( ( o N 2.2.2-3 W85tirighouse o:srrAACSVev4WO20202.wpf:040298
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Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM :: === 5 Revision: 4 ' Effective: 4/6/98 1 *
.ei Table 2.2.2-2 Functional ASME Code Capability Line Name Line Number Section III Required l PCCWST Discharge Lines PCS-PL-LOOIA/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 l Post-72-hour PCCWST Makeup PCS PL-LOO 4 Yes Yes Supply Line Connection PCS-PL-LO51 l Post-72-hour PCCWST Makeup PCS-PL-LO29 Yes Yes l Supply Line PCS-PL-LO54 i Post-72-hour SFS Makeup PCS-PL-L017 Yes Yes l PCS-PL-LO49 i O O
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Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM Z-7 /m Revision: 4 ~ 5 Effective: 4/6/98 1 .et 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 ne as-built PCS conforms with I of the PCS is as described in the will be performed. the functional arrangement as I Design Description of this described in the Design l Section 2.2.2. Description of this Section 2.2.2.
2.a) He components identified Inspection will be conducted of The ASME Code Section III in Table 2.2.2-1 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 2.2.2-1 as ASME Code ASME Code Section III Section III. requirements. l 2.b) ne 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 piping identified in constructed in accordance with Table 2.2.2 2 as ASME 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 2.2.2-1 as ASME Code in accordance with the ASME requirements are met for non- ; Section III meet ASME Code Code Section III. destructive examination of I Section III requirements. pressure boundary welds.
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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 i 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.a) He components identified A hydrostatic test will be A report exists and concludes that in Table 2.2.2-1 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 2.2.2-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. p 2.2.2-7 W8Stillgl10US8 oNTAACS\rev49t020202.wpf:040398
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM _ = .m Revision: 4 ~ E Effective: 4/6/A8 1 .et Table 2.2.2 3 (cont.) Inspections, Tests. Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 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 :,eismic 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. l 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 I is designed to withstand meets the requirements for which functional capability i, i combined normal and seismic functional capability. required meets the requirements I design basis loads without a loss for functional capability. I of its functional capability. I 5.c) The PCCAWST can Inspection will be performed for A report exists and concludes that I withstand a seismic event. the existence of a report verifying the as-installed PCCAWST and I that the as-installed PCCAWST its anchorage are designed using I and its anchorage are designed seismic Category II methods and I using seismic Category 11 methods criteria. I and criteria. l O 2.2.2-8 [ W85tiligt100SB oNTAACSvev4Vt020202.wpt:040298
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM = =i I (3 Revision: 4 E () Effective: 4/6/98 Table 2.2.2 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 6.a) The 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 lE equipment identified being qualified for a harsh performed on Class IE equipment in Tables 2.2.21 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 conditions that would exist before, l 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.
I 6.b) The 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. O l 6.c) Separation is provided between PCS Class IE divisions, See Certified Design Material, See Cc-tified Design Material, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. l k) m 2.2.2-9 [ WB5tillgh0LISB oNTAACSvev4Vt020202.wpf:040298 i
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM --- Flevision: 4 - Effective: 4/6/98 Table 2.2 2-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 7.a) The PCS provides the i) Testing will be performed 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 z 0.25 ft above the lowest standpipe
- 122 gpm at a PCCWST water level of 20.65 ft 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 l 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 I 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 CONTAINMENT COOLING SYSTEM =.. Revision: 4 - '\ Effective: 4/6/98 i Table 2.7 2-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 1 7.b) The PCS provides wetting i) Tese , will be performed to i) A report exists and concludes i
) of the outside surface of the measui6 . ie wetted rie of the that with water in the PCCWST l containment vessel. containment vessel from either of at the following levels, water I the two parallel flow paths to the delivery to the containment shell I containment vessel. provides coverage measured at the i
sp-ing line that is equal to or l greater than the corresponding l coverage used to calculate peak l l containment pressure in the safety ; I analysts. ! I I l
- 23.75 0.25 ft above the I
lowest standpipe
- 20.65 0.25 ft above the I lowest standpipe i
- 13.55 2 0.25 ft above the l l lowest standpipe 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 inorganic zine coating.
l 7.c) The PCS provides air flow Inspections of the air flow path Flow paths exist at each of the over the outside of the segments will be perfonned. 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 structure. - Base of the inner annulus
- Discharge structure 1 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" above the outside of the containment vessel flow performance. annulus drain inlet, the flow rate through the two upper annulus through each drain is greater than drains. or equal to 450 gpm. /~~'
2.2.2-11 W85tiligh00S8 oNTAACSVev4Vt020202.wpf:040298
Certified Design Mat rill PASSIVE CONTAINMENT COOLING SYSTEM : Revision: 4 - Effective: 4/6/98 _ Table 2.2.2 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.e) The 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 performed to ii) With a water supply measure the delivery rate from the connected to the PCS long-term long-tenn makeup connection to makeup connection, each PCS the PCCWST. recirculation pump delivers greater than or equal to 62 gpm when tested separately. I 7.f) The 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 from the PCCWST to the spent fuel pool delivers greater than or eq2al to 50 gpm. ii) Inspection of the PCCWST ii) The volume of the PCCWST will be performed. is greater than 400,000 gallons. I 8.a) The PCS provides a Inspection of the PCCAWST will The volume of the PCCAWST is l PCCAWST initial inventory of be performed. greater than 363,000 gallons. , cooling water for PCS delivery from hour 72 through day 7. l 8.b) The PCS provides the Testing will be performed to With PCCASWST aligned to the delivery of water from the measure the delivery rate from the suction of the recirculation PCCAWST to the PCCWST. PCCAWST to the PCCWST. pumps, each pump delivers greater than or equal to 62 gpm when tested separately. I 8.c) The PCS provides water See Certified Design Material See Certified Design Material, I inventory for the fire protection subsection 2.3.4, Fire Protection subsection 2.3.4, Fire Protection I syst em. System. System. I 9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.21 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. I 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 2.2.2-1 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 W, W85tiflgh0LIS8 o:VTAACSVev4Vt020202.wpf:040298
Certified Design Material PASSIVE CONTAINMENT COOLING SYSTEM Revision: 4 Effective: 4/6/98 1 Table 2.2.2 3 (cont.) ! Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 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 I from the PMS. table after receiving a signal from the PMS. l 10.c) The valves identified in Testing will be performed on the The remotely operated valves 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 the DAS. l II.a) The 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 2.2.2-1 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 2.2.2-1 position as indicated in the table. 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-verifying that the as-installed operated valves are bounded by motor-operated valves are bounded the tested conditions, by the tested conditions. I iii) Tests of the as-installed iii) Each motor-operated valve I motor-operated valves will be changes position as indicated in I performed under preoperational Table 2.2.2-1 under preoperational I flow, differential pressure, and test conditions. I temperature conditions. I iv) Exercise testing of the check iv) Each check valve changes I valves with active safety functions position as indicated in l identified in Table 2.2.2-1 will be Table 2.2.2-1. I performed under preoperational I test pressure, temperature and fluid l flow conditions. I i1.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 ofloss 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. 2.2.2-13 WBStiflgh0llS8 oNTAACSvev4Vt020202.wpf:040298
i l l Certified Design Materi:1 l 1 l l l 1 t PASSIVE CONTAINMENT COOLING SYSTEM = l l Revision: 4 M l Effective: 4/6/98 1 .es l ! l Table 2.22-4 . 1 > l Component Name Tag No. Component Location 1 l PCCWST PCS-MT-01 Shield Building i l PCCAWST PCS-MT-05 Yard l Recirculation Pump A PCS-MP-01 A Auxiliary Building l Recirculation Pump B PCS-MP-01B Auxiliary Building l I 1 l l l l 2.2.2-14 W Westinghouse o:VTAACSvev4WO20202.wpf:040298 t
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Certified Design Material PASSIVE CORE COOLING SYSTEM ".0 - " (]j (~ Revision: 4 Effective: 4/6/98 1 , e d 2.2.3 Passive Core Cooling System Design Description The passive core cooling system (PXS) provides emergency core cooling during design basis events. I 'Ihe PXS is as shown in Fig es 2.2.3-1 and 2.2.3-2 and the component locations of the PXS are as I shown in Table 2.2.3-5. I 1. The functional arrangement of the PXS is as described in the Design Description of this l Section 2.2.3.
- 2. a) The components identified in Table 2.2.3-1 as ASME Code Section III are designed and constmeted in accordance with ASME Code Section III requirements.
b) The piping identiSed in Table 2.2.3-2 as ASME Code Section III is designed and constmeted in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.
D (b b) Pressure boundary welds in piping identified in Table 2.2.3-2 as ASME Code Section III meet ASME Code Section III requirements.
- 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. I 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. I b) Each of the lines identified in Table 2.2.3-2 for which functional capability is required is I designed to withstand combined normal and seismic design basis loads without a loss of I its functional capability. I 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. l
- 7. a) The Class IE equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditioris that would exist before, during, and following a design basis accident without loss of safety function for the time required q to perform the safety function.
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Certified Design Material PASSIVE CORE COOUNG SYSTEM - Revision: 4 -
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Effective: 4/6/98 _ 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. 'Ihe PXS provides the following safety-n'ated functions:
a) The PXS provides containment isolation of the PXS lines penetrating the containment. I b) The PRHR HX provides core do.ay heat removal during design basis events. I c) The CMTs, accumulators, in-containment refueling water storage tank (IRWST) and I containment recirculation provide reactor coolant system (RCS) makeup, boration, and safety injection during design basis events. d) The PXS provides pH adjustment of water flooding the containment following design basis accidents. I 9. The PXS has the following features: I a) The PXS provides a function to drain the IRWST into the containment. I b) The accumulator discharge check valves (PXS-PL-V028A/B and V029A/B) are of a i different check valve type than the CMT discharge check valves (PXS-PL-V016A/B and i 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). I 1. 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. I 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. I
- 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. O 2.2.3-2 [ WB5tingh00$8 oNTAACSVev4Vt020203.wpf:1 t> 040298
l l l Certified De:Ign Material l l PASSIVE CORE COOLING SYSTEM '~-~ lI' Revision: 4 E ! Effective: 4/6/98 _
- 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. l
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Certified Design Material g PASSIVE CORE COOLING SYSTEM = I i Revision: 4 ~ O Effective: 4/6/98 _ Table 2.2.3-3 Equipment Tag No. Display Control Function CMT A Discharge Isolation Valve PXS-PL-V014A Yes (Position) - (Position) CMT B Discharge Isolation Valve PXS-PL-V014B Yes (Position) - (Position) CMT A Discharge Isolation Valve PXS-PL-V015A Yes (Position) - (Position) CMT B Discharge Isolation Valve PXS-PL-V015B 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) l Accumulator A Discharge Isolation Valve PXS PL-V027A Yes (Position) - (Position) q l ) l 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) - l Containment Recirculation A Isolation PXS-PL-Vi18A Yes (Position) - Valve (Position) l 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) PXS-PL-V121 A Yes (Position) - IRWST Line B Isolation Valve (Position) PXS-PL-V121B Yes (Position) - IRWST Injection A Isolation Squib PXS-PL-V123A Yes (Position) - (Position) Note: Dash (-) indacares not apphcable. U 2.2.3-13 W85tingh00SB o:\rTAACS\rev4\it020203.wpf 1b-040298
Certified Design Material PASSIVE CORE COOLING SYSTEM i== == Revision: 4 * = Effective: 4/6/98 Table 2.2.3 3 (cont.) Equipment Tag No. Display Contrgl Function IRWST Injection B Isolation Squib PXS-PL-V123i Yes (Position) - (Position) IRWST Injection A Isolation Squib FXS-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 Sens.or PXS-042 Yes - IRWST Bottom Temperature Sensor PXS-043 Yes - IRWST Bottom Temperature Sensor PXS-044 Yes - Note: Dash (-) indicates not apphcable. O 2.2.3-14 3 Westinghouse o:vrAAesvev4Vt020203.wpf:1 b440298
i Certified Design Material PASSIVE CORE COOLING SYSTEM -- ./G Revision: 4 m Q, Effective: 4/6/98 Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Cr'teria
- 1. The functional arrangement of Inspection of the as-built system The as-built PXS ccaforms with I the PXS is as described in the will be performed. the functional arrangement as i Design Description of this described in the Design i 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 designed 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) ne 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 repons. as ASME Code Section III. { l ASME Code Section III requirements. O) C,/ 3.a) Pressure boundary welds in 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 2.2.3-1 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 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 Section III meet performed in accordance with requirements are met for non- i ASME Code Section III the ASME Code Section III. destructive examination of pressure I requirements. boundary welds. r I ( 2.2.3-15 [ W8Silligh0llSe oNTAACSvev4Vt020203.wpf:1b-040398
Certified Design Material l l l PASSIVE CORE COOLING SYSTEM I M-Revision: 4
- 5 f Effective: 4/6/98 i . e Table 2.2.3-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.a) The components identified A hydrostatic test will be A report exists and 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 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 tha: 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. I 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 I functional capability is required is meets the requirements for in Table 2.2.3-2 for which I desiFned to withstand combined functional capability. functional capability is required I normal and seismic design basis meets the requirements for i loads without a loss of its functional capability. I functional capability. O 2.2.3-16 3 W65ti!1ghouse oNTAACSVev4Vt020203.wpf A b-040298
Certified Design Material / PASSIVE CORE COOLING SYSTEM Revision: 4
.p-"y
( Effective: 4/6/98 1 ,e m Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1 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 performed of the protection from protection from dynamic effects materials, or a pipe break the dynamic effects of a rupture of a pipe break. Certified evaluation report exists and 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, 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 2.2.3-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.2.3-1 as being qualified p) y environment can withstand the environmental conditions that Class IE equipment located in a harsh environment. for a harsh environment can 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. 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 lE 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 lE 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 o k v 2.2.3-17 WesMghotise 0:VTAACSirev4Vt020203.wpf;1 t>-040298
i Certified Design Material PASSIVE CORE COOLING SYSTEM EMU Revision: 4 E: i Effective: 4/6/98 . ,e ! I Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Desig. Commitment Inspections, Tests, Analyses Acceptance Criteria 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 I basis events. will be performed to determine with the design basis number of I the heat transfer from the HX. PRHR HX tubes plugged is: 1 For the test, the reactor coolant I hot leg temperature will be 21.06 x 10 8Bru/hr with $20*F l initially at 2 540*F with the HL and 120'F IRWST l reactor coolant pumps stopped. temperatures l The IRWST water level for the i test will be above the top of the 2 4.34 x 107Bru/hr with 420*F l HX. The IRWST water HL and 212'F IRWST l temperature is not specified for temperatures I the test. The test will continue I until the hot leg temperature I 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. I Test fixtures may Se used to I 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 Q/gpm2 and s 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 5 pressurized with nitrogen. All the reactor vessel is 21.49 x 10 valves in these lines will be ft/gpm and 51.86 x 10-5 ft/gpm2 2 open during the test. Sufficient i flow w;11 be provided to fully open the check valves. I O l 2.2.3-18 l [ W85tiflgtl0USB 0:VTAACSvev4Vt020203.wpt:1 b-040298 l 1
1 Certified Design Material PASSIVE CORE COOLING SYSTEM PT / ) Revision: 4 -
=
V Effective: 4/6/98 1 . t 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 vesselis 21.33 x 10 5 provided to fully open the check ft/gpm2 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
( ) each CMT to determine piping 5 7.69 x 104ft/gpm 2, V flow resistance from the cold leg to the CMT. The test will be performed by filling the CMT via the cold leg balance line by operating the normal residual heat removal pumps. l j n x._ l l d 2.2.3 19 W85ttrighouse a:vTAACSVev4V1020203.wpf:1 t>040298
I Certified De:Ign Material PASSIVE CORE COOLING SYSTEM - - 1 Revision: 4 I Effective: 4/6/98 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria I iii) Inspections of the routing of iii) 'Ihese lines have no downward I the following pipe lines will be sloping sections between the I conducted: connection to the RCS and the i high point of the line. 1 - CMT inlet line, cold leg to I high point I - PRHR HX inlet line, hot leg I to high point l l iv) Inspections of the elevation iv) The maximum elevation of the i of the following pipe lines will top inside surface of these lines is i be conducted: less than the elevation of: I l - IRWST injection lines; - IRWST bottom inside surface l IRWST connection to DVI I nonles 1 - Containment recirculation - IRWST bottom inside surface I lines; containment to IRWST I lines 1 - CMT discharge lines to DVI - CMT bottom inside surface I connection I - PRHR HX outlet line to SG - FRHR HX lower channel head I connection top inside surface i v) Inspections of the elevation v) The elevation of the bottom of the following tanks will be inside tank surface is higher than j conducted: the direct vessel injection nonle i centerline by the following:
- CMTs - CMTs 2 7.5 ft
- IRWST - IRWST 2 3.4 ft I vi) Inspections of each of the vi) The calculated volume of each following tanks will be of the following tanks is as conducted: follows:
- CMTs - CMTs 2 2000 ft3
- Accumulators - Accumulators 2 2000 ft3 3
l - IRWST - IRWST 2 5,000 7 ft between the tank outlet connection and the tank overflow O 2.2.3-20 [ W85tkigh0LISS c:vTAACSVev4Vt020203.wpf:1 tF040298
I l Certified Design Material I, PASSIVE CORE COOLING SYSTEM = = m su:= l
/ Revision: 4 V) Effective: 4/6/98 _
5 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i vii) Inspection of the as-built vii) Plates located above each I I components will be conducted containment recirculation screen i for plates located above the are no more than 10 ft above the l l containment recirculation top of the screen and extend out at I screens, least 10 ft from the trash rack I portion of the screen. l 1 viii) Inspections of the IRWST viii) The screen surface area l and containment recirculation (width x height) of each screen is I screens will be conducted. 2 70 ft 2, The bottom of the I containment recirculation screens is i 2 2 ft above the loop compartment I floor. I ix) Inspections will be ix) The type of insulation used on I conducted of the insulation used these lines and equipment is not a I inside the containment on ASME fiberous type. I Class I lines and on the reactor i vessel, reactor coolant pumps, C I pressurizer and steam generators. I x) Inspections will be conducted x) A report exists and concludes I of the as-built nonsafety-related that the coatings used on these
]
l coatings or of plant records of surfaces has a dry film density of ' 3 I the nonsafety-related coatings 2100 lb/ft . I used inside containment on I walls, floors, ceilings, structural i steel which is part of the j l building structure and on the i polar crane. I xi) Inspection of the as-built xi) The CMT inlet diffuser has a l CMT inlet diffuser will be flow area 2165 in ,2 I conducted. I xii) Inspections will be xii) The centerline of each upper I conducted of the CMT level level tap line at the tee for each I sensors (PSX-11 A/B/D/C, - level sensor is located !" 1" I 12A/B/C/D, - 13A/B/C/D, - below the centerline of the upper I 14A/B/C/D) upper level tap level tap connection to the CMT. I lines. I [ t
%-) 1 2.2.3-21
[ W85tiflghouse oNTAACSVev4Vt020203.wpt:1 b-040298 l
Certified Design Material l PASSIVE CORE COOLING SYSTEM =- l Revision: 4 ~ Effective: 4/6/98 1 ,ee 1 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria I 8.d) The PXS provides pH Inspections of the pH adjustment Two pH adjustment baskets exist. I adjustment of water flooding the baskets will be conducted. each with a calculated volume ) containment following design 2107 ft 3. basis accidents. The pH baskets are located below plant elevation 107 ft,2 in. I 9.a) The PXS provides a i) A flow test and analysis for i) The calculated flow resistance i function to c.ool the outside of the each IRWST drain line to the for each IRWST drain line I reactor vessel during a severe containment will be conducted. between the IRWST and the I accident. The test is initiated by opening containment is s 1.38 x 10 5 isolation valves in each line. ft/gpm2, l Test fixtures may be used to i simulate squib valves. I ii) Inspections of the as-built ii) The combined total flow area i reactor vessel insulation will be of the water inlets is not less than i performed. 6 ft2. 'Ihe combined total flow I area of the steam outlet (s) is not I less than 7.5 ft2, 1 A report exists and concludes that I the minimum flow area between I the vessel insulation and reactor i vessel for the flow path that vents I steam is not less than 7.5 ft2 I considering the maximum I deflection of the vesselinsulation I with a static pressure of 12.95 ft of I water. I iii) Inspections will be iii) A flow path with a flow area i conducted of the flow path (s) not less than 6 ft2 exists from the I from the loop compartments to loop compartment to the reactor I the reactor vessel cavity. vessel cavity. I 9.b) The accumulator discharge An inspection of the accumulator The accumulator discharge check l check valves (PXS-PL-V028A/B and CMT discharge check valves valves are of a different check I and V029A/B) are of a different is performed. valve type than the CMT discharge i check valve type than the CMT check valves. I discharge check valves (PXS-PL-1 V016A/B and V017A/B). O 2.2.3-22 3 WB5tiligh00S8 o:VTAACSVev4Vt020203.wpf:1 tr040298
Certified Design Material PASSIVE CORE COOLING SYSTEM * " O V Revision: 4 Effective: 4/6/98 r 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 (Q~~j 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 Table 2.2.3-1 using real or table after a signal is input to the simulated signals into the PMS. PMS. I iii) Testing will be petformed to iii) These valves open within i demonstrate that remotely 20 seconds after receipt of an I operated PXS isolation valves actuation signal. I PXS-V014A/B, V015A/B, l V108A/B open within the I required response times. II.c) The valves identified in i) Testing will be performed on i) Squib valves receive an j Table 2.2.31 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. p 2.2.3-23 W WBSilligh0US6 oNTAACSvev4Vt020203.wpf:1 b-040298 l
Certified Design Material PASSIVE CORE COOLING SYSTEM EE T Revision: 4 - Effective: 4/6/98 _ 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 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. I iii) Tests of the as-installed iii) Each motor-operated valve i motor-operated valves will be changes position as indicated in I performed under preoperational Table 2.2.3-1 under preoperational I flow, differential pressure, and test conditions. I temperature conditions. I iv) Exercise testing of the check iv) Each check valve changes i valves with active safety position as indicated in Table I functions identified in Table 2.2.3-1. I 2.2.3-1 will be performed under l preoperational test pressure, I temperature and fluid flow I conditions. 12.b) 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 2.2.3-1 assume conditions ofloss of motive in Table 2.2.3-1 assumes the the indicated loss of motive power. indicated loss of motive power 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. O 2.2.3-24 g W65tiligh00Se o:vTAAcs vev4ut020203.wpf:1 b-040298
Certified Design Material PASSIVE CORE COOLING SYSTEM == --- s Revision: 4 -
=
Effective: 4/6/98 _ l Table 2 2.3-5 l Component Name Tag No. Component Location l Passive Residual Heat Removal Heat PXS-ME-01 Containment Building i Exchanger (PRHR HX) i Accumulator Tank A PXS-MT-01 A Containment Building l Accumulator Tank B PXS-MT-OlB Containment Building l Core Makeup Tank (CMT) A PXS-MT-02A Containment Building I CMTB PXS-MT-02B Containment Building i IRWST PXS-MT-03 Containment Building ) I i 1RWST Screen A PXS-MY-Y01 A Containment Building l 1RWST Screen B PXS-MY-Y01B Containment Building I Containment Recirculation Screen A PXS-MY-YO2A Containment Building l Containment Recirculation Screen B PXS-MY-YO2B Containment Building I pH Adjustment Basket A PXS-MY-Y03A Containment Building l pH Adjustment Basket B PXS-MY-YO3B Containment Building (~}] l / \ Nj 2.2.3-25 WBStiflgh0llSS a:vTAACSVev4Vt020203.wpf:1 t>040398
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('D Passive Core Cooling System d 2.2.3 27 [ W85tingh00S8 ONTAACSVev4Vt020203.wpt:1b 040298
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l Certified Design Material 1 STEAM GENERATOR SYSTEM t==
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Revision: 4 '(r') v Effective: 4/6/98 2.2.4 Steam Generator System Design Description i 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 1 I operation. The SGS and portions of the main steam system (MSS) and turbine system (MTS) I transport and control steam from the steam generators to the turbine generator during normal 1 operations. These systems also isolate the steam generators from the turbine generator and the I condensate system during design basis accidents. I I The SGS and portions of the FWS, MSS, and MTS are as shown in Figure 2.2.4-1, 2.2.4-2, 2.2.4-3, , I and the component locations of the SGS are as shown in Table 2.2.4-5. l l I 1. The functional arrangement of the SGS and portions of the FWS, MSS, and MTS are as described I in the Design Description of this Section 2.2.4. 1 I
- 2. a) 'Ihe components identified in Table 2.2.4-1 as ASME Code Section III are designed and constmeted in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.4-2 as ASME Code Section III is designed and constructed I in accordance with ASME Code Section III requirements.
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- 3. a) Pressure boundary welds in components identified in Table 2.2.4-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.2.4-2 as ASME Code Section III meet ASME Code Section III requirements. 3
- 4. a) The components identified in Table 2.2.4-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.4-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure. I 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. I b) Each of the lines identified in Table 2.2.4-2 for which functional capability is required is I designed to withstand combined normal and seismic design basis loads without a loss ofits I functional capability.
- 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 protection from the dynamic effects of p a rupture of the line.
O 2.2.4-1 W85tiligt10US8 o AITAACSVev4Vt020204.wpf;1b-040398 L
Certified Design Material STEAM GENERATOR SYSTEM -- Revision: 4 '- E Effective: 4/6/98 1 .e
- 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 1E division. c) Separation is provided between SGS Class IE 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. I b) During design basis events, the SGS limits steam generator blowdown and feedwater flow to the steam generator, c) The SGS pn serves containment integrity by isolation of the SGS lines penetrating the containment. The inside containment isolation function (isolating the RCS and containment atmosphere from the environment) is provided by the steam generator, tubes, and SGS lines inside containment while isolation outside containment is provided by manual and automatic valves.
- 9. The SGS provides the following nonsafety-related functions:
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 generator blowdown and feedwater flow to the steam generator. b) During shutdown operations, the SGS removes decay heat by delively 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).
11.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.4-1 to perform active functions. b) The valves identified in Table 2.2.4-1 as having PMS control perform an active safety function after receiving a signal from PMS. O 2.2.4-2 3 Westilighouse cAITAACSVev4bt020204. wpm t>-040298
( Certified Design Material l i STEAM GENERATOR SYSTEM - i-Revision: 4 ) l l%/ l em) Effective: 4/6/98 E I l 12. a) The motor-operated valves identified in Table 2.2.41 perform an active safety-related function to change position as indicated in the table. b) After icss of motive power, the remotely operated valves identified in Table 2.2.4-1 assume the indicated loss of motive power position. i Inspections, Tests, Analyses, and Acceptance Criteria l Table 2.2.4-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the SGS.
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Certified Design Material l STEAM GENERATOR SYSTEM ==l l Revision: 4 l l Effective: 4/6/98 \ 1 Table 2.2.4-3 l l Equipment Name Tag No. Control Function i Turbine Stop Valve MTS-PL-V001 A Close l l l Turbine Stop Valve MTS-PL-V001B Close I Turbine Control Valve MTS-PL-V002A Close l l Turbine Control Valve MTS-PL-V002B Close ! ! Turbine Stop Valve MTS-PL-V003A Close i Turbine Stop Valve MTS-PL-V003B Close ! I Turbine Control Valve MTS-PL-V004A Close i Turbine Control Valve MTS-PL-V004B Close i Turbine Bypass Control Valve MSS-PL-V001 Close i Turbine Bypass Control Valve MSS-PL-V002 Close
! Turbine Bypass Control Valve MSS-PL-V003 Close l Turbine Bypass Control Valve MSS-PL-V004 Close I Moisture Separator Reheat Supply Steam Control Valve MSS-PL-V016 Close l Main to Startup Feedwater Crossover Valve FWS-PL-097 Close l Main Feedwater Pump FWS-MP-02A Trip 1 Main Feedwater Pump FWS-MP-02B Trip i Startup Feedwater Pump FWS-MP-03A Trip i Startup Feedwater Pump FWS-MP-03B Trip 9
2.2.4-14 WOStingh00S8 o:\lTAACSirev4\it020204.wpt1 b-040298 l
Certified Design Material STEAM GENERATOR SYSTEM __ (N Revision: 4 - s V Effective: 4/6/98 1 . ee Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. 'Ihe functional arrangement of Inspection of the ts-built system The as-built SGS and portions of I the SGS and portions of the will be performed. the FWS, MSS, and MTS conform l FWS, MSS, and MTS are as with the functional arrangement as I described in the Design defined in the Design Description l l Description of this Section 13.4. of this Section 2.2.4. 2.a) The components identified Inspection will be conducted of The ASME Code Section III in Table 2.2.4-I 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 1 constructed in accordance with as ASME Code Section III. I
-s ASME Code Section III I I l requirements.
G 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 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 l 2.2.4 15 WeStiflghouse onlTAACSVev4Vt020204,wpf:1 b-040398
Certified Design Material STEAM GENERATOR SYSTEM =_ Revision: 4 - 5 Effective: 4/6/98 1 .et 1 Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.a) The 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-I 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 repon 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. I 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 2.2.4-I can withstand equipment identified in Table Table 2.2.4-I 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, anilyses, 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 analyzed conditions. I S.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 I is designed to withstand meets the requirements for which functional capability is I combined normal and seismic functional capability. required meets the requirements I design basis loads without a loss for functional capability. I of its functional capability. O 2.2.4-16 WBStiflgh0ljS8 c:VT AACSVev4Vt020204.wpf:1 t>-040298
Certified Design Material STEAM GENERATOR SYSTEM 7"="E Revision: 4 E V Effective: 4/6/98 Table 2.2.4-4 (cont.) , Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment inspections, Tests, Analyses Acceptance Criteria 1 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 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 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 l identified in Table 2.2.4-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.2.4-1 as being qualified environment can withstand the Class lE equipment located in a for a harsh environment can r]j 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 basis accident without loss of for the time required to perform safety function for the time the safety function. required to perfonn the safety function. 7.b) The Class IE components Testing will be perfonned by A simulated test signal exists at identified ir Table 2.2.4-1 are providing a simulated test signal the Class IE equipment identified powered from weir respective in each Class IE division. in Table 2.2.4-1 when the Class 1E 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. l and non-Class IE cable. I 1 l (h \ )) \. 2.2.4-17 [ W85tkighotise o:\lTAACS\rev4\it020204.wpt:1 b-040298 i
I I \ l Certified Design Material i STEAM GENERATOR SYSTEM r Revision: 4 Y $ Effective: 4/6/98 - ,ee Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 8.a) The SGS provides a heat i) Inspections will be conducted i) The sum of the rated sink for the RCS and provides 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 111 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. I 8.b) During design basis events, i) Testing will be performed to See item 11 in this table. I 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. I See item 11 in this table. I ii) Inspection will be performed ii) A report exists to indicate the I for the existence of a report installed flow limiting orifice I confirming that the area of the within the SG main steam line i flow limiting orifice within the SG discharge nozzle does not exceed I main steam outlet nozzle will limit 1.4 sq. ft. I 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 be performed to ii) The pumps identified in isolation of the SGS to limit confinn the trip of the pumps Table 2.2.4-3 trip after a signal is steam generator blowdown and identified in Table 2.2.4-3. generated by the PMS. feedwater flow to the steam generator, l I e 2.2.4-18 WBStiflgt10llSB oNTAACSvev4Mt020204.wpf:1b 040298
Certified Design Material STEAM GENERATOR SYSTEM r ~'N Revision: 4 ' () Effective: 4/6/98 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 I decay heat by dehvery of stanup 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 performed 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 210 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. I 3 ' 11.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 identified in Table 2.2.4-1 listed in Table 2.2.4-1 using valves to perform active safety to perform active functions. controls in the MCR. functions.
I II.b) The 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 after receiving a signal simulated signals into the PMS. the active function identified in from PMS. the table after receiving a signal from the PMS. I ii) Testing will be performed to ii) These valves close within the I demonstrate that remotely following times after receipt of an I operated SGS isolation valves actuation signal: 1 SGS-V027A/B, V040A/B,
! V057A/B, V250A/B close within V027A/B < 44 sec l the required response times. V040A/B, V057A/B < 5 sec j l V250A/B < 5 sec !
q U 2.2.4-19 3 WBStingh0llSB o:\lTAACSvev4Vt020204.wpf:1 b-040298
Certified Design Materi:1
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STEAM GENERATOR SYSTEM == Revision: 4 = Effective: 4/6/98 Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 12.a) "Ihe motor-operated valves i) Tests or type tests of motor- 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 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 l motor-operated valves are bounded the tests or type tests. by the tests or type tests. I iii) Tests of the as-installed motor- iii) Each motor-operated valve i operated valves will be performed changes position as indicated in j l under pre-operational flow, Table 2.2.4-1 under pre- i I differential pressure, and operational test conditions. I temperature conditions. 12.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 2.2.4-1 of loss of motive power. in Table 2.2.4-1 assumes the l assume the indicated loss of indicated loss of motive power l motive power position. position. f I O' 2.2.4-20 Westfrighouse oNTAACS\rev4Vt020204.wpf:1 b-040298
Certified Design Material STEAM GENERATOR SYSTEM ; t" rw Revision: 4 E (m./) Effective: 4/6/98 I Table 2.2.4 S I Component Name Tag No. Component Location l Main Steam Line Isolation Valve SGS-PL-V040A Auxiliary Building i Main Steam Line Isolation Valve SGS-PL-V040B Auxiliary Building i Main Feedwater Isolation Valve SGS-PL-V057A Auxiliary Building l Main Feedwater Isolation Valve SGS-PL-V057B Auxiliary Building l Main Feedwater Control Valve SGS-PL-V250A Auxiliary Building i Main Feedwater Control Valve SGS-PL-V250B Auxiliary Building i Turbine Stop Valves MTS-PL-V001 A Turbine Building i MTS-PL-V001B 1 MTS-PL-V003A I MTS-PL-V003B I Turbine Control Valves MTS-PL-V002A Turbine Building i MTS-PL-V002B i MTS-PL-V004A gw l MTS-PL-V004B i Main Feedwater Pumps FWS-MP-01 A Turbine Building i FWS-MP-01B i Feedwater Booster Pumps FWS-MP-02A Turbine Building i FWS-MP-02B 1 /m1 V 2.2.4-21 3 Westinghouse oNTAACSVevWt020204 wpm 604W98
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Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM = Revision: 4 f}
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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 I the surrounding areas whenever ac power is not available to operate the nuclear island nonradioactive I ventilation system (VBS) or high radioactivity is detected in the MCR air supply. (See CDM ; i Section 3.5 for Radiation Monitoring). The VES also limits the heatup of the MCR, the j instrumentation and control (I&C) equipment rooms, and the Class IE de equipment rooms by using { the heat capacity of surrounding structures. l The VES is as shown in Figure 2.2.5-1 and the component locations of the VES are as shown in I Table 2.2.5-6. I 1. The functional arrangement of the VES is as described in the Design Description of this l 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 b) The piping identified in Table 2.2.5-2 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 2.2.5-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.2.5-2 as ASME Code Section III meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.2.5-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure. !
1 b) The piping identified in Table 2.2.5-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure. I 5. a) The seismic Category I equipment identified in Table 2.2.5-1 can withstand seismic design basis loads without loss of safety function. I b) Each of the lines identified in Table 2.2.5-2 for which functional capability is required is I designed to withstand combined normal and seismic design basis loads without a loss ofits I functional capability. [ v 2.2.5-1 Y W85tingh00S8 o%p600VTAACSvev4Nt0202o5.wpt040298
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM = Revision: 4 EE Effective: 4/6/98 _ l 6. a) The Class 1E components identified in Table 2.2.5-1 are powered from their respective Class IE division. b) Separation is provided between VES Class IE divisions, and between Class IE divisions and non-Class 1E cable. I 7. The VES provides the following safety-related functions: a) The 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 respect to the surrounding areas. c) The 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. I 8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR. I 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 2.2.51 as having protection and safety monitoring system (PMS) control perfonn their active safety function after receiving a signal from the PMS. I 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. I 11. Displays of the parameters identified in Table 2.2.5-3 can be retrieved in the MCR. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.2.5-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the VES. l 2.2.5-2 W Westinghouse espeoouTAAesvev4Vto2o2o5.wpf:o4o298
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Certified Design Material l MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM - l Revision: 4 - e l Effective: 4/6/98 _ 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-PL-022B Yes Yes Table 2.2.5-3 Equipment Tag No. Display I Air Storage Tank Pressure VES-001A Yes i Air Storage Tank Pressure VES-001B Yes Table 2.2.5-4 i Heat Load 0 to 24 Houn Heat Load 24 to 72 Room Name Room Numbers (Bru/s) Hours (Btu /s) l MCR Envelope 12401 12.8 (hour 0 through 3) 3.9 1 5.1 (hour 4 through 24) l I&C Rooms 12301, 12305 8.8 0 I I&C Rooms 12302,12304 13.0 4.2 1 de Equipment Rooms 12201, 12205 3.7 (hour 0 through 1) 0 1 2.4 (hour 2 through 24) I de Equipment Rooms 12203,12207 5.8 (hour 0 through 1) 2.0 1 4.5 (hour 2 through 24) l l O 2.2.5-8 W8@0M o:\ap600VTAACSvev4\it020205.wpf:040398
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM #5 x
~'i Revision: 4 '
E (Q Effective: 4/6/98 _ Table 2.2.5 5 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 VES conforms with I the VES is as described in the will be performed. the functional arrangement I Design Description of this described in the Design l Section 2.2.5. Description of this Section 2.2.5.
2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.2.5-1 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 2.2.5-1 as ASME Code ASME Code Section III Section III. requirements. 2.b) The piping identified in Inspection will be conducted of 'Ihe ASME Code Section III Table 2.2.5-2 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 constructed in accordance with Table 2.2.5-2 as ASME Code ASME Code Section III Section III. requirements. [9 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 2.2.5-1 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 2.2.5-2 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.a) The components identified in A hydrostatic test will be A report exists and concludes that Table 2.2.5-1 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 2.2.5-1 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 2.2.5-2 as ASME Code performed on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code Section 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 p Section III. (Jl 2.2.5-9 [ W8Stiflgh0tlS8 oMp600VTAACSVev4Vt020205.wpf:040298
I l I Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM Revision: 4 5 I Effective: 4/6/98 Table 2.2.5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria I 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 2.2.5-1 can withstand Category I equipment and valves Table 2.2.5-1 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 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 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that i in Table 2.2.5-2 for which the existence of a report each of the as-built lines identified I functional capability is required is verifying that the as-built piping in Table 2.2.5-2 for which I designed to withstand combined meets the requirements for functional capability is required I normal and seismic design basis functional capability. meets the requirements for l loads without a loss of its functional capability. I functional capability. I 6.a) "Ihe Class IE components Testing will be performed by A simulated test signal exists at identified in Table 2.2.5-1 are providing a simulated test signal the Class IE equipment identified powered from their respective in each Class IE division. in Table 2.2.5-1 when the assigned Class IE division. Class IE division is provided the test signal. I 6.b) Separation is provided See Cenified Design Material, See Certified Design Material, between VES Class IE divisions. Section 33, Nuclear Island Section 33, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. O 2.2.5-10 W85tirigh0llSB o:Napsoo\lTAACSirev4%it020205.wpf:040298
l Certified De2ign Material l l MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM - l [T Revision: 4 E V Effective: 4Kd98 Table 2.2.5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 7.a) The VES provides a 72-hour i) Testing will be performed to i) The air flow rate from the VES 1 supply of breathable quality air confirm that the required amount is a: least 60 scfm and not more j i for the occupants of the MCR. of air flow is delivered to the than 70 scfm. j MCR. ii) The calculated storage capacity I ii) Analysis of storage capacity is greater than or equal to I will be performed based on as- 314,132 sef. built manufacturers data. I iii) MCR air samples will be iii) Air quality analysis indicates I taken during VES testing and that breathable quality air is I analyzed for quality. supplied from the VES. I 7.b) The VES maintains the i) Testing will be performed The MCR pressure boundary is i MCR pressure boundary at a with VES flowrate between 60 pressurized to greater than or equal l positive pressure with respect to and 70 scfm to confirm that the to 1/8-in. water gauge with respect the surrounding areas. MCR is capable of maintaining to the surrounding area. ['w,/j the required pressurization of the pressure boundary. I ii) Air leakage into the MCR ii) Analysis of air leakage I will be measured during VES measurements indicate that VES I testing using a tracer gas. operation limits MCR air 1 infiltration consistent with operator i dose analysis. I 1 p
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2.2.5-11 , WO5ti@00SB o:\ap600\lTAACSirev4 Tit 020205.wpf:040298 I l
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM - - Revision: 4 - Z Effective: 4/6/98 1 . et Table 2.2.5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 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 lE de equipment from as-built equipment within identified in Table 2.2.5-4 are less I rooms are within design basis the rooms identified in than or equal to the specified I assumptions to limit the heatup of Table 2.2.5-4 are less than or va'ues or that an analysis report I the rooms identified in equal to the design basis exists that concludes: Table 2.2.5-4. assumptions I - The temperature and humidity I in the MCR remain within I limits for reliable human i performance for the 72-hour period.
- The maximum temperature for the 72-hour period for the I&C
, rooms is less than or equal to 125*F.
- The maximum temperature for the 72-hour period for the Class IE de equipment rooms is less than or equal to 125*F.
I 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. I 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 2.2.5-1 to perform their active functions. the controls in the MCR. perform their active safety functions. I 9.b) The valves identified in Testing will be performed on The remotely operated valves Table 2.2.5-1 as having PMS remotely operated valves listed identified in Table 2.2.5-1 as control perform their active safety in Table 2.2.51 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. I 10. After loss of motive power, Testing of the installed valves After loss of motive power, each the remotely operated vahes 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 W85tirighotise oMp600VTAACSvev4Vt020205.wpf:040298
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM "r (~N Revision: 4 - E (j Effective: 4/6/98 1 .ee Table 2.2.5-5 (cont.) Inspections, Tests, Ari ses, f 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 retrieved in the MCR. in the MCR. the MCR. tO V n 2.2.5-13 3 Westinghotise o:WOOVTAACSVev4Vt020205.wpt040298 l
Certified Design Material MAIN CONTROL ROOM EMERGENCY HAB:TABILITY SYSTEM C 32 Revision: 4 = E Effective: 4/6/98 1 .et I Table 2.2.5-6 i Component Name Tag Number Component Location I Emergency Air Storage Tank 01 VES-MT-01 Auxiliary Building i Emergency Air Storage Tae 02 VES-MT-02 Auxiliary Building i Emergency Air Storage '.aix 03 VES-MT-03 Auxiliary Building l Emergency Air Storage Tank 04 VES-MT-04 Auxiliary Building i Emergency Air Storsge Tank 05 VES-MT-05 Auxiliary Euilding i Emergency Air Storage Tank 06 VES-MT-06 Auxiliary Building i Emergency Air Storage Tank 07 VES-MT-07 Auxiliary Building l Emergency Air Storage Tank 08 VES-MT-08 Auxiliary Building i Emergency Air Storage Tank 09 VES-MT-09 Auxiliary Building i Emergency Air Storage Tank 10 VES-MT-10 Auxiliary Building i Emergency Air Storage Tank 11 VES-MT-ll Auxiliary Building l l Emergency Air Storage Tank 12 VES-MT-12 Auxiliary Building i Emergency Air Storage Tank 13 VES-MT-13 Auxiliary Building i Emergency Air Storage Tank 14 VES-MT-14 Auxiliary Building i i Emergency Air Storage Tank 15 VES-MT-15 Auxiliary Building l l Emergency Air Storage Tank 16 VES-MT-16 Auxiliary Building i
! Emergency Air Storage Tank 17 VES MT-17 Auxiliary Building i Emergency Air Storage Tank 18 VES-MT-18 Auxiliary Building i Emergency Air Storage Tank 19 VES-MT-19 Auxiliary Building I Emergency Air Storage Tank 20 VES-MT-20 Auxiliary Building i Emergency Air Storage Tank 21 VES-MT-21 Auxiliary Building i Emergency Air Storage Tank 22 VES-MT-22 Auxiliary Building i Emergency Air Storage Tank 23 VES-MT-23 Auxiliary Building i Emergency Air Storage Tank 24 VES-MT-24 Auxiliary Building i Emergency Air Storage Tank 25 VES-MT-25 Auxiliary Building l Emergency Air Storage Tank 26 VES-MT-26 Auxiliary Building I Smergency Air Storage Tank 27 VES-MT-27 Auxilinry Building i Emergency Air Storage Tank 28 VES-MT-28 Auxiliary Building 2.2.5-14
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Certified Design Materi::l MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM - Revision: 4 " (~~} \j Effective: 4/6/98
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I Table 2.2.5 6 (cont.) l l l Component Name Tag Number Component Location i Emergency Air Storage Tank 29 VES-MT-29 Auxiliary Building i Emergency Air Storage Tank 30 VES-MT-30 Auxiliary Building i Emergency Air Storage Tank 31 VES-MT-31 Auxiliary Building i Emergency Air Storage Tank 32 VES-MT-32 Auxilie-v Building l l 1 l n U /- ( l \_/ 2.2.5-15 [ W85tingh0LIS8 c:\ap600\lTAACSirev4\it020205 wpf:040298
Certified Design Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM =t: .= Revision: 4 E i Effective: 4/6/98 _ I l E I vt3-M-Bec44 C 'R #0p i vts-M-vsefa 3 3eaGE 5 vil m' gi teeltw g vis-N-Il00 5 v[1-WS-016 , vil-%-varts m-0_0_0_Q I'- d - d d - d -
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Certified Design Material COMPONENT COOLING WATER SYSTEM y = ._ Revision: 4 f3 5 ' ( ) Effective: 4/6/98 w' 1 *.et 2.3.1 Component Cooling Water System Design Description The component cooling water system (CCS) removes heat from various plant components and I transfers this heat to the service water system (SWS) during normal modes of plant operation I including power generation, shutdown and refueling. The CCS has two pumps and two heat I exchangers. I The CCS is as shown in Figure 2.3.1-1 and the CCS component locations are as shown in i Table 2.3.1-3. I 1. The functional arrangement of the CCS is as described in the Design Description of this l 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.
b 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. l l 1 j I I ( i G' 2.3.1 1 We5drigh0USB 0:\lT AACS\rev4\it020301.wpf.1 b-o40398
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l COMPONENT COOLING WATER SYSTEM - l Revision: 4 s Effective: 4/6/98 .
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Table 2.3.1 1 Equipment Name Tag No. Display Control Function I CCS Pump A CCS-MP-01 A Yes Start (Run Status) l CCS Pump B CCS-MP-01B 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) V Note: Dash (-) indicates not appix:able. I l O 2.3.12 W Westinghouse o:VTAACS\rev4Mt020301.wpt1t>C33098
Certified Design Material COMPONENT COOLING WATER SYSTEM ~. T (p v
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Revision: 4 Effective: 4/6/98 9
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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 I the CCS is as described in the will be performed. the functional arrangement i Design Description of this described in the Design l Section 2.3.1. Description of this Section 2.3.1.
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- 2. The CCS preserves containment See Certified Design Material, See Cenified 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 1 nonsafety-related functions of the existence of a report that that the UA of each CCS heat k 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. modes of operation to the SWS. ii) Testing vill be performed to ii) Each pump of the CCS can confirm that the CCS can provide provide at least 2520 gpm of cooling water to the RNS HXs cooling water to one RNS HX while providing cooling water to and at least 720 gpm of cooling (~] Q the SFS HXs. water to one SFS HX while providing at least 1160 gpm to other users of cooling water.
- 4. Controls exist in the MCR to Testing will be performed to Controls in the MCR operate to cause the pumps identified in actuate the pumps identified in cause pumps listed in 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.
l
- 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 1 i O 2.3.1-3 [ WBSilligh0LISO o:VT AACSvev4Vt020301.wpf:1 t>-033198
g.- Certified Design Material COMPONENT COOLING WATER SYSTEM EEEEEJI Revision: 4 - E Effective: 4/6/98 I Table 2.3.13 i Component Name Tag No. Component Location l CCS Pump A CCS-MP-01A Turbine Building i CCS Pump B CCS-MP-01B Turbine Building I CCS Heat Exchanger A CCS-ME-OlA Turbine Building l CCS Heat Exchanger B CCS-ME-01B Turbine Building O 1 0 2.3.1-4 W Westinghouse oMAACSvevWt02030twput>433198
Certified Design Material COMPONEtJT COOLING WATER SYSTEM -+-- p Revision: 4 E li ( Effective: 4/6/98 . ,,, 1 SWS r-------- , - 4
! $ LETDOWN HXl ( gO f,7# t$3 - lj !!: --
3 [' _d."$0T Mx.____j CCS HEAT EXCMANCER A CCS-ME- 01 A p , CCS-MP-01 A ! p SWS fa !
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CCS HEAT EXC NGER B CCS-ME-018 C05 PUMP B CCS-vP-018 (D
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Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM E ( Revision: 4 l C]/ Effective: 4Rd98 2.3.2 Chemical and Volume Control System Design Description I The chemical and volume control system (CVS) provides reactor coolant system (RCS) purification, i RCS inventory control and makeup, chemical shim and chemical control, and oxygen control, and I provides for auxiliary pressurizer spray. The CVS performs these functions during normal modes of I operation including power generation and shutdown. 1 I The CVS is as shown in Figure 2.3.2-1 and the component locations of the CVS are as shown in i Table 2.3.2-5. I 1. The functional arrangement of the CVS is as described in the Design Description of this I Section 2.3.2.
- 2. a) The components identified in Table 2.3.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.2-2 as ASME Code Section III is designed and constmeted in accordance with ASME Code Section III requirements. ['v 3. a) Pressure boundary welds in components identified in Table 2.3.2-1 as ASME Code Section III meet ASME Code Section III requirements. b) Pressure boundary welds in piping identified in Table 2.3.2-2 as ASME Code Section III meet j ASME Code Section III requirements.
- 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.
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.
I 6. a) The Class 1E 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 design basis accident without loss of safety function for the time required to perform the safety function.
- b) The Class 1E components identified in Table 2.3.2-1 are powered from their respective Class 1E division.
1 v l 2.3.2-1 W65tiflgt10llSe eNTAACSvev&Jt02o3o2.wpf:1 b-040398
Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM Revision: 4 Effective: 4/6/98 c) Separation is provided between CVS Class IE divisions, and between Class IE divisions and non-Class IE cable. I 7. The 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 demineralized water from the RCS. c) The CVS provides isolation of makeup to the RCS. I 8. The CVS provides the following nonsafety-related functions: a) The CVS provides makeup water to the RCS. I b) The CVS provides to the pressurizer auxiliary spray. I 9. Safety-related displays in Table 2.3.2-1 can be retrieved in the main control room (MCR). I 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.3.2-1 to perfonn 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. I 11. a) The motor-operated and check valves identified in Table 2.3.2-1 perform an active safety-related function 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. 1 1 12. a) Controls exist in the MCR to cause the pumps identified in Table 2.3.2-3 to perform the listed function. I b) The pumps identified in Table 2.3.2-3 start after receiving a signal from the PLS. I 13. Displays of the parameters identified in Table 2.3.2-3 can be retrieved in the MCR. I 14. The non-safety related piping located inside containment and designated as reactor coolant pressure i boundary, as identified in Table 2.3.2-2 (pipe lines with *No" in the ASME Code column), has i been designed to withstand a seismic design basis event and maintain structural integrity. O 2.3.2-2 [ WBStilighouse a:vTAAcsvev49to20ao2.wpt:1 o.o40398
l Certified De2ign Mitirl;l l l CHEMICAL AND VOLUME CONTROL SYSTEM 2 O Revision: 4 E Q Effective: 4/6/98 Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.2-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the CVS. O 4 i O 3 WC5tifigh0US8 o:\!TAACSVev4WO20302.wpf;1 9
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Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM !==
== /N Revision: 4 =
() Effective: 4/6/98 Taale 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 I CVS Supply Line to Regercrative Heat BBD LO02 No l Exchanger 1 CVS Return Line from Regenerative Heat BBD L018 No l Exchanger BBD LO73 No I CVS Line from Regenerative Heat Exchanger to BBD LOO 3 No I Letdown Heat Exchanger BBD LO72 No i CVS Lines from Letdown Heat Exchanger to BBD LOO 4 No I Demin. Tanks BBD LOOS No I CVS Lines from Demin Tanks to RC Filters BBD LO20 No I BBD LO21 No p I i BBD LO22 No I BBD LO29 No I BBD LO37 No I CVS Lines from RC Filters to Regenerative BBD LO30 No l Heat Exchanger BBD LO31 No i BBD LO34 No i CVS Resin Fill Lines to Demin. Tanks BBD LOO 8 No I BBD L013 No l BBD LO25 No l (% N. E 2.3.2-7 [ W85tlDgh00S8 o:VTAACSVev4Vt020302.wpt:1 b-040398 i
Certified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM == j
'?,4 Vision: 4 j Effective: 4/6/98 .
l Table 2.3.2 3 Control Equipment Tag No. Display Function i CVS Makeup Pump A CVS-MP-01 A Yes Start (Run Status) i CVS Makeup Pump B CVS-MP-01B Yes Start (Run Status) Letdown Flow Sensor CVS-001 Yes - Letdown Flow Sensor CVS-025 Yes - CVS Purification Return Lire (Position CVS-PL-V081 Yes - Indicator) Auxiliary Spray Line Ist lation Valve CVS-PL-V084 Yes - (Position Indicator) Boric Acid Tank Level Sensor CVS-109 Yes - Boric Acid Flow Sensor CVS-Il5 Yes - Makeup Blend Valve (Position Indicator) CVS-PL-VI15 Yes - CVS Demineralized Water Isolation Valve CVS-PL-136A Yes - (Position Indicator) CVS Demineralized Water Isolation Valve CVS-PL-136B Yes - (Position Indicator) Makeup Pump Discharge Flow Sensor CVS-157 Y<; - Makeup Flow Control Valve (Position CVS-PL-V157 Yes - Indicator) Note: Dash (-) indicates not applicable. O 2.3.2-8 [ WBStingh0USB o:VTAACSVev4Vt020302.wpf:1t> 040398
l l l Certified Design Material CHEMICAL AND VOLUME CONTFIOL SYSTEM - O Revision: 4 - l kj Effective: 4/6/98 Table 2.3.2 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 CVS conforms with I the CVS is as described in the will be performed, the functional arrangement as l Design Description of this described in the Design i Section 2.3.2. Description of this Section 2.3.2 2.a) The components identified Inspection will be conducted of The 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 Section III are designed and documented in the ASME design components identified in constructed in accordance with reports. Table 2.3.2-I 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 2.3.2-2 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 2.3.2-2 constructed in accordance with reports. as ASME Code Section III. ASME Code Section III requirements. j k 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 2.3.2-1 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 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 2.3.2-2 pressure boundary welds will be the ASME Code Section III l as ASME Code Section III meet performed in accordance with requirements are met for non- I ASME Code Section III the ASME Code Section III. destructive examination of pressure requirements. boundary welds. 4.a) The components identified A hydrostatic test will be A report exists and concludes that i 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. (d\ 2.3.2-9 [ W8StingflotlSB oNTAACS\rev4Mt020302.wpt1 b-040398
1 Certified De:Ign Material 1 l CHEMICAL AND VOLUME CONTROL SYSTEM .:= Revision: 4 - Effective: 4H/98 . I E Table 2.3.2 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria E Design Comraitment 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 II' 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 equipmnt 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 en the seismic design basis loads in Table 2.3.2-1 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 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. l 6.a) lhe 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 q.talified 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 c:tist 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. I 6.b) The 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 lE division is provided the test signal. O 2.3.2-10 W_ WBSilligh0llSe o:VTAACS\rev4\it020302.wpt:1 t>-040398
Certified Design Materi:1 I CHEMICAL AND VOLUME CONTROL SYSTEM = r~N () Revision: 4 Effective: 4/6/98 Table 2.3.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 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. I 7.a) The CVS preserves See Certified Design Material, See Cenified 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. I 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 RCS. I 7.c) The CVS provides isolation See item 10b in this table. See item 10b in this table. I of makeup to the RCS. I 8.a) The CVS provides makeup i) Testing will be performed by i) Each CVS makeup pump ks 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. makeup flow to the RCS at pressure greater than or equ.al 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 botic 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 j and the tank overflow. I 8.b) The CVS provides the Testing will be performed by Each CVS makeup pump provides I 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. 10 2.3.2-11 W85tingh0USB oNTAACsvev4\ito20302.wpt:1t> 040398
Certified Design MCterial CHEMICAL AND VOLUME CONTROL SYSTEM == Revision: 4 - Effective: 4/6/98 Table 2.3.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 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 2.3.21 can be retrieved in retrieved in the MCR. displays in the MCR. the MCR. I 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. I 10.b) The valves identified in i) Testing will be performed i) The valves identified in Table 2.3.2-1 as having PMS using 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 the PMS. receiving a signal from the PMS. I ii) Testing will be performed to ii) These valves close within the I demonstrate that the remotely following times after receipt of an I operated CVS isolation valves actuation signal: 1 CVS-V090, V091, V136A/B 1 close within the required V090,V091 < 10 see I response time. Vl36A/B < 20 see 1 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 repon exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are t>ounded by the tests or motor-operated valves are type tests. bounded by the tested conditions. O 2.3.2-12 [ WB5tiflgh00SB oTTAACS\rev4Vt020302.wpf:1 b-040398
i Cettified Design Material CHEMICAL AND VOLUME CONTROL SYSTEM L. = A Revision: 4 - E (JI Effective: 4/6/98 Table 2.3 2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l iii) Tests of the as-installed iii) Each motor-operated valve i motor-operated valves will be changes position as indicated in i performed under pre-operational Table 2.3.2-1 under pre-operational I flow, differential pressure, and test conditions. I temperature conditions. I I iv) Exercise testing of the check iv) Each check valve changes i valves with active safety position as indicated in I functions identified in Table 2.3.2-1. i i Table 2.3.2-1 will be performed I under pre-operational test I pressure, temperature and fluid I flow conditions. I ll.b) After loss of motive power, Testing of the installed valves Upon loss of motive power, each the remotely operated valves will be performed un.ier the remotely operated valve identified identified in Table 2.3.2-1 assume conditions of loss of motive in Table 1.3.2-1 assumes the the indicated loss of motive power. indicated loss of motive power I power position. ( 3 position. LJ l 12.a) Controls exist in the MCR Testing will be perforrned 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. listed function, the MCR. I 12.b) The pumps identified in Testing will be performed to The pumps identified in l l Table 2.3.2-3 stan after receiving confirm starting of the pumps Table 2.3.2-2 start after a signal is , I a signal from the PLS. identified in Table 2.3.2-3. generated by the PLS.
]
I 13. Displays of the parameters Inspection will be performed for Displays identified in Table 2.3.2-3 I identified in Table 2.3.2-3 can be retrievability of tb displays can be retrieved in the MCR. retrieved in the MCR. identified in Tab!c 2.3.2-3 in the MCR. I 14. The non-safety related piping Inspection will be conducted of The CVS Seismic Analysis I located inside containment and the as-built components as Reports exist for the non-safety I designated as reactor coolant documented in the CVS Seismic related piping located inside I pressure boundary, as identified Analysis Report. containment and designated as ! I in Table 2.3.2-2, has been reactor coolant pressure boundary I designed to withstand a seismic as identified in Table 2.3.2 2.
- I design basis event and maintain j i structural integrity.
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l 2.3.2-13 WB5dly,t10LISS o:VTAACSVev4Vt020302.wpt:1 tr040398
Certified Design Material
=
CHEMICAL AND VOLUME CONTROL SYSTEM l Revision: 4 E I Effective: 4/6/98 l Table 2.3.2-5 I Component Name Tag No. Component Location l CVS Makeup Pump A CVS-MP-01 A Auxiliary Building i CVS Makeup Pump B CVS-MP-OlB Auxiliary Building l Boric Acid Tank CVS-MT-02 Yard i Regenerative Heat Exchanger CVS-ME-01 Containment i Letdown Heat Exchanger CVS-ME-02 Containment i Mixed Bed Demineralizer A CVS-MV-OlA Containment 1 Mixed Bed Demineralizer B CVS-MV-OlB Containment I Cation Bed Demineralizer CVS-MV-02 Containment i Reactor Coolant Filter A CVS MV-03A Containment l Reactor Coolant Filter B CVS-MV-03B Containment O l 9 2.3.2-14 [ W85tingh00S8 o:\lTAACS\rev4\it020302.wpt:1tr040398
Certified De:Ign Mat: rial CHEMICAL AND VOLUME CONTROL SYSTEM -- " (p) Revision: 4 Effective: 4/6/98 I l ml u I! os11l 3: 11l t il ll 1 il ?e I'd " j!!' i "gl' 8 18 .. _ g:fl3gEIdl8 gel
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1 IlI ' 38! g l lI l Figure 2.3.2-1 l l Chemical and Volume Control System 2.3.2-15 W WB5tiflgh00S8 o:VTAACSVev4Vt020302.wpf:1 b-040398
Certified Design Materi:1 STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM =
=
j Q Revision: 4 E
> Effective: 4/6/98 2.3.3 Standby Diesel and Auxiliary Boiler Fuel Oil System Design Description I The standby diesel and auxiliary boiler fuel oil system (DOS) supplies diesel fuel oil for the onsite I standby power system. The diesel fuel oil is supplied by two above-ground fuel oil storage tanks.
I ne DOS also provides fuel oil for the ancillary diesel generators. A single fuel oil storage tank i services both ancillary diesel generators. I The DOS is as shown in Figure 2.3.3-1 and the component locations of the DOS are as shown in I Table 2.3.3-3. I 1. The functional arrangement of the DOS is as described in the Design Description of this i Section 2.3.3. I 2. The ancillary diesel generator fuel tank can withstand a seismic event. I 3. The DOS provides the following nonsafety-related functions: I a) Each fuel oil storage tank provides for at least 7 days of continuous operation of the associated _ standby diesel generator.
/T U l b) Each fuel oil day tank provides for at least four hours of continuous operation of the I associated standby diesel engine generator.
I c) The fuel oil flow rate to the day tank of each standby diesel generator provides for continuous operation of the associated diesel generator. I d) The ancillary diesel generator fuel tank is sized to supply power to long-term safety-related I post-accident monitoring loads and control room lighting through a regulating transformer and l 1 one PCS recirculation pump for a period of 4 days. l 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. ' l 5. Displays of the parameters identified in Table 2.7 3-1 can be retrieved in the MCR. l Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.3-2 specifies the inspections, tests, analyses, and associated acceptance criteda for the DOS. f D 2.3.3-1 W85tiflgh0USB o:VTAACSvev4Vt020303.wpf:1 t>-040198
I Certified Design Material l l STANDBY DIESEL AND AUX LIARY BOILER FUEL OIL SYSTEM "~~~~"[ Revision: 4 E l i Effective: 4/6/98 . 4 Table 2.3.3-1 Control j l Equipment Name Tag No. Display Function 1 Diesel Fuel Oil Pump 1 A (Motor) DOS-MP-01 A Yes Stan (Run Status) Diesel Fuel Oil Purnp IB (Motor) DOS-MP-OlB Yes Start (Run Status) Diesel Generator Fuel Oil Day Tank A Level DOS-016A Yes - Diesel Generator Fuel Oil Day Tank B Level DOS-016B Yes - Note: Dash (-) indicates not applicabic. e l el
- 2.3.3-2 W6Mi @ USB o:\lTAACS\rev4Nt020303.wpf:1 tr040198 l
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f l l Certified De:ign Material i STANDBY DIESEL AND AUXlLIARY BOILER FUEL OIL SYSTEM - HE 1
/m Revision: 4 ~
l I, ) Effective: 4/6/98 Table 2.3.3-2 Inspections, Tests, Analyses, and Acceptance Criteria f Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built DOS conforms with the !
I the DOS is as described in the will be performed. functional arrangement described in ) I Design Description of this the Design Description of this l 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 j l fuel tank can withstand a seismic the existence of a report verifying the as-installed m try diesel I l event. that the as-installed ancillary generator fuel tank and its I diesel generator fuel tank and its anchorage are designed using ; I anchorage are designed using seismic Category 11 methods and i i seismic Category Il methods and criteria. I criteria. j 3.a) Each fuel oil storage tank Inspection of each fuel oil storage The 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. (] V i l 3.b) Each fuel oil storage day tank Inspection of the fuel oil day tank provides for at least 4 hours of will be performed. The volume of each fuel oil day tank is greater than or equal to 1300 J l operation of the associated standby gallons. I diesel generator. I 3.c) The fuel 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. l generator provides for continuous operation of the associated diesel generator. I 3.d) The 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 I to long-term safety-related post performed. equal to 450 gallons. accident monitoring loads and control room lighting through a i regulating transformer and one l PCS recirculation pump for four days.
- 4. 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 2.3.3-1 using cause the components listed in Table Table 2.3.3-1 to perform the listed controls in the MCR. 2.3.3-1 to perform the listed function. functions.
l
- 5. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.3.3-1 can be retrievability of parameters in the Table 2.3.3-1 can be retrieved in the retrieved in the MCR. MCR. MCR.
O V 2.3.3-3 [ W85tiligtl0USB o NTAACSvev4Vt020303.wpf:1 t>-040198 I l
Certified Design Material STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM * ~~ Revision: 4 = Effective: 4/6/98 . s. I Table 2.3.3-3 1 Component Name Tag No. Component Location i Diesel Oil Transfer Package A DOS-MS-01 A Yard l Diesel Oil Transfer Package B DOS-MS-OlB Yard i Fuel Oil Storage Tank A DOS-MT-01A Yard l Fuel Oil Storage Tank B DOS-MT-OlB Yard l Diesel Generator A Fuel Oil Day Tank DOS-MT-02A Diesel Building l Diesel Generator B Fuel Oil Day Tank DOS-MT-02B Diesel Building l Ancillary Diesel Fuel Oil Storage Tank DOS-MT-03 Annex Building O O 2.3.3-4 Wedl@0USB o:VTAACSVev4Mt020303.wpf:1 b-040198
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Certified Design Material FIRE PROTECTION SYSTEM ~~
/^' Revision: 4 7
( Effective: 4/6/98 2.3.4 Fire Protection System Design Description i The fire protection system (FPS) detects and suppresses fires in the plant. I The FPS is as shown in Figure 2.3.4-1 and the component locations of the FPS are as showTi in i Table 2.3.4-3. I 1. The functional arrangement of the FPS is as described in the Design Description of this l Section 2.3.4.
- 2. The FPS piping identified in Figure 2.3.4-1 remains functional following a safe shutdown earthquake.
I 3. The FPS provides the efety-related function of preserving containment integrity by isolation of the FPS line penetrating the containment. I 4. The FPS provides for manual fire fighting capability in plant areas containmg equipment required for safe shutdown. 7,) 5. Displays of the parameters identified in Table 2.3.4-1 can be retrieved in the main control room
;d (MCR).
I 6. The FPS provides nonsafety-related containment spray for severe accident management. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.4-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the FPS.
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O 2.3.4-1 W85tlligh00S6 o:VT AACSvev4Vt020304.wpf:1 b-040398 1
Certified Design Material s iIRE PROTECTION SYSTEM - t' Revision: 4 Effective: 4/6/98 7 [ Table 2.3.41 Equipment Name Tag No. Display Control Function Motor driven Fire Pump FPS-MP-01A Yes (Run Status) Start I Diesel-driven Fire Pump FPS-MP-OlB Yes (Run Status) Start Jockey Pump FPS-MP-02 Yes (Run Status) Stan O' 1 O 2.3.&2 W Westinghouse o:\lT AACS\rev4\it020304.wpf:1 b-040398
1 Certified Design Material FIRE PROTECTION SYSTEM - -
/7 Flevision: 4
() Effective: 4/6/98 _ Table 2.3.4 2 Inspections, Tests, Analyses, and Acceptance Critesia Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built FPS conforms with I the FPS is as described in the will be performed. the functional arrangement i Design Description of this described in the Design i Section 2.3.4. Description of this Section 2.3.4.
- 2. 'Ihe FPS piping depicted in i) h. ection will be performed i) The piping depicted in Figure 2.3.41 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 Island. ii) A reconciliation analysis ii) The 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 canhquake, performed.
"] l 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. I 4. The FPS provides for manual i) Inspection of the passive i) The volume of the PCS tank i fire fighting capability in plant containment cooling system above the standpipe feeding the I areas containing equipment (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 ar.d when the watei for less than 75 gpm. the fire is supplied from the FCS I storage tank. w. 2.3.4 3 WC5tiflghouse ONTAACS\rev4Vt020304.wpf.i b-040398 l t
1 Certified Design Materlat FIRE PROTECTION SYSTEM = Revision: 4 Effective: 4/6/98 _ Table 2.3.4-2 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 5. Displays of the parameters Inspection will be performed for The displays 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.
I 6. The FPS provides nonsafety- Inspection of the containment The FPS has spray headers and I related containment spray for spray headers will be performed. nozzles as follows: I severe accident management. I At least 44 nozzles at plant i elevation of at least 235 feet, and 1 24 nozzles at plant elevation of at i least 250 feet. O l i ( O
- 2.3.4-4
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Certified Design Material 1 f FIRE PROTECTION SYSTEM == ==
/~ Revision: 4 =
l k ,')s Effective: 4/6/98 _ I Table 2.3.4-3 i Component Name Tag No. Location l Motor-driven Fire Pump Package FPS-MS-01 A Turbine Building I Diesel-driven Fire Pump Package FPS-MS-OlB Turbine Building i Jockey Pump FPS-MP-02 Turbine Building i Primary Fire Water Tank FPS-MT-01 A Yard i Secondary Fire Water /Clearwell Storage Tank FPS-MT-OlB Yard I Fire Pump Diesel Fuel Day Tank FPS-MT-02 Turbine Building o O l
%.J 2.3.4-5
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Certified Design Material , MECHANICAL HANDLING SYSTEM -- T.n (^\ Revision: 4 V Effective: 4/6/98 2.3.5 Mechanical Handling System Design Description l The mechanical handling system (MHS) provides for lifting heavy loads. The MHS equipment can be 1 operated during shutdown and refueling. l l The component locations of the MHS are as shown in Table 2.3.5-3.
- 1. The seismic Category I equipment identified in Table 2.3.5-1 can withstand seismic design basis l loads without loss of safety function.
l
- 2. The applicable portion of 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. I 3. The spent fuel shipping cask crane carmot move over the spent fuel pool. Inspections, Tests, Analyses, and Acceptance Criteria U Table 2.3.5-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the MHS. l l l l l
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l 2.3.5-1 [ W85tingh00S8 o:VT AACSVev4Vt020305.wpf:1 b-032798 i
Certified Design Material MECHANICAL HANDLING SYSTEM _ = _3 Revision: 4 = Effective: 4/6/98 1 *
.et Table 2.3.51 Class 1E/
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 O 2.3.5-2 3 Westinghouse o:VTAACSvevWt020305.wpf:1 t>-032798 i I
.__-__-______0
Cettified Design Material MECHANICAL HANDLING SYSTEM n. ; Revision: 4 ~ * 'r-] j Effective: 4/6/98 Table 2.3.5-2 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 2.3.5-1 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. V 2.a) The containment polar crane Load testing of the main and The crane lifts the test load, and prevents the uncontrolled auxiliary hoists that handle lowers, stops, and holds the test lowering of a heavy load. heavy loads will be performed, load with the hoist holding brakes. The test load will be at least equal to the weight of the reactor vessel head and integrated head package, but not more than 125% of the weight of the reactor vessel head and integrated head package. 2.b) The equipment hatch hoist 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 3. The spent fuel shipping cask Testing of the spent fuel The spent fuel shipping cask crane l crane cannot move over the spent shipping cask crane is does not move over the spent fuel I fuel pool. performed. pool. I O V , 1 2.3.5 3 3 Westinghouse o'\lT AACS\rev4\it020305.wpf:1 b-032798
1 Certified Design Material MECHANICAL HANDLING SYSTEM - a Revision: 4 Effective: 4/6/98 1 i Table 2.3.S-3 l Component Name Tag No. Component Location { l Containment Polar Crane MHS-MH-01 Containment l Equipment Hatch Holst MHS-MH-05 Containment l Spent Fuel Shipping Cask Crane MHS-MH-02 Auxiliary Building I 1 1 O O 2.3.5-4 3 Westinghouse oMAAOSvevWt020305.wpd t>-033098
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM i A Revision: 4 -
=
() Effective: 4/6/98 2.3.6 Normal Residual Heat Removal System The normal residual heat removal system (RNS) removes heat from the core and reactor coolant I system (RCS) and provides RCS low temperature over-pressure (LTOP) protection at reduced RCS I pressure and temperature conditions after shutdown. The RNS also pmvides a means for cooling the I in-containment refueling water storage tank (IRWST) during normal plant operation. I he RNS is as shown in Figure 2.3.6-1 and the RNS component locations are as shown in i Table 2.3.6-5. I 1. The functional arrangement of the RNS is as described in the Design Description of this I Section 2.3.6. i'
- 2. a) The components identified in Table 2.3.6-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.6-2 as ASME Code Section III is designed and constructed in accc +nce 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. I ./m U) ( b) Pressure boundary welds in piping identified in Table 2.3.6-2 as ASME Code Section III meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.3.6-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.3.6-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure. I 5. a) De seismic Category I equipment identified in Table 2.3.6-1 can withstand seismic design basis loar t without loss of safety function. I b) Each of the lines identified in Table 2.3.6-2 for which functional capability is required is i designed to withstand combined normal and seismic design basis loads without a loss ofits I functional capability. I 6. Each of the as-built lines identified in Table 2.3.6-2 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. I g 2.3.6 1 [ Westiligh0tlSe oNTAACSVev&4020306.wpf:1b-040398
Certified Design Mcterial NORMAL RESIDUAL HEAT REMOVAL SYSTEM =
~
Revision: 4 - Effective: 4/6/98
- 7. a) The Class IE equipment identified in Table 2.3.6-1 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 2.3.6-1 are powered from their respective Class IE division, c) Separation is provided between RNS Class IE divisions, and between Class IE divisions and non-Class IE cable.
- 8. The RNS provides the following safety-related functions:
a) The RNS preserves containment integrity by isolation of the RNS lines penetrating the containment. b) The RNS provides a flow path for long-term, post-accident makeup to the RCS.
- 9. The RNS provides the following nonsafety-related functions:
a) The RNS provides low temperature overpressure protection (LTOP) for the RCS during shutdown operations. b) he RNS provides heat removal from the reactor coolant during shutdown operations. l c) ne RNS provides low pressure makeup flow from the in-containment refueling water storage < tank (IRWST) to the RCS for scenarios following actuation of the automatic depressurization system (ADS). I d) The RNS provides heat removal from the in-containment refueling water storage tank.
- 10. Safety-related displays identified in Table 2.3.6-1 can be retrieved in the main control room (MCR).
I1. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions. b) The valves identified in Table 2.3.6-1 as having protection and safety monitoring system (PMS) control perform active safety functions after receiving a signal from the PMS.
- 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.
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. 2.3.6-2 WB5tiligholise a:VTAACSVev4Vt020306.wpf:1 b-o4o398 1 1
-_______._-__--__a
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM .-=. O Revision: 4 9 5 V Effective: 4/6/98 i .ee
- 13. Controls exist in the MCR to cause the pumps identified in Tabie 2.3.6-3 to perform the listed function.
- 14. Displays of the RNS parameters identified in Table 2.3.6-3 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.6-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the RNS. O O s. m 2.3.6-3 W85filigh0llS8 o:VTAACSvev4Vt0203GS.wpf;1 b-040398 I
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Certified De:ign Mat:ri:1 NORMAL RESIDUAL HEAT REMOVAL SYSTEM == Revision: 4 = (j~N,, s Effective: 4/6/98 - Table 2.3.6-3 Equipment Name Tag No. Display Control Function RNS Pump 1A (Motor) RNS-MP-OlA Yes Start (Run Status) RNS Pump 1B (Motor) RNS-MP-01B Yes Start (Run Status) RNS Flow Sensor RNS-Ol A Yes - RNS Flow Sensor RNS-OlB Yes - Nor- Dash (-) indicates not applicable. /~'N (} 2.3.6-9 j [ WBSilDgh0USB o:vTAACSvev4Vt020306.wpf:1 b-040398 1
Certified Design Material l NORMAL RESIDUAL HEAT REMOVAL SYSTEM -
= ._
Revision: 4 E Effective: 4/6/98 Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria 1 Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. He 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 I Design Description of this described in the Design l Section 2.3.6. Description of this Section 2.3.6.
2.a) The components identified Inspection will be conducted of The ASME Code Section III in Table 2.3.6-1 as ASME Code the t.s-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. requirements. 2.b) The piping identified in Inspection will be conducted of he 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 Ill. 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 til meet ASME Code the ASME Code Section III. destructive examination of pressure Section III requirements. boundary welds. I 3.b) Pressure boundary welds in Inspection of the as-built A report exists and concludes that I piping identified in Table 2.3.6-2 pressure boundary welds will be the ASME Code Section III I as ASME Code Section III meet performed in accordance with requirements are met for non-1 ASME Code Section Ill the ASME Code Section III. destructive examination of pressure I requirements. boundary welds. ; r i 4.a) The components identified A hydrostatic test 21125 psi will A report exists and concludes that I in Table 2.3.6-1 as ASME Code be performed on the 900 psi the results of the hydrostatic test of I 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 111 conform with the tested. requirements of the ASME Code p Section III. l 2.3.6-10 3 W8Stiflgh0USB o:MTAACSvev4Vt020306.wpt:1 t>-040398
T Certified De:Ign Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM ;;" 7 r' Revision: 4 = j ()N Effective: 4/6/98 _ l Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 4.b) The piping identified in Table A hydrostatic test 21125 psi will A report exists and concludes that l 2.3.6-2 as ASME Code Section III be performed on the 900 psi the results of the hydrostatic test of I 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. I 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 2.3.6-1 can withstand equipment identified in Table 2.3.6-1 is located on the seismic design basis loads without Table 2.3.6-1 is located on the Nuclear Island. loss of safety function. Nuclear Is!'and. 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. m l ( iii) Inspection will be performed iii) A report exists and concludes 1 b 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. i 5.b) Each of the lines identified in Inspection will be performed for A report exists and concludes that l Table 2.3.6-2 for which functional the existence of a report 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 I withstand combined normal and requirements for functional functional capability is required I seismic design basis loads without capability. meets the requirements for I a loss of its functional capability, functional capability. I 6. Each of the as-built lines Inspection will be performed for An LBB evaluation report 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 report or an evaluation criteria are met by the as-built RCS criteria, or an evaluation is report on the protection from piping and piping materials, or a performed of the protection from dynamic effects of a pipe break. pipe break evaluation report exists the dynamic effects of a rupture of Certified Design Material, and concludes that protection from the line. Section 3.3, Nuclear Island the dynamic effects of a line break Buildings, contains the design is provided, descriptions and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture. A 2.3.6-11 [ W85tiligholise c:\tTAACSVev4Vt020306.wpu b-040398
Certified Design Material
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NORMAL RESIDUAL HEAT REMOVAL SYSTEM t Revision: 4 Ei j Effective: 4/6/98 _ 1 Table 2.3.6 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.a) he 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 Class 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 lE 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 lE division is provided the test signal. 7.c) Separation is provided See Certified Design Material, See Cenified Design Material, between RNS 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. 8.a) ne RNS preserves See Cenified 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) The 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) The RNS provides LTOP for i) Inspections will be conducted i) The rated capacity recorded on I the RCS during shutdown on the low temperature the valve vendor code plate is not i operations. overpressure protection relief less than 555 gpm. valve to confirm that the capacity of the vendor code plate rating is greater than or equal to system relief requirements. I ii) Testing and analysis in ii) A report exists and concludes I accordance with the ASME Code that the relief valve opens at a i Section III will be performed to pressure such that the relief capacity i determine set pressure. is not less than $55 gpm at a i pressure of 621 psig. O 2.3.6-12 W85tiflgh00SB 0:VTAACSVev4Vt020306.wpf:1t>-040398 l l
Certified Design Material 1 1 NORMAL RESIDUAL HEAT REMOVAL SYSTEM -
,fq Revision: 4 Ei V Effective: 4/6/98 _
Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 9.b) The 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. I 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 j l flow through the RNS heat when the hot leg water level is at an I exchangers when the pump elevation 15.5 inches 22 inches I suction is aligned to the RCS hot above the bottom of the hot leg. leg and the discharge is aligned to l both PXS DVI lines with the RCS I at atmospheric pressure. I iii) Inspection will be performed iii) The RCS cold legs piping
,_s i of the reactor coolant loop piping. centerline is 17.5 inches 2 inches
[ ') I above the hot legs piping centerline. (/ I l iv) Inspection will be performed iv) The RNS pump suction piping I of the RNS pump suction piping. from the hot leg to the pump suction I piping low point does not form a ! I local high point (defined as an ! I upward slope with a vertical rise I greater than 3 inches). l I l v) Inspection will be performed v) The RNS suction line connected I of the RNS pump suction nozzle to the RCS is constructed from 20-I connection to the RCS hot leg. inch Schedule 160 pipe. 9.c) The RNS provides low Testing will be perfonned to Each RNS pump provides at least l 1 pressure makeup flow from the confirm that the RNS can provide 925 gpm net flow to the RCS when I IRWST to the RCS for scenarios low pressure makeup flow from the water level above the bottom of ! I 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. J 2.3.6-13 W85tiligh00SB o:\lTAACSvev6t020306.wpf:1 t>-040398
Certified Design Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM - Revision: 4 Effective: 4/6/98 i Table 2.3.6-4 (cont.) l Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 9.d) The RNS provides heat Testing will be performed to Each RNS pump provides at least I removal from the in-containment confirm that the RNS can provide 925 gpm to the IRWST. I refueling water storage tank flow through the RNS heat I (IRWST). exchangers when the pump i suction is aligned to the IP,WST l and the discharge is aligned to the 1 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 operated 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. , J l O 2.3.6-14 l [ W85tiflgh0US8 oNTAACSvev4Vt020306.wpf:1 b-040398
Certified Design Materill NORMAL RESIDUAL HEAT REMOVAL SYSTEM T' - Revision: 4
~
r3 5 V Effective: 4/6/98 1 -
. et Table 2.3.6-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 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. I iii) Tests of the as-installed iii) Each motor-operated valve 1 motor-operated valves will be changes position as indicated in I performed under preoperational Table 2.1.2-1 under preoperational I flow, differential pressure and test conditions. I temperature conditions. l iv) Exercise testing of the check iv) Each check valve changes h(~~T I valves active safety functions position as indicated in I identified in Table 2.3.6-1 will be Table 2.3.6-1. I performed under preoperational I test pressure, temperature and I 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 of loss 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. ID V 2.3.6-15 [ Westiflghouse o:VTAACSVev4Vt020306.wpf:1b-040398
Certified Design Material 1 I l NORMAL RESIDUAL HEAT REMOVAL SYSTEM **=27j I Revision: 4 i Effective: 4/6/98 ! l Table 2.3.6-5 l l Component Name Tag No. Component Location i RNS Pump A RNS-MP-Ol A Auxiliary Building i RNS Pump B RNS-MP-OlB Auxiliary Building i RNS Heat Exchanger A RNS-ME-Ol A Auxiliary Building l l RNS Heat Exchanger B RNS-ME-OlB Auxiliary Building O l l O 2.3.6-16 3 W85tingh0t!Se o:VTAACSVev4Vt020306.wpt i b-040398
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Certified De:ign Material SPENT FUEL POOL COOLING SYSTEM =_
,Q Revision: 4 V Effective: 4/6/98 2 3.7 Spent Fuel Pool Cooling System l
Design Description i The spent fuel pool cooling system (SFS) removes decay heat from the water in the spent fuel pool I and transfers the heat to the component cooling water system during normal modes of operation. 'Ihe l SFS purifies the water in the spent fuel pool, fuel transfer canal, and in-containment refueling water l l storage tank during normal modes of operation. j l The SFS is as shown in Figure 2.3.7-1 and the component locations of the SFS are as shown in l Table 2.3.7-5. I 1. The functional arrangement of the SFS is as described in the Design Description of this I Section 2.3.10.
- 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 ASME Code Section III meet ASME Code Section Ill requirements.
.m 4.. The piping identified in Table 2.3.7-2 as ASME Code Section III retains its pressure boundary V)
( integrity at its design pressure.
- 5. The seismic Category I equipment identified in Table 2.3.7-1 can withstand seismic design basis loads without loss of safety function. ;
I 6. a) The Class IE components identified in Table 2.3.7-1 are powered from their respective Class 1E division. b) Separation is provided between SFS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable. 1 7. The SFS provides the following safety-related functions: a) The SFS preserves containment integrity by isolation of the SFS lines penetrating the containment. b) The SFS provides spent fuel cooling for 7 days by boiling water in the pool and providing i makeup water from safety-related sources. I l l 8. The SFS provides the nonsafety-related function of removing spent fuel decay heat using pumped flow through a heat exchanger. O V r [ W85tingh0USB oNTAACS\rev49t020307.wpf:1 98 l
Certified Design Material i SPENT FUEL POOL COOLING SYSTEM =" Revision: 4 t Effective: 4/6/98 . l l l 9. Safety related displays identified in Table 2.3.7-1 can be retrieved in the main control room j (MCR). { 1 l 10. Controls exist in the MCR to cause the pumps identified in Table 2.3.7-3 to perform the.r listed functions. I 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 l l l O 3 Westingh00S8 o:vTAAcsvev4vto20307.wpf:1b 9 l
Certified Design Material SPENT FUEL POOL COOLING SYSTEM EE /^g Revision: 4 - () Effective: 4/6/98 Table 2.3.71 Class IE/ Seismic Qual. for Equipment Name Tag No. Cat. I liarsh 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 Number ASME Code Section III Fuel Transfer Canal Drain LO47 Yes Cask Washdown Pit Drain LO68 Yes rx Cask Loading Pit Drain LO43 Yes Transfer Branch Line L(M5 Yes Reactor Cavity Drain LO30 Yes Table 2.3.7 3 Equipment Name Tag No. Display Control Function SFS Pump 1A SFS-MP-01 A Yes Start (Run Status) SFS Pump 1B SFS-MP-01B Yes Start (Run Status) SFS Flow Sensor SFS-13A Yes - SFS Flow Sensor SFS-13B Yes - Spent Fuel Pool Temperature Sensor SFS-018 Yes - Note: Dash (-) indicates not applicable. [N ; Y 2.3.7 3 3 Westinghouse oMAACSvev4t020307.wpf;1b-040298
I . Certified Design Material l
==: =E l SPENT FUEL POOL COOLING SYSTEM Revision: 4 =E Effective: 4/6/98 _
Table 2.3.7-4 Inspections, Tests, Ana!yses, 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 I the SFS is as described in the will be performed. the functional arrangement as l Design Description of this described in the Design l Section 2.3.10. Description Portion of this l Section 2.3.10.
- 2. "Ihe piping identified in Inspection will be conducted of The ASME Code Section III Table 2.3.7-2 as ASME Code the as-built piping as documented design reports exist for the as-Section 111 is designed and in the ASME design reports. built piping identified in constructed in accordance with Table 2.3.7-2 as ASME Code ASME Code Section III Section III.
requirements.
- 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 Table 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 pressure. 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 Table 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. 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-built 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 2.3.7-4 [ W85ti!1gflot!SB o:\lTAACS\rev4\it020307.wpt.1b-040298
Certified Design Material SPENT FUEL POOL COOLING SYSTEM a-O Revision: 4 - 4 y/ Effective: 4/6/98 l Table 2.3.7-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections Tests, Analyses Acceptance Criteria i 6.a) 7he Class IE components 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 disision. the assigned Class IE division is provided the test signal. l 6.b) Separation is provided See Cenified Design Material, See Cenified Design Material, between SFS 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 7 a) The SFS preserves contain- See Cenified Design Material, See Cenified Design Material, ment integrity by isolation of the subsection 2.2.1, Containment subsection 2.2.1, Containment SFS lines penetrating the System. System. containment. I 7.b) The SFS provides spent fuel i) Inspection will be performed to i) The volume of the spent fuel cooling for 7 days by boiling verify that the spent fuel pool pool and fuel transfer canal above 73 water in the pool and providing includes a sufficient volume of the fuel and to the elevation
- ]
makeup water from safety-related sources. water. 6 feet below the operating deck is greater than or equal to 46,700 gallons. , I ii) Inspection will be performed ii) The volume of the cask f to verify the cask washdown pit washdown pit is greater than or ! includes sufficient volume of equal to 30,900 gallons. I water. f I iii) A safety-related flow path lii) See item 1 of this table. ) exists from the cask washdown pit { to the spent fuel pool. l iv) See Cenified Design Material iv) See Cenified D: sign 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. I storage tank to the spent fuel pool. 7 I
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Certified Design Material SPENT FUEL POOL COOLING SYSTEM = En Revision: 4 Effective: 4/6/98 I Table 2.3.7 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 8. The SFS provides the ;) 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 l 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.
I 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 identified in pumps identified in Table 2.3.7-3 l Table 2.3.7-3 to perform their Table 2.3.7-3 using controls in the to perform the listed functions. listed functions. MCR. I 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. I Table 2.3.7 S i 1 l Component Name Tag No. Component Location I SFS Pump A SFS-MP-Ol A Auxiliary Building l SFS Pump B SFS-MP-OlB Auxiliary Building l SFS Heat Exchanger A SFS-ME-Ol A Auxiliary Building I SFS Heat Exchanger B SFS-ME-OlB Auxiliary Building I O 2.3.7-6 3 W85tingt10tlSB 0:VTAACSvev4\it020307.wpf:1 b-040398
Certified De:Ign Material SPENT FUEL POOL COOLING SYSTEM EE i=. : s Revision: 4 9 Ei {j s Effective: 4/6/98 .
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Certified Design Material SERVICE WATER SYSTEM -- ,o Revision: 4 = I Effective: 4/6/98 (J 1 , a 2.3.8 Service Water System Design Description The service water system (SWS) transfers heat from the component cooling water heat exchangers to I the atmosphere. The SWS operates during normal modes of plant operation, including startup, power I operation (full and partial loads), cooldown, shutdown, and refueling. t I ne SWS is as shown in Figure 2.3.8-1 and the component locations of the SWS are as shown i Table 2.3.8-3. I 1. The functional arrangement of the SWS is as described in the Design Description of this i Section 2.3.8.
- 2. The SWS provides the following nonsafety-related functions:
a) The 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.
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- 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. n N,sl\ 3 Westinghouse oNTAACSVev4Vto20308.wptt> 0 98 i
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Certified Design Material SERVICE WATER SYSTEM - Revision: 4 = E Effective: 4/6/98 Table 2.3.81 Equipment Name Tag No. Display Control Function Service Water Pump A (Motor) SWS-MP-01 A Yes Start (Run Status) Service Water Pump B (Motor) SWS-MP-OlB Yes Start (Run Status) Service Water Cooling Tower Fan A (Motor) SWS-MA-01 A Yes Start (Run Status) Service Water Cooling Tower Fan B (Motor) SWS-MA-01 A Yes Stan (Run Status) Service Water Pump 1 A 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 Discharge SWS-005B Yes - Temperature Sensor Note; Dash (.) indicates not agplicable. O 2.3.8-2 [ WBStingh0t!SB o:uTAACSvev4Vt020308.wpf;b-040198
Certified Design Material SERVICE WATER SYSTEM = ~ Revision: 4 n) i v Effective: 4/6/98 5 l Table 2.3.8 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 SWS conforms with I the SWS is as described in the will be performed. the functional arrangement as l Design Description of this described in the Design 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) 'Ihe 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 Bru/hr at cell. a 80'F ambient wet bulb temperature and a cold water temperature of 88.5'F.
- 3. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to (O) cause the components ioentified in Table 2.3.8-1 to perform the li; ed components in Table 2.3.8-1 using controls in the MCR.
cause the components listed in Table 2.3.8-1 to perform the function. listed functions.
- 4. Displays of the parameters Inspection will be performed for The 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 ;;= == Revision: 4 Effective: 4Mi/98 l Ta'sle 2.3.8-3 l 1 Componerst Name Tag No. Coroponent Location i Service Water Pump A SWS-MP-01A Turbine Building or yard l Service Water Pump B SWS-MP-OlB Turbine Building or yard l Service Water Cooling Tower SWS-ME-01 Yard O I O l 2.3.8-4 3 W85tingh00SB o:VTAACSvev4Mt020308.wpt:b-040198
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Certified Design Material l j CONTAINMENT HYDROGEN CONTROL SYSTEM -- i fm Revision: 4 h t Effective: 4/6/98 i 2.3.9 Containment . Hydrogen Control System l The containment hydrogen control system (VLS) limits hydrogen gas concentration in containment I during accidents. l The VLS has catalytic hydrogen recombiners (VLS-MY-E01 A, VLS-MY-E01B, VLS-MY-E02 and i VLS-MY-E03) that are located inside containment. The VLS has hydrogen igniters located as shown I on Table 2.3.9-2. l
- 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 environmenta' 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 2.3.9-1 are powered from their respective Class IE division. c) Separation is provided between VLS Class IE divisions, and between Class IE divisions and O non-Class IE cable.
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- 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. i 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.
b) The components identified in Table 2.3.9-2 perform the listed function after receiving a i manual signal from the diverse actuation system (DAS). O V 2.3.9-1 Ndh00 o:\lTAACSvev4\it020309.wpf;1 b-o40398 1 _ _ )
Certified Dezign Miterill CONTAINMENT HYDROGEN CONTROL SYSTEM = "* Revision: 4 Effective: 4/6/98 Inspections, Tests, Analyses, and Acceptance Criteria 1 Table 2.3.9-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the VLS. O O 2.3.9-2 W85tilighouse o:\lTAACS\rev4\it020309.wpf;1 b-040398
Certified Design Material
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CONTAINMENT HYDROGEN CONTROL SYSTEM ;;; (~~} Revision: 4 5
'(f Effective: 4/6/98 Table 2.3.9-1 ASME Class IE/
Code Qual. for Safety-Section Seismic Harsh Related Equipment Name Tag No. III Cat. I Envir. Display Catalytic Hydrogen Recombiner A VLS-MY-E01 A No Yes NA/Yes - Catalytic Hydrogen Recombiner B VLS-MY-E01B No Yes NA/Yes - 1 IRWST Catalytic Hydrogen VLS-MY-E02 No Yes NA/Yes - I Recombiner l CVS Compartment Catalytic VLS-MY-E03 No Yes NA/Yes - l 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 apphcable. V O t N.s/ 2.3.9-3 3 W85tiligh00S8 o:vTAACSVev4bt020309.wpf:1 b-040398 i
Certified Design Material l CONTAINMENT HYDROGEN CONTROL SYSTEM +- 5 Revision: 4 35 l Effective: 4/6/98 1 .e Table 2.3.9-2 j l Power l Tag Group Room l Equipment Name Number Function Number Location No. l Hydrogen Igniter 01 VLS-EH-01 Energize i Tunnel connection loop compartments 112N l Hydrogen Igniter 02 VLS-EH-02 Energize 2 Tunnel connection loop compartments ll2N l Hydrogen Igniter 03 VLS-EH-03 Energize 1 Tunnel connection loop compartments 11204 I Hydrogen Igniter N VLS-EH-04 Energize 2 Tunnel connection loop compartments ll2M l Hydrogen Igniter 05 VLS EH-05 Energize 1 Loop compartment 02 11402 l Hydrogen Igniter 06 VLS-EH-06 Energize 2 Loop compartment 02 11502 l Hydrogen Igniter 07 VLS-EH-07 Energize 2 Loop compartment 02 11402 l Hydrogen Igniter 08 VLS-EH-08 Energize 1 Loop compartment 02 11502 I Hydrogen Igniter 09 VLS-EH-09 Energize 1 In-containment refueling water storage 11305 tank (IRWST) l Hydrogen Igniter 10 VLS-EH-10 Energize 2 IRWST 11305 l Hydrogen Igniter 1i VLS-EH-11 Energize 2 Loop compartment 01 11401 l Hydrogen Igniter 12 VLS-EH-12 Energize 1 Loop compartment 01 11501 l Hydrogen Igniter 13 VLS-EH 13 Energize I Loop compartment 01 11401 l Hydrogen Igniter 14 VLS-EH-14 Energize 2 Loop compartment 01 11501 i Hydrogen Igniter 15 VLS-EH-15 Energize 2 IRWST 11305 l Hydrogen Igniter 16 VLS-EH-16 Energize 1 IRWST 11305 l 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 l Hydrogen Igniter 19 VLS-EH-19 Energize 2 East valve room 11208 l Hydrogen Igniter 20 VLS-EH-20 Energize 2 Southeast accumulator room 11206 l Hydrogen Igniter 21 VLS-EH-21 Energize 1 Southeast valve room 11206 l Hydrogen Igniter 22 VLS-EH-22 Energize I Lower compartment area (core makeup 11400
!.4 try ,,,,a valve area)
I Hydrogen Igniter 23 VLS-EH-23 Energize 2 Lower compartment area (CMT and 11400 valve area) l Hydrogen Igniter 24 VLS-EH-24 Energize 2 Lower companment area (CMT and 11400 valve area) l Hydrogen Igniter 25 VLS-EH-25 Energize 2 Lower compartment area (CMT and 11400 valve area) l Hydrogen Igniter 26 VLS-EH-26 Energize 2 Lower compartment area (CMT and 11400 valve area) O 2.3.9-4 [ W8Stiligh0USB o AITAACSVev4Vt020309.wpt i b-040398
Certified Design Material CONTAINMENT HYDROGEN CONTROL SYSTEM = = p Revision: 4 s y) Effective: 4/6/98 _ Table 2.3.9 2 (cont.) Power Tag Group Room Equipment Name Number Function Number Location No. l Hydrogen Igniter 27 VLS-EH-27 Energize 1 Lower compartment area (CMT and 11400 valve area) l Hydrogen Igniter 28 VLS-EH-28 Energize 1 Lower compartment area (CMT and 11400 valve area) i Hydrogen Igniter 29 VLS-EH-29 Energize 1 Lower compartment area (CMT and 11400 valve area) l Hydrogen Igniter 30 VLS-EH-30 Energize 2 Lower compartment area (CMT and 11400 valve area) l Hydrogen Igniter 31 VLS-EH-31 Energize 1 Lower compartment area (CMT and i1400 valve area) l Hydrogen Igniter 32 VLS-EH-32 Energize 1 Lower compartment area (CMT and 11400 valve area) l Hydrogen Igniter 33 VLS EH-33 Energize 2 North CVS equipment room 11209 i l Hydrogen Igniter 34 VLS EH-34 Energize 1 North CVS equipment room i1209 O l Hydrogen Igniter 35 VLS-EH-35 Energize i IRWST 11305 V l Hydrogen Igniter 36 VLS-EH-36 Energize 2 IRWST 11305 l Hydrogen Igniter 37 VLS-EH-37 Energize 1 IRWST 11305 l Hydrogen Igniter 38 VLS EH-38 Energize 2 IRWST 11305 l Hydrogen Igniter 39 VLS-EH-39 Energize 1 Upper compartment lower region 11500 l Hydrogen Igniter 40 VLS-EH-40 Energize 2 Upper compartment lower region 11500 ! l Hydrogen Igniter 41 VLS-EH-41 Energize 2 Upper compartment lower region 11500 l l Hydrogen Igniter 42 VLS-EH-42 Energize 1 Upper compartment lower region 11500 l Hydrogen Igniter 43 VLS-EH-43 Energize i Upper compartment lower region 11500 I Hydrogen Igniter 44 VLS-EH-44 Energize i Upper compartment lower region 11500 l Hydrogen Igniter 45 VLS-EH 45 Energize 2 Upper compartment lower region 11500 l Hydrogen Igniter 46 VLS-EH-46 Energize 2 Upper compartment lower region 11500 l Hydrogen Igniter 47 VLS-EH-47 Energize 1 Upper compartment lower region 11500 1 Hydrogen Igniter 48 VLS-EH-48 Energize 2 Upper compartment lower region 11500 l Hydrogen Igniter 49 VLS-EH-49 Energize 1 Pressurizer compartment 11503 l Hydrogen Igniter 50 VLS-EH-50 Energize 2 Pressurizer compartment 11503 i Hydrogen Igniter 51 VLS-EH-51 Energize i Upper compartment mid-region i1500 l Hydrogen Igniter 52 VLS-EH-52 Energize 2 Upper compartment mid-region 11500 g l Hydrogen Igniter 53 VLS-EH-53 Energize 2 Upper compartment mid-region 11500 () .. 2.3.9-5 [ W8Stiflgh0USB o:\lTAACS\rev4\it020309.wpf:1 b-040398
I - i Certified Design Material CONTAINMENT HYDROGEN CONTROL SYSTEM --- Revision: 4 Effective: 4/6/98 _ Table 2.3.9 2 (cont.) Power Tag Group Room Equipment Name Number Function Numtwr Location No. l Hydrogen Igniter 54 VLS-EH-54 Energize 1 Upper compartment mid-region 11500 l Hydrogen Igniter 55 VLS-EH-55 Energize 1 Refueling cavity 115N l Hydrogen Igniter 56 VLS-EH-56 Energize 2 Refueling cavity 115N l Hydrogen Igniter 57 VLS-EH-57 Energize 2 Refueling cavity 11504 I Hydrogen Igniter 58 VLS-EH-58 Energize 1 Refueling cavity 11504 l Hydrogen Igniter 59 VLS-EH-59 Energize 2 Pressurizer compartment i1503 l Hydrogen Igniter 60 VLS-EH-60 Energize i Pressurizer compartment i1503 l Hydrogen Igniter 61 VLS-EH-61 Energize 1 Upper compartment-upper region 11500 l Hydrogen Igniter 62 VLS-EH-62 Energize 2 Upper compartment-upper region 11500 l Hydrogen Igniter 63 VLS-EH-63 Energize 1 Upper compartment-upper region 11500 l Hydrogen Igniter 64 VLS-EH-64 Energize 2 Upper compartment-upper region 11500 O l l 1 l 9 2.3.9-6 l W W85tiflghouse o:\lTAACS\rev4\st020309.wpf:1b-040398 l i l
Certified Design Material CONTAINMENT HYDROGEM CONTROL SYSTEM == "- p Revision: 4 5 (j Effective: 4/6/98 _ 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 2.3.9-1 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 perfonned. design basis loads without loss of safety function. iii) Inspection will be performed iii) A report exists and concludes f ar the existence of a report that the as-installed equipment j verifying that the as-installed including anchorage is seismically equipment including anchorage bounded by the tested or analyzed is seismically bounded by the conditions. O terted or analyzed conditions. L/I 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 eact 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 Cestified Design Material, See Certified Design Material, between VLS Class 1E divisions, Section 3.3, Nuclear Island Section 3.3, Nuclear Island and between Class IE divisions Buildings. Buildings. and non-Class IE cable. ,/- V 2.3.9-7 W Westinghouse o:\lTAACS\rev4\it020309.wpf:1 t>-040398
Certified Design Mair il 1 CONTAINMENT HYDROGEN CONTROL SYSTEM c.- == Revision: 4
- E Effective: 4/6/98 _
Table 2.3.9 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 3. The 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 non-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 performed. 4.b) The 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 I concentration during and elevations 150 and 175 ft and with I following a design basis accident. PAR centerline greater than 10 ft I 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 1 scfm of hydrogen at a prevailing concentration of 3 volume-percent for a test conducted at atmospheric pressure
+2 psi and an ambient temperature of 120.
O 2.3.9-8 3 Westinghouse oMAACSWV4Mt020309.wpf;1b-040398
Certified Design Material l l l CONTAINMENT HYDROGEN CONTROL SYSTEM - - (N Revision: 4 ' e i (,_) Effective: 4/6/98 _ Table 2.3.9 3 (cont.) l inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1 1 5. The VLS provides the i) Inspection for the number of i) At least 64 hydrogen igniters I nonsafety-related function to igniters will be performed. are provided inside containment at j control the containment hydrogen the locations specified in j concentration for beyond design Table 2.3.9-2. basis accidents. { J ii) Operability testing will be ii) The surface temperature of the j performed on the igniters. igniter exceeds 1700 F. j l iii) An inspection of the as-built iii) The minimum distance I containment internal structures between the primary openings l will be performed. through the ceilings of the passive l I core cooling system valve / ) I accumulator rooms (11206,11207) I and the containment shell is at I least 19 feet. Primary openings I are those that constitute 98% of the I opening area. Other openings I through the ceilings of these rooms f)T (. I must be at least 3 feet from the l containment shell. I l iv) An inspection will be iv) "Ihe discharge from each of l performed of the as-built IRWST these IRWST vents is oriented I vents that are located in the roof generally away from the I of the IRWST along the side of containment shell. I the IRWST next to the I 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. l 7.b) The components identified Testing will be performed on the The igniters energize after in Table 2.3.9-2 perform the igniters using the DAS controls. receiving a signal from DAS. l listed function after receiving l i manual a signal from DAS.
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v 2.3.9-9 WBStiflgh00S8 o NTAACS\rev4Vt020309.wpf: 1 t>040398 l l
Certified Design Material LIQUID RADWASTE SYSTEM == (3 Revision: 4 = (,/ Effective: 4/6/98 2.3.10 Liquid Radwaste System Design Description i The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater. I The WLS has components which receive and store radioactive or potentially radioactive liquid waste. 1 These are the reactor coolant drain tank, the containment sump, the effluent holdup tanks and the I waste holdup tanks. The WLS components store and process the waste during nonnal operation and I during anticipated operational occurrences. Monitoring of the liquid waste is performed prior to I discharge. I I 'Ihe WLS is as shown in Figure 2.3.10-1 and the component locations of the WLS are as shown in i Table 2.3.10-5. I 1. The functional arrangement of the WLS is as described in the Design Description of this i Section 2.3.10.
- 2. a) The components identified in Table 2.3.10-1 as ASME Code Section III are designed and n constructed in accordance with ASME Code Section III requirements.
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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 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. I 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. I b) Each of the lines identified in Table 2.3.10-2 for which functional capability is required is I designed to withstand combined normal and seismic design basis loads without a loss of its I functional capability. i
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Certified Design Material
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LIQUID RADWASTE SYSTEM
- 3 Revision: 4 Effective: 4/6/98 1 6. 'Ihe WLS provides the following safety-related functions:
a) The WLS preserves containment integrity by isolation of the WLS lines penetrating the containment. I b) Check valves in drain lines to the containment sump limit cross flooding of compartments. I 7. The WLS provides the nonsafety-related functions of: I a) Detecting leaks within containment to the containment sump. b) Controlling releases of radioactive materials in liquid effluents. I 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. I 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. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.10-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the WLS. O 2.3.10-2 3 Westinghouse o:MTAACSVev4Vm20310.wpf:1 t> 040308
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Certified Design Material LIQUID RADWASTE SYSTEM == i= Revision: 4 - E Effective: 4/6/98 , I i Table 2.3.10 2 Line Name Line No. ASME Section III Functional Capability Required WLS Drain from P75 LO62 Yes Yes Compartment A WLS Drain frr m PXS LO63 Yes Yes Companment B WLS Drain f rom CVS LO61 Yes Yes Compartmeni Table 2.3.10 3 Equipment Name Tag No. Control Function WLS Effluent Discharge Isol . son WLS-PL-V223 Close Valve O O 2.3.10-4 Westirighouse o VTAACSvev4Vt020310.wpf:1 t> 040398
Certified Design Material LIQUID RADWASTE SYSTEM == == Revision: 4 (G) Effective: 4/6/98 _ Table 2.3.I0-4 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 WLS conforms with I the WLS is as described in the will be performed. the functional arrangement as
! Design Description of this described in the Design l Section 2.3.10. Description of this Section 2.3.10.
2.a) he 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 the 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 reports exist for the as-Section III is designed and in the ASME design repons. built piping identified in constructed in accordance with Table 2.3.10-2 as ASME Code ASME Code Section III Section III. I requirements. n ( l 3.a) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that N components identified in boundary welds will be the ASME Code Section III Table 2.3.10-1 as ASME Code performed in accordance with the requirements are met for non-Section 111 meet ASME Code ASME Code Section Ill. 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 as ASME Code Section III meet performed in accordance with the requirements are met for non. ASME Code Section III ASME Code Section Ill. 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. 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 requirements of the ASME Code [3 Section III.
%_Y 2.3.10-5 W8Stiflgt10llS8 o:VTAACSVev4Vt020310.wpt i b-040398
Certified Design Material l LIQUID RAL s ASTE SYSTEM _
==
Revision: 4 = Effective: 4/6/98 Table 2.3.10-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria 1 1 Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1 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 withstand 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. l 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that I in Table 2.3.10-2 for which the existance of a report verifying each of the as-built lines I functional capability is required is that the as-built piping meets the identified in Table 2.3.10-2 for I designed to withstand combined . requirements for functional which functional capability is I normal and seismic design basis capability. required meets the requirements I loads without a loss of its for functional capability. I functional capability. I 6.a) "Ihe 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. I 6.b) Check valves in drain lines Refer to item 9 in this table. Refer to item 9 in this table. l to the containment sump limit cross flooding of compartments. O 2.3.10-6 [ Westiflgt10tlSB oNT AACSVev4Vt020310.wpf;1 b-040398
1 Certified Design Material LIQUID RADWASTE SYSTEM Z- E (7 Revision: 4 ' 5 () Effective: 4/6/98 1 . e Table 2.3.10-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria i 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 I 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 report 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. I 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 I controlling releases of radioactive radiation signal from the discharge isolation valve i materials in liquid effluents. radiation monitor, WLS-229, WLS-PL-V223 to close. causes the discharge isolation
,m valve WLS-PL-V223 to close:
I V) I 8. Controls exist in the MCR to cause the remotely operated valve Stroke testing will be performed on the remotely operated valve Controls in the MCR operate to cause the remotely operated valve I 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. I 9. The check valves identified Exercise testing of the check Each check valve changes I in Table 2.3.10-1 perform an valves with active safety functions position as indicated on I active safety-related function to identified in Table 2.3.10-1 will Table 2.3.10-1. I change position as indicated in be performed under pre-I the table. operational test pressure, I temperature and flow conditions. 1 i l 7 ( v
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2.3.10-7 NONbSO o:\lTAACSirev4\it020310.wpf;1 b-040398
Certified Design Material
==
LIQUID RADWASTE SYSTEM
- Revision: 4 Effective: 4/6/98 I Table 2.3.10-5 i Component Name Tag No. Component Location l WLS Reactor Coolant Drain Tank WLS-MT-01 Containment l WLS Containment Sump WLS-MT-02 Containment I WLS Degasifier Column WLS-MV-01 Auxiliary Building l WLS Effluent Holdup Tanks WLS-MT-05A Auxiliary Building l l WLS MT-05B I
l WLS Waste Holdup Tanks WLS-MT-06A Auxiliary Building i i WLS-MT-06B I WLS Waste Pre-Filter WLS-MV-06 Auxiliary Building l WLS lon Exchangers WLS-MV-03 Auxiliary Building l WLS-MV-04A I WLS-MV-04B l WLS-MV-04C l WLS Waste After-Filter WLS-MV-07 Auxiliary Building l WLS Monitor Tanks WLS-MT-07A Axuiliary Bundmg , 1 l WLS-MT-07B l 1 WLS-MT-07C l O 2.3.10-8 [ W8Stiligh00S6 o:VTAACSVev4Vt020310.wpf:1 b-040398
Certified Design Material LIQUID RADWASTE SYSTEM = == [) (./ Revision: 4 Effective: 4/6/98
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1 Certified Design Material 4 I SOLID RADWASTE SYSTEM l C: :
/3 Revision: 4 E' E5
(,) Effective: 4/6/98 1 - e! l 2.3.12 Solid Radwaste System 1 Design Description i The solid radwaste system (WSS) receives, collects and stores the solid radioactive wastes received j l prior to their processing and packaging by mobile equipment for shipment off-site. i l The WSS is described by the Design Commitments portion of this Section 2.3.12. l The component locations of the WSS are as shown in Table 2.3.12-2. l l 1. The functional arrangement of the WSS is as described in the Design Description of this l Section 2.3.12. I 2. The WSS provides the nonsafety-related function of storing radioactive spent resins prior to i processing or shipment. l I U,o I i
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Certified Design Material l SOLID RADWASTE SYSTEM F -~~~ Revision: 4 E Effective: 4/6/98 1 .e Table 2.3.12-1 Inspections, Tests, Analyses, and Acceptance Criteria
=m -
Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. The functional arrangement of Inspection of the as-built system The as-built WSS is as described I the WSS is as described in the will be performed. in the Design Description of this ! Design Description of this Section 2.3.12. I Section 2.3.12.
- 2. The WSS provides the Inspection will be performed to A report exists and concludes that nonsafety-related function of verify that the volume of each of the volume of each of the spent storing radioactive solids prior to the spent resin tanks, resin tanks, WSS-MV01A and I processing or shipment. WSS-MV01A and WSS-MV01B, is at least 250 ft3.
WSS-MV01B, is at least 250 ft3. l Table 2.3.12 2 l Component Name Tag No. Component Location l WSS Spent Resin Tank A WSS-MV-01 A Auxiliary Building l WSS Spent Resin Tank B WSS-MV-OlB Auxiliary Building O 1 2.3.12-2 W Westinghouse oMAACSVev4Vt020312. wpm t>-040298
Certified Design Material ! PRIMARY SAMPLING SYSTEM -
/'] Revision: 4 E
( ,/ Effective: 4/6/98 2.3.13 Primary Sampling System i The primary sampling system collects samples of fluids in the reactor coolant system (RCS) and the I containment atmosphere during normal operations and following an accident. l The PSS is as shown in Figure 2.3.13-1. I 1. 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 III are designed and constructed in accordance with ASME Code Section III requirements.
- 3. Pressure boundary welds in components identified in Table 2.3-13-1 as ASME Code Section III meet ASME Code Section III requirements.
- 4. The components identified in Table 2.3.13-1 as ASME Code Section III 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.
f' 6. a) The Class 1E equipment 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 function, for the time required to perform the safety function. I b) The Class 1E comp >nents identified in Table 2.3.13-1 are powered from their respective Class 1E division.
- c) Separation is provided between PSS Class 1E divisions, and between Class 1E divisions and non-I Class IE divisions.
l 7. The PSS provides the safety-related function of preserving containment integrity by isolation of the l PSS lines penetrating the containment.
- 8. The PSS provides the nonsafety-related function of providing the capability of obtaining post-accident reactor coolant and containment atmosphere samples.
- 9. Safety-related displays identified in Table 2.3.13-1 can be retrieved in the MCR.
- 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.
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- 11. a) The check valves identified in Table 2.3.13-1 perform an active safety-related function to change position as indicr';J 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 3 WB5tingh0llSB o:vrAACSVev&a020313.wp6:1b 9
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