ML20236Y182
| ML20236Y182 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 07/24/1998 |
| From: | Mcintyre B, Piplica E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20236Y171 | List: |
| References | |
| GW-GL-030, GW-GL-030-R06, GW-GL-30, GW-GL-30-R6, NUDOCS 9808110234 | |
| Download: ML20236Y182 (800) | |
Text
{{#Wiki_filter:, . _ _ _ _ . , _ - _ , _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ ______ __ . __ l $- L L-I-f i- .. .. .[ , CHANGE PAGE INSTRUCTIONS FOR AP600 TIER 1 MATERIAL cl l
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AP600 DOCUMENT COVER SHEET TDC: IDS: 1 S Form B8202G(5/94) AP600 CENTRAL FILE USE ONLY: 0058.FRM RFS#: RFS ITEM #: 9 AP600 DOCUMENT NO. GW-GL-030 ALTERNATE DOCUMENT NUMBER: REVISION NO. 6 Page 1 of ASSIGNED TO WORK BREAKDOWN #: 3.2.5 DESIGN AGENT ORGANIZATION: PROJECT: AP600 TITLE: AP600 Tier 1 Material ATTACHMENTS: DCP #/REV. INCORPORATED IN THIS DOCUMENT REVISION: CALCULATION / ANALYSIS
REFERENCE:
ELECTRONIC FILENAME ELECTRONIC FILE FORMAT ELECTRONIC FILE DESCRIPTION Wordperfect (C) WESTINGHOUSE ELECTRIC COMPANY 1998 WESTINGHOUSE PROPRIETARY CLASS 2 This document contains information propnetary to Wesbnghouse Electric Company; it is submitted in confidence and is to be used solely for the purpose for which it is fumished and retumed upon request. This document and sum information is not to be reproduced, transmitted, disclosed or used r,therwise in whole or in part without prior wntten authorization of Westinghouse Electric Company, Energy Systems Business Unit, subject to the legends contained hereof. O WESTINGHOUSE PROPRIETARY CLASS 2C This document is the property of and contains Proprietary information owned by Westinghouse Electric Company and/or its subcontractors and suppliers. It is transmitted to you in confidence and tr.ist, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you. WESTINGHOUSE CLASS 3 (NON PROPRIETARY) COMPLETE UNDER FOAKE. 1 IF WORK PERFORMED UNDER DESIGN CERTIFICATION Q3 COMPLETE 2 IF WORK PERFO 1 ODOE DESIGN CERTIFICATION PROGRAM - GOVERNMENT LIMITED RIGHTS STATEMENT [See page 2) Copyright statement: A license is reserved to the U.S. Govemment under corr, act DE-AC03-90SF18495. EDOE CONTRACT DELIVERABLES (DELIVERED DATA) Subject to specified exceptions, disclosure of this data is restricted until September 30,1995 or Design Certification under DOE contract DE ACO3-90SF18495, whichever is later. EPRI CONFIDENTIAL: NOTICE: 1E 2 0 3 O 4 0 s O CATEGORY: AEBDCODDEOFO 2 OARC FOAKE PROGRAM - ARC LIMITED RIGHTS STATEMENT [See page 21 Copyright statement: A heense is reserved to the U.S. Govemment under contract DE-FCO2-NE34267 and subcontract ARC-93-3-SC-001. D ARC CONTRACT DELIVERABLES (CONTRACT DATA) Subject to specified excephons, disclosure of this data is restricted under ARC Subcontract ARC-93-3-SC-001. ORIGINATOR Si ATURE/DATE E. J. Piplica /g AP600 RESPONSIBLE MANAGER
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7fy/g SIGNA URE' '
' APPROVAL DATE G 'B. A. McIntyro . , . f gf8 7/ pg Approval of tne responsible manager signifies that document is complete, all require (rWiews are complete, electronic file as attached and document is released for use.
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AP600 DOCUMENT CSVER SHEET PC9eS l Form 58202G(5/94) LIMITED RIGHTS STATEMENTS l DOE GOVERNMENT UMITED RIGHTS STATEMENT (A) These data are submitted with limited rights under govemment contract No. DE-AC03-90SF18495. These data may be reproduced and used by the govemment with the express limitation that they will not, without wntten perm,ssion of the contractor, be used for purposes of rnanuScturer nor disclosed outsice the government; except that the govemment may disclose these data outside the governr.1ent for the following purposes, if any, provided that the govemment mrakes such discinsure subject to prohibition against further use and disclosure (1) This ' Proprietary Data' may be disclosed for evaluation purpose under the restrictions above. (11) The ' Proprietary Data
- may be disclosed to the Electnc Power Research Institute (EPRI), electric utihty representatives and their direct consultants, excluding direct comrnercial compettors, and the DOE National Laboratories under the prohibitions and r9stnctions above.
(B) This notice shall be marked on any reproduction of these data, in whole or in part. ARC UMITED RIGHTS STATEMENT: This propnetary data, fumished under Subcontract Number ARC-93-3-SC-001 with ARC rnay be duphcated and used by the govemment and ARC, subject to the limitations of Article H-17.F. of that subcontract, with the express kmitations that the proonetary data may not be disclosed outside the government or ARC, or ARC's Class 1 & 3 rnembers or EPRI or be used for purposes of manufacture without prior permission of the Subcontractor, except that further disclosure or use may be rnade solely for the following purposes: This proprietary data may be disclosed to other than commercial competitors of Subcontractor for evaluation purposes of this subcontract under the restnction that the proprietary data be retained in confidence and not be further disclosed, and subject to the terms of a non-disclosure agreement between the Subcontractor and that organization, excluding DOE and its contractors. DEFINITIONS CONTRACT /DEUVERED DATA - Consists of documents (e.g. specifications, drawings, reports) which are generated under the DOE or ARC contracts which contain nc, background proprietary data. EPRI CONFIDENTIALITY / OBLIGATION NOTICES NOTICE 1: The data in this docurnent is subject to no confidentiality obligations. NOTICE 2: Tha data in this document is proprietary and confidential to Westinghouse Electnc Company and/or its Contractors. It is forwarded to recipient under an obligation of Confidence and Trust for hmited purposes only. Any use, disclosure to unauthonzed persons, or copying of this document or parts thereof is prohibited except as agreed to in advance by the Electnc Power Research Institute (EPRI) and Westinghouse Electnc Company. Recipient of this data has a duty to inquire of EPRI and/or Westinghouse as to the uses of the information containeo herein that are permitted. NOTICE 3: The data in this document is proprietary and confidential to Westinghouse Electric Company and/or its Contractors. it is forwarded to recipient under an obligaton of Confidence and Trust for use only in evaluation tasks specifically authorized by the Electnc Power Research Institute (EPRI). Any use, disclosure to unauthonzed persons, or copying this document or parts thereof is prohibited except as agreed to in advance by EPRI and Westinghouse Electric Company. Recipient of this data has a duty to inquire of EPRI and/or Westinghouse as to the uses of the information contained herein that are permitted. This document and any copies or excerpts thereof that may have been generated are to be retumed to Westinghouse, directly or through EPRI, when requested to do so. NOTICE 4: The data in this document is propnetary and confidential to Westinghouse Electric Company and/or its Contractors. It is being revealed in confidence and trust only to Employees of EPRI and to certain contractors of EPRI for hmited evaluation tasks authorized by EPRt. Any use, disclosure to unauthorized persons, or copying of this document or parts thereof is prohibited. This Document and any copies or excerpts ' hereof that may have been generated are to be retumed to Westinghouse, directly or through EPRI, when requested to do so. NOTICE The data in this document is proprietary and co,1fidential to Westinghouse Electric Company and/or its Contractors. Access to this data is gi in Confidence and Trust only at Westinghouse facilities for lirnited evaluation tasks assigned by EPRI. Any use, disclosure to unauthonzs ' persons, or copyin removed from Westinghouse fa :g of this document or parts thereof is prohibited. Neither this document nor any excerpts therefrom are hties. EPRI CONFIDENTIALITY / OBLIGATION CATEGORIES CATEGORY "A"- (See Delivered Data) Consists of CONTRACTOR Foreground Data that is contained in an issued reported. CATEGORY 'B"- (See Dehvered Data) Consists of CONTRACTOR Foreground Data that is not contained in an issued report, except for computer programs. CATEGORY *C"- Consists of CONTRACTOR Background Data except for computer programs. CATEGORY "D"- Consists of computer programs developed in the course of performing the Work. CATEGORY *E*- Consists of computer programs developed prior to the Effective Date or after the Effective Date but outside the scope of the Work. CATEGORY 7"- Consists of administrative plans and administrative reports. O
i lO l Simplified Passive Advanced Light Water Reactor Plant Program AP600 TIER 1 MATERIAL i 1 'O l Prepared for 1 U.S. Department of Energy ! ( ,$an Francisco Operations Office l l DE-AC03-90SF18495 I l i Revision 6 l 1 i July 1998 ) O
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Tier 1 M terlil TABLE OF CONTENTS s=
] Revision: 6 (V Effective: July 1998 _
TABLE OF CONTENTS Section Page LIST OF FIGURES vii 1.0 IN'IRODUCTION 1.1 Definitions 1.0-1 1.2 General Provisions 1.0-3 1.3 Figure Legend 1.0-5 1.4 List of Acronyms and Abbreviations 1.0-9 2.0 SYSTEM BASED DESIGN DESCRIPTIONS AND ITAAC 2.1 Reactor 2.1.1 Fuel Handling and Refueling System 2.1.1 -1 2.1.2 Reactor Coolant System 2.1.2-1 2.1.3 Reactor System 2.1.3-1 2.2 Nuclear Safety Systems 2.2.1 Containment System 2.2.1-1 2.2.2 Passive Containment Cooling System 2.2.2-1 2.2.3 Passive Core Cooling System 2.2.3-1 f] V' 2.2.4 Steam Generator System 2.2.4-1 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 2.3.5 Mechanical Handling System 2.3.5-1 2.3.6 Normal Residual Heat Removal System 2.3.6-1 2.3.7 Spent Fuel Pool Cooling System 2.3.7-1 2.3.8 Service Water System 2.3.8-1 2.3.9 Containment Hydrogen Control System 2.3.9-1 2.3.10 Liquid Radwaste System 2.3.10-1 2.3.11 Gaseous Radwaste System 2.3.11-1 2.3.12 Solid Radwaste System 2.3.12-1 2.3.13 Primary Sampling System 2.3.13 1 1 2.3.14 Demineralized Water Transfer and Storage System 2.3.14-1 j 2.3.15 Compressed and Instrument Air System 2.3.15-1 i
- 2.3.16 Potable Water System 2.3.16d l 2.3.17 Waste Water System 2.3.17-1 2.3.18 Plant Gas System 2.3.18-1 2.3.19 Communication System 2.3.19-1 2.3.20 Turbine Buildine Closed Cooline Water System 2.3.20-1 l O 2.3 21 Secondary Sampline System 2 3.21-1 b
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t Revision: 6 l Effective: July 1998 1 .et j l 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 Gravity and Roof Drain Collection System 2.3.25-1 2.3.26 This section intentionally blank 2.3.26-1 2.3.27 Sanitary Drainace System 2.3.22d 2.3.28 Turbine Island Vents. Drains. and Relief System 2.3.28-1 2.3.29 Radioactive Waste Drain System 1.3.29-1 2.4 Steam and Power Conversion Systems 2.4.1 Main and Startup Feedwater System 2.4.1 -1 2.4.2 Main Turbine System 2.4.2-1 2.4.3 Main Steam System 2.4.3-1 2.4.4 Steam Generator Blowdown System 2.4.4-1 2.4.5 Condenser Air Removal System 2.4.5-1 2.4.6 Condensate System 2.4.6-1 2.4.7 This section intentionally blank 2.4.7-1 2.4.8 Auxiliary Steam Supp1v System 2.4.8-1 2.4.9 Condenser Tube Cleanine System 2.4.9-1 2.4.10 Turbine Island Chemical Feed System 2.4.10-1 2.4.11 Condensate Polishine System 2.4.11d 2.4.12 Gland Seal System 2.4.12-1 2.4.13 Generator Hydrocen and CO, System 2.4.13-1 2.4.14 Heater Drain System 2.4.14-1 2.4.15 Hydroren 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 Radiation Monitorine System 2.5.8-1 2.5.9 Seismic Monitoring System 2.5.9- 1 2.5.10 Main Turbine Control and Diarnostic System 2.5.10-1 2.6 Electrical Power Systems 2.6.1 Main ac Power System 2.6.1-1 2.6.2 Non-Class IE de and Unintenuptible Power Supply System 2.6.2-1 0 3 Westinghouse oNp0 WTAACSvev6Vntmtr.wpf.1 b-0730
Ti:r 1 Mrt: rill TABLE OF CONTENTS (^ ( Revision: 6 Effective: July 1998 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 Groundine and Lichtnine Protection System 2.6.6-1 2.6.7 Special Process Heat Tracine System 2.6.7-1 2.6.8 Cathodic Protection System 2.6.8-1 2.6.9 Plant Security System 2.6.9-1 2.6.10 Closed Circuit TV System 2.6.10-1 2.6.11 Main Generation System 2.6.11-1 2.6.12 Excitation and Voltare Regulation System 2.6.12-1 2.7 HVAC Systems 2.7.1 Nuclear Island Nonradioactive Ventilation System 2.7.1-1 2.7.2 Central Chilled Water System 2.7.2-1 2.7.3 Annex / Auxiliary Building Nonradioactive Ventilation System 2.7.3 1 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 L 2.7.8 Radwaste Building 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 3.3 Buildings 3.3-1 3.4 Initial Test Program 3.4-1 3.5 Radiation Monitoring 3.5-1 3.6 Reactor Coolant Pressure Boundary Leak Detection 3.6-1 , 3.7 Design Reliability Assurance Program 3.7-1 4.0 INTERFACE REQUIREMENTS 4.0-1 5.0 SITE PARAMETERS 5.0-1
- Underlined sections - title only, no entry for Design Certification. i
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Tier 1 Miterial TABLE OF CONTENTS
/^ Revision: 6 F__3; j \ Effective: July 1998 1 l
l LIST OF FIGURES Figure Title Page 2.1.2-1 Reactor Coolant System 2.1.2-30 2.1.3.= 1 Reactor Upper Internals Rod Guide Arrangement 2.1.3-13 l 2.1.3-2 Rod Cluster Control and Drive Rod Arrangement 2.1.3-14 2.1.3-3 Reactor Vessel Arrangement 2.1.3-15 2.2.1-1 Containment System 2.2.1-15 2.2.2-1 Passive Containment Cooling System 2.2.2-15 2.2.3-1 Passive Core Cooling System 2.2.3-28 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 l 2.3.1-1 Component Cooling Water System 2.3.1-5 f 2.3.2-1 Chemical and Volume Control System 2.3.2-15 l 2.3.3-1 Standby Diesel and Auxiliary Boiler Fuel Oil System 2.3.3-5 2.3.4-1 Fire Protection System (Seismic Piping) 2.3.4-6 2.3.6-1 Normal Residual Heat Removal System 2.3.6-17 2.3.7-1 Spent Fuel Pool Cooling System 2.3.7-7 2.3.8-1 Service Water System 2.3.8-5 2.3.10-1 Liquid Radwaste System 2.3.10-9 2.3.11-1 Gaseous Radwaste System 2.3.11-6 i 2.3.13-1 Primary Sampling System 2.3.13-8 I 2.3.29-1 Radioactive Waste Drain System 2.3.29-3 l 2.4.1 -1 Main and Startup Feedwater System 2.4.1 -4 ! 2.5.2-1 Protection and Safety Monitoring System 2.5.2-19 2.6.11 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 Unintermptible Power Supply System (Division A) 2.6.3-16 f 2.7.1-1 Nuclear Island Nonradioactive 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) Design and Implementation Process 3.2-11 3.3-1 Nuclear Island Section A-A 3.3-27 3.3-2 Nuclear Island Section B-B 3.3-29 3.3-3 Nuclear Island Plan View at Elevation 66'-6" 3.3-31 3.3-4 Nuclear Island Plan View at Elevation 82'-6" 3.3-35 3.3-5 Nuclear Island Plan View at Elevation 96'-6" 3.7-37 3.3-6 Nuclear Island Plan View at Elevation 100*-0" 3.3-39 3.3-7 Nuclear Island Plan View at Elevation 117'-6" 3.3> 1 3.3-8 Nuclear Island Plan View at Elevation 135'-3" 3.3-43 3.3-9 Nuclear Island Plan View at Elevation 153'-3" & 160'-6" 3.3-45 3.3-10 Nuclear Island Plan View at Shield Building Roof 3.3-47 3.3-11 Annex Building Plan View at Elevation 100'-0" 3.3-49 3.3-12 Annex Building Plan View at Elevation 117'-6" O 3.3-51 vil W85tiligh00S8 oNp01 VTAACSVev6Vntmtr.wpf:1 b-072798
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- TABLE OF CONTENTS Revision: 6 Effective: July 1998 LIST OF FIGURES (cont.)
Figure Title Page 3.3-13 Annex Building Plan View at Elevation 135'-3" 3.3-53 3.3-14 Nuclear Island Stnictures Dimension at Elevation 66'-6" 3.3-55 10-1 Horizontal Design Response Spectra Safe Shutdown Earthquake 5.0-4 5.0-2 Vertical Design Response Spectra Safe Shutdown Earthquake 5.0-5 5.0-3 Free-Field Motions at Foundation Level (40 ft. Depth) Envelope of Horizontal Motions 5.0-6 5.0-4 Free-Field Motions at Foundation Level (40 ft. Depth) Envelope of Vertical Motions 5.0-7 O O 3 We@@ouse o:sapsoos:T AAc ssrevesfntmtr.wpt.1 o.072
Tier 1 M;t: rial INTRODUCTION gs O b Revision: 6 Effective: July 1998 E
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1.0 Introduction 1.1 Definitions The following definitions apply to terms used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC). Acceptance Criteria means the performance, physical condition, or analysis result for a stmeture, 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. As-built means the physical propenies of a structure, system, or component following the completion of its installation or constmetion activities at its final location at the plant site. I Column Line is the designation applied to a plant reference grid used to define the location of I building walls and columns. Column lines may not represent the center line of walls and columns. p Design Commitment means that portion of the design description that is verified by ITAAC. Design Description means that portion of the design that is certified. I Design Plant Grade means the elevation of the soil around the nuclear island assumed in the design I of the AP600, i.e., floor elevation 100'-0". Division (for electrical systems or electrical equipment) is the designation applied to a given safety-related system or set of components that is physically, electrically, and functionally independent from other redundant sets of components. 1 Floor Elevation is the designation applied to name a floor. The actual elevation may vary due to I floor slope and layout requirements. 1 Functional Arrangement (for a system) means the physical arrangement of systems and components i to provide the service for which the system is intended, and which is described in the system design description. I Inspect or Inspection means visual obsen'ations, physical examinations, or reviews of records based i on visual observation or physical examination that compare the structure, system, or component i condition to one or more design commitments. Examples include walkdowns, configuration checks, measure.nents of dimensions, or nondestmetive examinations. Inspect for Retrievability of a display means to visually observe that the specified information
) appears on a monitor when summoned by the operator.
1.0-1 [ W65tiligh0LISO o:WITAACSvevfiA0101.wpf:071398 l
Ti2r 1 M:terlil INTRODUCTION EE Revision: 6 Effective: Jul/ 1998 _ L,is the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J. l l Physical Arrangement (for a structure) means the arrangement of the building features (e.g., floors, I ceilings, walls, and basemat) and of the structures, systems, and components within, which are i described in the building design description. Qualified for liarsh 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. These environmental conditions include I applicable time-dependent temperature and pressure profiles, humidity, chemical effects, radiation, I aging, submergence, and their synergistic effects which have a significant effect on the equipment I performance. Equipment identified in the Design Description as being Qualified for Harsh Environment includes the:
- a. equipment itself
- b. sensors, switches and lubricants that are an integral part of the equipment
- c. electrical components connected to the equipment (wiring, cabling and terminations)
Items b and c are Qualified for Harsh Environment only when they are necessary to support operation of the equipment to meet its safety-related function listed in the Design Description table and to the extent such equipment is located in a harsh environment during or following a design basis accident. I 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. I Site Grade means the as-built elevation of the soil to the west side of the nuclear island. Adjacent I buildings are located on the other sides of the nuclear island. 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. I I j 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.
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l l UA of a heat exchanger means the product of the heat transfer coefficient and the surface area. ] O 3 Westinghouse o:sapsoosiTAAcssreetolo1.wpf:07 98
Tier 1 M tiriti INTRODUCTION : ==
/,\ Revision: 6 V Effective: July 1998 1.2 General Provisions The following general provisions are applicable to the design descriptions and associated ITAAC.
Treatment of Individual Items The absence of any discussion or depiction of an item in the design description or accompanying figures shall not be ccatrued 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 criteria, it refers to 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 The ITAACs are provided in tables with the following three-column format: J 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 require that separate inspections, tests, or analyses must be performed for each design commitment. 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 on by its authorized vendors, contractors, or consultants. Fmthermore, an ITA may be performed by more chan a single individual or group, may be implemented through discrete activities separated by time, ano may be performed at any time prior i to fuel load (including before issuance of the combined license for those ITAACs that do not necessarily pertain to as-installed equipment). Additionally, an ITA may be performed as part of the ( activities that are required to be performed under 10 CFR Past 50 (indsding, for example, the quality j assurance (QA) program required under Appendix B to Part 50); therefore, an ITA need not be performed as a separate or discrete activity. l I o 1 l L.J 1.0-3 W W85tingh0USB o Aap600VT AAC SVev6Vt0101.wpf:071398 i .._
Ti;r 1 Materi:1 INTRODUCTION ==- Revision: 6 E
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Effective: July 1998 _ Discussion of Matters Related to Operations In some cases, the design descriptions in this document refer to matters that relate to operation, such as normal valve or breaker alignment during normal operation modes. Such discussions are provided solely to place the design description provisions in context (for example, to explain automatic features for opening or closing valves or breakers upon off-norTnal conditions). Such discussions shall not be construed as requiring operators during operation to take any particular action (for example, to maintain valves or breakers in a particular position during normal operation). Interpretation of Figures 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 part of the system. Unless specified explicitly, the figures are not indicative of the scale, location, dimensions, 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 thermal power for the AP600 certified design is 1933 megawatts thermal (MWt). l l l l l l O 1 T Westinghouse ospeoouTAAcsvevswoiotwato a
Tier 1 Material INTRODUCTION -
/\ Hevision: 6 l CI Effective: July 1998 1.3 Figure Legend The conventions used in this section are for figures described in the design description. The figure I legend is provided for information and is not part of the Tier 1 Material.
VALVES Valve C><3 Check Valve M Relief Valve N Q\- VALVE OPERATORS Operator Of Unspecified Type T Motor Operator h i Solenoid Operator h_ Pneumatic / Hydraulic Operator l Pneumatic Operator P ' l T r^x Squib Valve C U T 1.0-5 [ W85tirigh0US8 o:\ap600\lTAACS\revfNt0101.wpf.071398 i
Tier 1 M:teri;l INTRODUCTION CZ-~22
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Revision: 6 Effective: July 1998 WECHANICAL EQUIPMENT l Centrifugal Pump fl Pump Type Not Specified } Tonk Centrifugal fan h Axial fan Hect Exchanger O Vent Droin U D Pipe Cop __]. Smd flange _g Orifce _ j_ O w ~~~~ ---.._ ,2*;'
Tier 1 M:teri:1 INTRODUCTION == =E
, Revision: 6 " 's Effective: July 1998 _
DAMPERS Gravity Or Monually Operated Damper Remotely Operated Damper ELECTRICAL EQUIPMENT Battery EEE Circuit Breaker A 1 Disconnect Switch / -- Isolation Transformer A ' 9 i fue h l Heater LW.J Generator 1.0-7 o WB5tingh0USB oMp600\lTAACSVev6\it0101.wpf:071398
Tier 1 Material INTRODUCTION r-C Revision: 6
= m Effective: July 1998 1 .et MlSCEUANE0VS A component that is part of the , Component Name system functional arrangement shown Component Tag No.
on the f,igure and is included ,in the design commitments for the system. A component that is part of the Component Namel-- system functional arrangement shown - on the figure. LComponent Tag No.J __ A system or component of another system FS ystem or Component Name1 _,_ that is not part of the system functional - System Acronym arrangement shown on the figure. L_ _ A functional connection to another system that is not part of the system functional --g TEM Oy 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). l ASME CODE SEC110N lli CLASS l L2 uj
- x N NOTES:
1
- 1. The header, "ASME Code Section 111 Class", must appear at least once on each l
figure on which ASME class breaks are shown, but need not appear at every class l break shown on a figure. 1 l 7 Indicates Non-ASME Code Section ill i O 3 Westinghouse o:Wp600VTAACsVev6Vt0101.wpt07 9
Tier 1 M:t: rill INTRODUCTION ss :=- f)(/ Revision: 6 Effective: July 1998
=
1.4 List of Acronyms and Abbreviations l The acronyms presented in this section are used in the Tier 1 Material. The acronyms are provided 1 for information and are not part of the Tier 1 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 CAV Cumulative Absolute Velocity CCS Component Cooling Water System CDM Certified Design Material CDS Condensate System CFR Code of Federal Regulations CIV Containment Isolation Valve CL Cold Leg 3 CMT Core Makeup Tank (V CNS COL Containment System 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 l DBA Design Basis Accident de Direct Current DC Design Commitment DDS Data Display and Processing System DOS Standby Diesel and Auxiliary Boiler Fuel Oil System DPU Distributed Processing Unit D-RAP Design Reliability Assurance Program DTS Demineralized Water Treatment System DVI Direct Vessel Injection - DWS Demineralized Water Transfer and Storage System ECS Main ac Power System EDS Non-Class lE de and Uninterruptible Power Supply System EFS Communication System EGS Grounding and Lightening Protection System ELS Plant Lighting System EMI Electromagnetic Interference ( ERF Emergency Response Facility i 1.0-9 Westitighouse o:\ap600\lTAACS\rev6\it0101.wpf:071398 i I
Tier 1 Material INTRODUCTION Revision: 6 Effective: July 1998 List of Acronyms and Abbreviations (cont.) ESD Electrostatic Discharge ESF Emergency Safety Features ESFAS Engineering Safety Feature Actuation System F Fahrenheit FHM Fuel Handling Machine FHS Fuel Handling and Refueling System FID Fixed Incore Detector FPS Fire Protection System ft Feet FTS Fuel Transfer System FWS Main and Startup Feedwater System gpm Gallons per Minute HEPA High Efficiency Particulate Air HFE Human Factors Engineering HL Hot Leg hr Hour HSI Human-System Interface HVAC Heating, Ventilation, and Air Conditioning HX Heat Exchanger Hz Hertz I&C Instrumentation and Control IDS Class 1E de and Uninterruptible Power Supply System IIS In-core Instrumentation System ILRT Integrated Leak Rate Test IHP Integrated Head Package in Inches I/O Input / Output I&C Instrumentation and Control IRC Inside Reactor Containment IRWST In-containment Refueling Water Storage Tank I ISI Inservice Inspection IST Inservice Testing l ITA Inspections, Tests, Analyses l ITAAC Inspections, Tests, Analyses, and Acceptance Criteria l LBB Leak Before Break LTOP Low Temperature Overpressure Protection M Bru Million British Thermal Units MCC Motor Control Center MCR Main Control Room MHS Mechanical Handling System l MMIS Man-machine Interface System l l O 3 W85tiflgh00Se sp600VTAACSVev6Mt0101.wpf:07 39
l ! Tier 1 Material ! INTRODUCTION - '[' Revision: 6 3 - Effective: July 1998 List of Acronyms and Abbreviations (cont.) MOV Motor-operated Valve MSIV Main Steam Isolation Valve MSLB Main Steam Line Break MSS Main Stearr. System MTS Main Turbine System MW Megawatt MWe Megawatt Electric MWt Megawatt Thermal N/A Not Applicable NDE Nondestmctive Examination NI Nuclear Island NSSS Nuclear Steam Supply System OCS Operation and Control Centers System ORC Outside Reactor Containment ORE Occupational Radiation Exposure OSA Operational Sequence Analyses OSC Operations Support Center PAR Passive Autocatalytic Recombiner PCCAWS (o j PCWS Passive Containment Cooling Ancillary Water Storage Tank Passive Containment Cooling Water Storage PCCWST Passive Containment Cooling Water Storage Tank PCS Passive Containment Cooling System P&ID Piping and Instrument Diagram PGS Plant Gas System pH Potential of Hydrogen PLS Plant Control System PMS Protection and Safety Monitoring System PORV Power-operated Relief Valve PRA Probabilistic Risk Assessment
. PRHR Passive Residual Heat Removal psia Pounds per Square Inch Absolute PSS Primary Sampling System PXS Passive Core Cooling System PWR Pressurized Water Reactor RAP Reliability Assurance Program RAT Reserve Auxiliary Transformer RCDT Reactor Coolarit Drain Tank RCP Reactor Coolant Pump RCPB Reactor Coolant Pressure Boundary
, RCS Reactor Coolant System l RFI Radio Frequency Interference l RM Refueling Machine f RMS Radiation Monitoring System 1.0-11 W85tingh0USB o:\ap600\lTAACSVev6\it0101.wpf:071398
Tier 1 Material
= =
INTRODUCTION Revision: 6 Effective: July 1998 _ List of Acronyms and Abbreviations (cont.) RNS Normal Residual Heat Removal System kPV Reactor Pressure Vessel RSR Remote Shutdown Room RSW Remote Shutdown Workstation RTD Resistance Temperature Detector RXS Reactor System RV Reactor Vessel scf Standard Cubic Feet scfm Standard Cubic Feet per Minute SFP Spent Fuel Pool SFS Spent Fuel Pool Cooling System SG Steam Generator SGS Steam Generator System SJS Seismic Monitoring System SMS Special Monitoring System SSAR Standard Safety Analysis Report SSCs Structures, Systems, and Components SSE Safe Shutdown Earthquake SWC Surge Withstand Capability SWS Service Water System TID Total Integrated Dose TSC Technical Support Center UAT Unit Auxiliary Transformer UBC Uniform Building Code UPS Uninterruptible Power Supply V Volt VAS Radiologically Controlled Area Ventilation System VBS Nuclear Island Nonradioactive Ventilation System VCS Containment Recirculation Cooling System VES Main Control Room Emergency Habitability System VFS Containment Air Filtration System VHS Health Physics and Hot Machine Shop Areas VLS Containment Hydrogen Control System VWS Central Chilled Water System VXS Annex / Auxiliary Building Nonradioactive Ventilation System VZS Diesel Generator Building Ventilation System WGS Gaseous Radwaste System WLS Liquid Radwaste System WSS Solid Radwaste System ZOS Onsite Standby Power System O 1.0-12 W8StlDgh0US8 o:\ap600\lTAACSVev6ut0101.wpf;071398
I Tirr 1 Mit: rial l FUEL HANDLING AND REFUELING SYSTEM Z-
/q ) Revision: 6 =
' Effective: July 1998 _
2.1.1 Fuel Handling and Refueling System l Design Description The fuel handling and refueling system (FHS) transfers fuel assemblies and core components during fueling operations and stores new and spent fuel assemblies in the new and spent fuel storage racks. The refuding machine (RM) and the fuel transfer tube are operated during refueling mode. The fuel handling machine (FHM) is operated during normal tnodes of plant operation, including stanup, power operation, cooldown, shutdown and refueling. The component locations of the FHS are as shown in Table 2.1.1-2.
- 1. The functional arrangement of the FHS is as described in the Design Description of this Section 2.1.1.
- 2. The FHS has the RM, the FHM, and the new and spent fuel storage racks.
- 3. The FHS preserves containment integrity by isolation of the fuel transfer tube penetrating containment.
pV
- 4. The RM and FHM gripper assemblies are designed to prevent opening while the weight of the fuel assembly is suspended from the gripper.
- 5. The lift height of the RM and FHM masts is limited such that the minimum required depth of water shielding is maintained.
- 6. The RM and FHM are designed to maintain their load carrying and stmetural integrity functions during a safe shutdown earthquake.
- 7. The new and spent fuel storage racks maintain the effective neutron multiplication factor less than the required limits during normal operation, design basis seismic events, and design basis dropped fuel assembly accidents. l l
Inspections, Tests, Analyses, and Acceptance Criteria l Table 2.1.1-1 specifies the inspections, tests, analyses, and associated acceptance criteria for the FHS.
)
l 1 l l {)\ w 2.1.1 1 3 W85fl!1ghouse oNTAACSvev6\it020101.wpf:073098 ) t .______________A
Tier 1 Mcterial FUEL HANDLING AND REFUELING SYSTEM 7 -~ Z Revision: 6 Effective: July 1998 - Table 2.1.1 1 ] Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. The functional arrangement of Inspection of the as-built system The as-built FHS conforms with I the FHS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.1.1. Description of this Section 2.1.1.
- 2. 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. I 3. The FHS preserves See Tier 1 Material, subsection See Tier 1 Material, subsection containment integrity by isolation 2.2.1, Containment System. 2.2.1, Containment System. of the fuel transfer tube penetrating containment.
- 4. 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. <
- 5. The lift height of the RM and The RM and FHM will be tested The bottom of the dumrny fuel FHM masts is limited such that by attempting to raise a dummy assembly cannot be raised to the minimum required depth of fuel assembly, within 24 ft,6 in of the operating water shielding is maintained. deck floor.
- 6. The RM and FHM are i) Inspectior, will be performed to i) The RM and FHM are located designed to maintain their load verify that the RM and FHM are on the nuclear island.
carrying and structural integrity located on the nuclear island. functions during a safe shutdown earthquake. ii) Type test, analysis, or a ii) A report exists and concludes combination of type tests and that the RM and FHM can analyses of the RM and FHM will withstand seismic design basis be performed. dynamic loads without loss of load carrying or structural integrity functions. O1 W8Silflgh0US8 o:\lTAACS\rev6\it020101.wp 7149
l Tier 1 Mit:ri:1 , 1 i FUEL HANDLING AND REFUELING SYSTEM (~] Revision: 6 (/ Effective: July 1998 Table 2.1.1 1 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 7. The new and spent fuel i) Analyses will be performed to i) The calculated effective storage rnks maintain the calculate the effective neutron neutron multiplication factor for effective neutron multiplication multiplication factor in the new the new and spent fuel storage i 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.
f 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 g multiplication factor less than 0.95. O) ( iv) Analysis of the new and spent iv) A report exists and concludes fuel storage racks under design that the new and spent fuel racks basis dropped fuel assembly loads can withstand design basis will be performed. dropped fuel assembly loads and maintain the calculated effective neutron multiplication factor less than 0.95.
)
l i 1 1 t A W wesunghouse o m m e m oto, ';'i'i
j Tier 1 Mcterial FUEL HANDLING AND REFUELING SYSTEM . Revision: 6 l Effective: July 1998 I l l Table 2.1.12 Component Name Tag No. Component Location Refueling Machine FHS-FH-01 Containment Fuel Handling Machine FHS-FH-02 Auxiliary Building Spent Fuel Storage Racks FHS-FS-20 Auxiliary Building New Fuel Storage Racks FHS-FS-01 Auxiliary Building Fuel Transfer Tube FHS-FT-01 Auxiliary Building / Containment O O 2.1.1 -4 3 W85tiligh0USB o:MTAACSVev6\it020101.wpf:071498
L' 1 Tier 1 Mitsri:1 REACTOR COOLANT SYSTEM
. Q( ) . Revision: 6 Effective: July 1993
}
2.I.2 Reactor Coolant System I t Design Description l
- The reactor coolant system (RCS) removes heat from the reactor core and transfers it to the secondary side of the steam generators for power generation. The RCS contains two vertical U-tube steam generators.
l four canned motor reactor coolant pumps (RCPs), and oile pressurizer. l The RCS is as shown in Figure 2.1.2-1 and the component locations of the RCS are as shown in Table 2.1.2-5.
- 1. The functional arrangement of the RCS is as described in the Design Description of this Section 2.1.2.
l
- 2. a) The components identified in Tr.ble 2.1.2 ASME Code Section III are designed and constructed in accordance with ASME Code Section Ih requirements.
b) The piping identified in Table 2.1.2-2 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 2.1.2-1 as ASME Code Section III V
O meet ASME Code Section III requirements. b) Pressure boundary welds in piping identified in Table 2.1.2-2 as ASME Code Section III meet ASME Code Section III requirements.
- 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.
b) The piping identified in Table 2.1.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.1.2-1 can withstand seismic design basis 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 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 l LBB criteria. or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
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Tier 1 M;terial REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998
- 7. a) The Class 1E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class 1E components identi6ed in Table 2.1.2-1 are powered from their respective Class 1E division. c) Separation is provided between RCS Class 1E divisions, and between Class IE divisions and non-Class 1E cable.
- 8. The RCS provides the following safety-related functions:
a) The pressurizer safety valves provide overpressure protection in accordance with Section III of the ASME Boiler and Pressure Vessel Code. b) The pressurizer safety valves operate with low flow at pressures near the valve set pressure, c) The reactor coolant pumps (RCPs) have a rotating inertia to provide RCS flow coastdown on loss of power to the pumps. d) Each RCP flywheel assembly can withstand a design overspeed condition. e) The RCS provides automatic depressurization during design basis events. f) The RCS provides emergency letdown during design basis events.
- 9. The RCS provides the following nonsafety-related functions:
a) The RCS provides circulation of coolant to remove heat from the core. b) The RCS provides the means to control syWrn pressure. c) The pressurizer heaters trip after a signal is generata by the PMS.
- 10. Safety-related displays identified in Table 2.1.2-1 can be retneved 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 r an active safety function after receiving a signal from DAS. T Westinghouse omcamewo20io2wps$NN
Tier 1 Mituill F REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 _
- 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) After loss of motive power, the remotely operated valves identified in Table 2.1.2-1 assume the indicated loss of motive power position. 13.a) Controls exist in the MCR to trip the RCPs. b) The RCPs trip after receiving a signal from the PMS. c) The RCPs trip after receiving a signal from the DAS.
- 14. Controls exist in the MCR to cause the components identified in Table 2.1.2-3 to perfonn the listed function.
- 15. Displays of the parameters identified in Table 2.1.2-3 can be retrieved in the MCR.
1 Inspections, Tests, Analyses, and Acceptance Criteria l Table 2.1.2-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the RCS. l l l I 2.1.2-3 I T Westinghouse oNTAACSirev6\it020102 wp6:10-072498 l
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=E REACTOR COOLANT SYSTEM E Revision: 6 Effective: July 1998 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 - I 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-EH-04B Yes On/Off Pressurizer Heaters RCS-BH-(MC 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-VO(MB Yes - (Position Indication) Fourth-stage ADS Squib Valve RCS-PL-V004C Yes - (Position Indication) Fourth-stage ADS Squib Valve RCS-PL-V004D Yes - (Position Indication) Presstuizer Safety Valve RCS-PL-V005A Yes - (Position Indication) Pressurizer Safety Valve RCS-PL-V005B Yes - (Position Indication) Pressurizer Spray Valve RCS-PL-VI 10A Yes - (Position Indication) Note: Dash (-) mdicates not apphcable. j O [ W8Stilighouse onlTAACSvev6bt029102.wp6:1 07249
Tier 1 Mit2 rill O REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2.1.2 3 (cont.) Equipment Tag No. Display Control Function Pressurizer Spray Valve RCS-PL-VI 10B Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-150A Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS PL-150B Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-ISOC Yes - (Position Indication) Reactor Vessel Head Vent Valve RCS-PL-150D Yes - (Position Indication) Note: Dash (-) indicates not applicable. v) l l l l n U 2.1.2 19 W85tiligh0US8 o:\lTAACS\rev6 Tit 020102.wp6:1 b-072498 1
Tier 1 M:t: rill E REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2 I.2-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Cornmitment Inspections. Tests. Analyses Acceptance Criteria I 1. The functional arrangement of Inspection of the as-built system The as-built RCS conforms with the I the RCS is as described in the will be performed, functional arrangement described in I Design Description of this the Design Description of this I Section 2.1.2. Section 2.I.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 Section III. requirements. 2.b) The piping identified in Inspection will be conducted of The ASME code S2 tion III design Table 2.1.2-2 as ASME Code the as-built components as reports exist for the as-built piping Section IIIis designed and documented in the ASME design identified in Table 2.1.2 2 as ASME constructed in accordance with reports. Code Section III. ASME Code Section III requirements. 3.a) Pressure boundary welds in 3.a) Pressure boundary welds in A report exists and concludes that components identified in components identified in the ASME Code Section III Table 2.1.2-1 as ASME Code Table 2.1.2-1 as ASME Code requirements are met for non-Section III meet ASME Code Section III meet ASME Code destructive examination of pressure ! Section III requirements. Section III requirements. boundary welds. j 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.1.2-2 boundary welds will be the ASME Code Section III as ASME Code Section III meet performed in accordance with the requirements are met for non-ASME Code Section III ASME Code Section III. destructive examination of pressure requirements. boundary welds. 1 1 O E Westinghouse ovrAACSvev6Mt020102.wp6 029 1
Tier 1 M teri:1 ( REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.) Inspections. Tests. Analyses,and Acceptance Criteria Design Commitment Inspections. Tests. Analyses Acceptance Criteria 4.a) The components identified in A hydrostatic test will be A report exists and concludes that Table 2.1.2-1 as ASME Code performed on the components the results of the hydrostatic test of Section III retain their pressure required by the ASME Code the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.1.21 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.1.2-2 as ASME Code performed on the piping required the results of the hydrostatic test of Section III retains its pressure by the ASME Code Section III to the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.1.2 2 as ASME Cc,de pressure. Section III conform with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.1.2-1 can withstand equipment and valves identified Table 2.1.2-1 is located on the [" seismic design basis loads without in Table 2.1.2-1 are located on Nuclear Island. ( loss of safety function. 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 is bounded by the tested or analyzed seismically bounded by the tested conditions. or analyzed conditions. 5.b) Each of the lines identified in Inspection will be performed for A report exists and concludes that
- Table 2.1.2-2 for which functional the existence of a report verifying each of the as-built lines identified
! capability is required is designed that the as-built piping meets the in Table 2.1.2-2 for which to withstand combined normal and requirements for functional functional capability is required l seismic design basis loads without capability. meets the requirements for l a loss of its functional capabilitv. functional capabilitv. l I r 2.1.2-21 WBStiflgh0USB o:VTAACSvev69t020102.wp6:1 b-072498
Tier 1 Mit:ri:1 REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.) Inspections Tests, Analyses, and Acceptance Criteria Design Commitment inspections. Tests. Analyses Acceptance Criteria
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation report exists identified in Table 2.1.2-2 as the existence of an LBB and concludes that the LBB designed for LBB meets the LBB evaluation report or an evaluation acceptance criteria are met by the criteria, or an evaluation is report on the protection from as-built RCS piping and piping performed of the protection from dynamic effects of a pipe break. materials, or a pipe break evaluation i the dynamic effects of a rupture of Tier 1 Material, Section 3.3, report exists and concludes that the line. Nuclear Island Buildings, protection from the dynamic effects contains the design descriptions of a line break is provided.
and inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture. 7.a) The Class lE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.1.2-1 as being combination of type tests and the Class IE equipment identified in qualified for a harsh environment analyses will be performed on Table 2.1.2-1 as being qualified for can withstand the environmental Class IE equipment located in a a harsh environment can withstand conditions that would exist before, harsh environment. the environmental conditions that during, and following a design would exist before, during, and basis accident without loss of followig MMgn 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 simulated test Class IE equipment identified in powered from their respective signal in each Class IE division. Table 2.1.2-1 when the assigned Class IE division. Class IE division is provided the test signal. I 7.c) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material Section 3.3, between RCS Class IE divisions, Nuclear Island Buildings. Nuclear Island Buildings. and between Class lE divisions and non-Class IE cable. 8.a) The pressurizer safety valves i) Inspections will be conducted i) The sum of the rated capacities provide overpressure protection in to confirm that the value of the recorded on the valve ASME Code accordance with Section III of the vendor code plate rating is greater plates of the safety valves exceeds ASME Boiler and Pressure Vessel than or equal to system relief 800,000 lb/hr. Code. requirements. ii) Testing and analysis in ii) A report exists and concludes accordance with ASME Code that the safety valves set pressure is Section III will be performed to 2485 psig 25 psi. determine set pressure. O [ W8Stingt100S8 oNTAACS\rev6Vt020102.wp6:1b 07249
Ti:r 1 M:tirial
^ REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.)
Inspections. Tests, Analyses,and Acceptance Criteria Design Commitment Inspections. Tests. Analyses Acceptance Criteria 8.b) The pressurizer safety valves Tests or type tests are performed A report exists and concludes that operate with low flow at piessures to correlate flow through the the safety valves operate in a stable near the valve set pressure. safety valves as a function ofinlet manner with a leakage rate greater pressure. or equal to 0.35 lbm/sec at a pressure below the valve full-open pressure. 8.c) The RCPs have a rotating Inspection of as-built RCP vendor The calculated rotating inertia of inertia to provide RCS flow data will be performed. each RCP is no less than 5000 lb-ft 2. coastdown on loss of power to the pumps. 8.d) Each RCP flywheel assembly Shop testing of each RCP Each RCP flywheel assembly has can withstand a design overspeed flywheel assembly will be passed an overspeed condition of no condition. performed at the vendor facility at less than 125% of operating speed. overspeed conditions. 8.e) The RCS provides automatic i) A low pressure flow test and i) The calculated ADS piping flow depressurization during design associated analysis will be resistance from the pressurizer basis events. conducted to determine the total through the sparger with all valves piping flow resistance of each of each ADS group open is 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 injection flow into the RCS discharging through the ADS valves. Inspections and associated analysis of the piping flow paths i from the discharge of the ADS 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 design flow resistance calculations. r ( W85tiflgtl0US8 oNTAACSVev6'Jt020102.wp6:1b h249 u______________________________ __
1 l Tier 1 M:t;ri:1 REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 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 routing used for design flow resistance calculations. iii) Inspections of each fourth- iii) The flow area through each stage ADS valve will be fourth-stage ADS valve is 2 38 in'. conducted to determine the flow area through each valve. iv) Type tests and analysis will iv) A report exists and concludes be performed to determine the that the effective flow area through effective flow area through each each stage 1 ADS valve 2 4.6 in stage 1,2,3 ADS valve. and each stage 2,3 ADS valve is 2 21 in . v) Inspections of the elesation of v) The minimum elevation of the the ADS stage 4 valve discharge bottom inside surface of the outlet will be conducted. of these valves is greater than plant elevation 110 feet. vi) Inspections of the ADS stage vi) The discharge of the ADS stage 4 valve discharge will be 4 valves is directed into the steam conducted. generator compartments. i vii) Inspection of each ADS vii) The flow area through the holes sparger will be conducted to in each ADS sparger is a 274 in:. determine the flow area through the sparger holes. viii) Inspection of the elevation viii) The centerline of the of each ADS sparger will be connection of the sparger arms to conducted. the sparger hub is s 11.5 feet below I the IRWST overflow level. 8.f) The RCS provides emergency inspections of the reactor vessel A report exists and concludes that letdown during design basis head vent valves and inlet and the capacity of the reactor vessel events, outlet piping will be conducted. head vent is sufficient to pass not less than 8.2 lbm/see at 1250 psia in the RCS. O 2.1.2-24 3 Westinghouse o AITAACSvev6\it020102.wp6:1 b-072498
i Tier 1 M:ttriIl ! REACTOR COOLANT SYSTEM 4 ( Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.) Inspections, Tests. Analyses,and Acceptance Criteria Design Conunitment Inspections, Tests, Analyses Acceptance Criteria 9.a) The RCS provides circulation Testing and analysis to measure The calculated post-fuelload RCS of coolant to remove heat from the RCS flow with four reactor flow rate is 2193,200 gpm. ; core. coolant pumps cperating at no- ; load RCS pressure and temperature conditions will be performed. Analyses to convert the measured pre-fuel load flow will be performed. This analysis accounts for flow measurement ; uncertainties. 9.b) The RCS provides the means i) Inspections will be performed i) Pressurizer heater backup groups to control system pressure, to verify the rated capacity of A and B cach has a rated capacity of l 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. 9.c) The pressurizer heaters trip Testing will be performed to The pressurizer heaters identified in l after a signal is generated by the confirm trip of the pressurizer Table 2.1.2-3 trip after a signalis PMS. heaters identified in generated by the PMS. Table 2.1.2-3.
- 10. Safety-related displays Inspection will be performed for Safety-related displays identified in j identified in Table 2.1.2-1 can be retrievability of the safety-related Table 2.1.2 1 can be retrieved in the i retrieved in the MCR. displays in the MCR. MCR. l 11.a) Controls exist in the MCR to i) Testing will be performed on i) Controls in the MCR operate to cause the remotely operated valses 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
=
2.1.2-25 T Westinghouse o:VTAAC$ sev6Vt020102.wp6:1 b-072498
Tier 1 Miterial REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.) Inspections Tests Analyses, and Acceptance Criteria Design Commitment Inspections Tests, Analyses Acceptance Criteria l l 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 j 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 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 frc;m PMS. iii) Testing will be performed to iii) These valves open within the demonstrate that remotely following times after receipt of an operated RCS isolation valves actuation signal: RCS-V001 A/B, V002A/B, V003A/B open within the V001 A/B s 30 sec required response times. V002A/B, V003A/B s 80 sec V011 A/B s 20 see V012A/B. V013A/B s 30 sec 11.c) The valves identified in i) Testing will be perforrned on i) The squib valves receive a signal Table 2.1.2-1 as having DAS the squib valves identified in at the valve electrical leads that is control perform an active safety Table 2.1.2-1 using real or capable of actuating the squib valve. function after receiving a signal simulated signals into the DAS from DAS. without stroking the valve. ii) Testing will be performed on ii) The other remotely operated the other remotely operated valves identified in Table 2.1.2-1 as valves identified in Table 2.1.2-1 having DAS control perform the using real or simulated signals active function identified in the into the DAS. table after receiving a signal from DAS. l T Westinghouse ovrAACSvevNDE02 wp6 -02 J
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Tier 1 Mitirial REACTOR COOLANT SYSTEM g Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.) Inspections. Tests, Analyses,and Acceptance Criteria Design Commitment Inspections. Tests Analyses Acceptance Criteria 12.a) The automatic i) Tests or type tests of motor- I) A test report exists and depressurization valves identified operated valves will be performed concludes that each motor-operated ' in Table 2.1.2-1 perform an active that demonstrate the capability of valve changes position as indicated safety-related function to change the valve to operate under its in Table 2.1.2-1 under design position as indicated in the table. design conditions. conditions. ii) Inspection will be performed li) A report exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are bounded by the tests or motor-operated valves are type tests. bounded by the tests or type tests. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be chaiges position as indicated in performed under pre-operational Table 2.1.2-1 under pre-operational flow, differential pressure and test conditions. temperature conditions.
) iv) Tests or type tests of squib iv) A test report exists and V valves will be performed that concludes that each squib valve i demonstrate the capability of the changes position as indicated in valve to operate under its design Table 2.1.2-1 under design conditions. conditions.
v) Inspection will be performed v) A report exists and concludes ! for the existence of a report that the as-installed squib valves are verifying that the as-installed bounded by the tests or type tests. squib valves are bounded by the tests or type tests. vi) See item Le.i in this table. vi) See item 8.e.iin this table. The ADS stage 1-3 valve flow l resistances are verified to be consistent with the ADS stage 1-3 l l path flow resistances. l vii) See item 8.e.iiin this table. vii) See item 8.e.ii in this table. The ADS stage 4 valve flow l resistances are verified to be consistent with the ADS stage 4 path flow resistances.
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Tier 1 M:t risi E-7 -- REACTOR COOLANT SYSTEM Revision: 6 Effective: July 1998 Table 2.1.2-4 (cont.) Inspections, Tests Analyses, and Acceptance Criteria Design Commitment Inspections Tests Analyses Acceptance Criteria viii) See item 8.e.iii in this table. viii) See item 8.e.iii in this table. l ix) See item 8.e.iv in this table. ix) See item 8.e.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 I 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 c'ontrols in the MCR. the RCPs. 13.b) The RCPs trip after Testing will be performed using The RCPs trip after receiving a receiving a signal from the PMS. real or simulated signals into the signal from the PMS. PMS. 13.c) The RCPs trip after Testing will be performed using The RCPs trip after receiving a receiving a signal from the DAS. real or simulated signals into the signal from the DAS. DAS.
- 14. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operate to cause the components identified in components in Table 2.1.2-3 cause the components listed in Table 2.1.2-3 to perform the listed using controls in the MCR. Table 2.1.2-3 to perform the listed function. functions.
- 15. Displays of the parameters inspection will be performed for The displays identified in identified in Table 2.1.2-3 can be retrievability of the RCS Table 2.1.2-3 can be retrieved in the retrieved in the MCR. parameters in the MCR. MCR.
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Tier 1 Mit:rirl REACTOR COOLANT SYSTEM E p() Revision: 6 Effective: July 1998 Table 2.1.2-5 Compe,nent Name Tag No. Component Location
- l. Steam Generator i RCS-MB-01 Containment Steam Generator 2 RCS-MB-02 Containment Reactor Coolant Pump 1 A RCS-MP-01 A Containment Reactor Coolant Pump IB RCS-MP-OlB Containment i
Reactor Coolant Pump 2A RCS-MP-02A Containment Reactor Coolant Pump 2B RCS-MP-02B Containment Pressurizer RCS-MV-02 Containment ADS Sparger A PXS-MW-01 A Containment ADS Sparger B PXS-MW-Ol B Containment 1 J O 2.1.2-29 .
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Tier 1 Materi:1 REACTOR SYSTEM ss ==, A Revision: 6 = = () Effective: July 1998 2.1.3 Reactor System Design Description The reactor system (RXS) generates heat by a cortrolled nuclear reaction and transfers the heat generated to the reactor coolant, provides a barrier that prevents the release of fission products to the ' atmosphere and a means to insert negative reactivity into the reactor core and to shutdown the reactor core. The reactor core contains a matrix of fuel rods assembled into fuel as:;emblies using structural elements. Rod cluster control assemblies (RCCAs) are positioned and held within the fuel assemblies i by control rod drive mechanisms (CRDMs). The CRDMs unlatch upon termination of electrical power l l to the CRDM thereby releasing the RCCAs. The fuel assemblies and RCCAs are designed in I accordance with the principal design requirements. The RXS is operated during normal modes of plant operation, including startup, power operation, cooldown, shutdown and refueling. l The component locations of the RXS are as shown in Table 2.1.3-3. l
- 1. The functional arrangement of the RXS is as described in the Design Description of this
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- 2. a) The reactor upper internals rod guide arrangement is as shown in Figure 2.1.3-1.
b) The rod cluster control and drive rod arrangement is as shown in Figure 2.1.3-2. c) The reactor vessel arrangement is as shown in Figure 2.1.3-3.
- 3. The components identified in Table 2.1.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
- 4. Pressure boundary welds in components identified in Table 2.1.3-1 as ASME Code Section III meet ASME Code Section III requirements.
- 5. The pressure boundary components (reactor vessel [RV), control rod drive mechanisms [CRDMs],
incore instrument guide tubes) identified in Table 2.1.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
- 6. The seismic Category I equipment identified in Table 2.1.3-1 can withstand seismic design basis loads without loss of safety function.
- 7. The reactor internals will withstand the effects of flow induced vibration.
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Tier 1 Materici REACTOR SYSTEM :: == Revision: 6 = Effective: July 1998 _
- 8. The reactor vessel direct injection nozzle limits the blowdown of the reactor coolant system (RCS) following the break of a direct vessel injection line.
- 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 Class IE division. c) Separation is provided between RXS Class IE divisions, and between Class IE divisions and non-Class IE cable.
- 10. The reactor lower internals assembly is equipped with holders for at least eight capsules for storing material surveillance specimens.
- 11. The reactor pressure vessel (RPV) beltline material has a Charpy upper-shelf energy of no less than 75 ft-lb.
- 12. Safety-related displays of the parameters identified in Table 2.1.3-1 can be retrieved in the main control room (MCR).
- 13. The fuel assemblies and rod control cluster assemblies intended for initial core load and listed in Table 2.1.3-1 have been designed and constmeted in accordance with the principal design I requirements.
Inspections, Tests, Analysis, and Acceptance Criteria Table 2.1.3-2 specifies the inspections, tests, analysis, and associated acceptance criteria for the RXS. O
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Tier 1 Material REACTOR SYSTEM EE EE Revision: 6 = Effective: July 1998 _ Table 2.1.3-2 Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections, Tests, Analysis Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built RXS conforms with the RXS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.1.3. Description of this Section 2.1.3.
2.a) The reactor upper in ernals Inspection of the as-built system The as-built RXS will rod guide arrangement is av will be performed. accommodate the fuel assembly shown in Figure 2.3.1-1. and control rod drive mechanism pattern shown in Figure 2.3.1-1. 2.b) The rod cluster cont Iand Inspection of the as-built system The as-built RXS will l drive rod arrangement is as will be performed. accommodate the rod cluster { shown in Figure 2.1.3-2. control and drive rod urangement I shown in Figure 2.1.3-2. l 2.c) The reactor vessel Inspection of the as-built system The as-built RXS will arrangement is as shown in will be performed. accommodate the reactor vessel Figure 2.1.3-3. arrangement shown in Figure 2.1.3-3.
- 3. The components identified in Inspection will be conducted of The ASME Code Section III Table 2.1.3-1 as ASME Code the as-built components as design reports exist for the as-Section 111 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.
- 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 Ill Table 2.1.3-1 as ASME Code in accordance with the ASME requirements are met for non-Section 111 meet ASME Code Code Section III. destructive examination of Section 111 requirements. pressure boundary welds.
- 5. The pressure boundary A hydrostatic test will be A repon exists and concludes that components (RV, CRDMs, incore performed on the components of the results of the hydrostatic test instrument guide tubes) retain the RXS required by the ASME of the pressure boundary their pressure boundary integrity Code Section Ill to be components (RV, CRDM's, at their design pressure. hydrostatically tested. incore instrument guide tubes) conform with the requirements of the ASME Code Section III.
O 3 Westinghouse oNTAACSieet020103.wp 7 69
Tier 1 Mat:ri:1 < l REACTOR SYSTEM a= == l [ \ Revision: 6 . l Effective: July 1998 _ . I Table 2.1.3 2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections, Tests, Analysis Acceptance Criteria
- 6. The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.1.3-1 can withstand equipment identified in Table 2.1.3-1 is located on the j seismic design basis loads without Table 2.1.3-1 is located on the Nuclear Island.
loss of safety function. Nuclear Island, ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of , safety function. iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or analyzed conditions. (n) LJ or analyzed conditions.
- 7. The reactor internals will i) A vibration type test will be i) A report exists and concludes withstand the effects of flow conducted on the AP600 prototype that the prototype reactor induced vibration. reactor internals. internals have no observable damage or loose parts as a result of the vibration type test.
ii) A pre-test inspection, a flow ii) The as-built reactor internals test and a post-test inspection will have no observable damage or b: conducted on the as-built loose parts. reactor internals.
- 8. The reactor vessel direct An inspection will be conducted The throat area of the direct vessel injection nozzle limits the to verify the flow area of the flow vessel injection line nozzle flow blowdown of the RCS following limiting venturi within each direct limiting venturi is less than or t.1e break of a direct vessel vessel injection nozzle. equal to 12.57 in 2 injection line.
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REACTOR SYSTEM "E Revision: 6 E 3 Effective: July 1998 { l l Table 2.1.3-2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections Tests, Analysis Acceptance Criteria 9.a) The Class IE equipment Type tests, analysis, .or a A report exists and concludes that identified ir. Table 2.13-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analysis will be performed on in Table 2.13-1 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. 9.b) The Class IE components Testing will be performed by A simulated test signal exists for identified in Table 2.13-1 are providing simulated test signals in Class lE equipment identified in powered from their respective each Class IE division. Table 2.13-1 when the assigned Class lE division. Class IE division is provided the test signal. I 9.c) Separation is provided See Tier 1 Material, Section 3J, See Tier 1 Material, Section 33, between RXS Class IE divisions, Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class IE cab!*.
- 10. The reactor lower internals Inspection of the reactor lower At least eight capsules are in the assembly is equipped with holders internals assembly for the reactor lower internals assembly.
for at least eight capsules for presence of capsules will be , storing material surveillance performed. specimens.
- 11. The RPV beltline material Testing of the Charpy V-Notch A report exists and concludes that has a Charpy upper-shelf energy specimen of the RPV beltline the initial RPV beltline Charpy of no less than 75 ft-lb. material will be performed. upper-shelf energy is no less than 75 ft-lb.
- 12. Safety-related displays of the Inspection will be perfortned for Safety-related displays identified parameters identified in retrievability of the safety-related in Table 2.13-1 can be retrieved Table 2.13-1 can be retrieved in displays in the MCR. in the MCR.
the MCR. O [ WB5tingh0USB 0:VTAACSVev6Vt020103.wpf 7 69
Tier 1 Material REACTOR SYSTEM _ J == - O Revision: 6 T Effective: July 1998 i . l Table 2.1.3 2 (cont.) Inspections, Tests, Analysis, and Acceptance Criteria Design Commitment Inspections Tests, Analysis Acceptance Criteria
- 13. The fuel assemblies and rod An analysis is perforrned of the A report exists and concludes that control cluster assemblies reactor core design. the fuel assemblies and rod intended for initial core load and cluster control rod assemblies listed in Table 2.1.3-1 have been intended for the initial core load designed and constructed in and listed in Table 2.1.3-1 have accordance with the principal been designed and constructed in design requirements, accordance with the principal design requirements.
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2.1.3-9 [ W95tiligh00SB a:uTAACSvev6Vt020103.wpf.071698
Tier 1 M;teri:1 REACTOR SYSTEM == i Revision: 6 Effective: July 1998 _ Table 2.1.3-3 Component Name Tag No. Component Location RV RXS-MV-01 Containmer.t Reactor Upper Internals Assembly RX-MI-01 Containment Reactor Lower Internals Assembly RXS-M1-02 Containment Fuel Assemblies (145 locations) RXS-FA- Containment A04/A05/A06/A07/A08/A09/ A10/B03/B04/B05/B06/B07/ B08/B09/B10/B11/C02/C03/ C04/C05/C06/C07/C08/C09/ C10/C11/C12/D01/D02/D03/ D04/D05/D06/D07/D08/D09/ D10/D11/D12/D13/E01E02/ E03E04E05E06E07E08/ E09El0/EI1E12513/F01/ F02/F03/F04/F05/F06/F07/F08/ F09/F10/F11/F12/F13/G01/ G02/G03/G04/G05/G06/G07/ G08/G09/G10/G11/G12/G13/ H01/H02/H03/H04/H05/H06/ H07/H08/H09/H10/HI1/H12/ H13/J01/J02/J03/J04/J05/J06/ J07/J08/J09/J10/Jl1/J12/Jl3/ K01/K02/K03/K04/K05/K06/ K07/K08/K09/K10/K11/K12/ K13/LO2/LO3/LO4/L05/LO6/ LO7/LO8/LO9/L10/L11/L1?> M03/M04/M05/M06/M07/ M08/M09/M10/M11/N04/N05/ N06/N07/N08/N09/N10 Rod Cluster Control Assemblies PJS-FR- Containment (RCCAs)(minimum 45 locations) B04/B06/B08/B 10/C05/ C07/C09/D02/D04/D06/D08/ D10/D12E03El1/F02/F04/ F06/F08/F12/G03/G07/G11/ H02/H04/H06/H08/H10/H12/ J03/J11/K02/K04/K06/K08/ K10/K12/LOS/LO7/M04/M06/ M08/M10 0 2.1.3-10 [ WB5tiflgh0tise o:uTAACSVev6Mt020103.wpf:071698
Tier 1 Mit: rial ! l REACTOR SYSTEM Revision: 6 l ( Effective: July 1998 t Table 2.1.3-3 Component Name Tag No. Component Location - l l Control Rod Drive Mechanisms RXS-MV- Containment ' (CRDMs)(61 Locations) 11 A07/1IBN/I1806/1IB08/ 11B10/11C03/11C05/11C07/ 11C09/1ICI1/1ID02/11D04/ I1D06/11D08/l1D10/11D12/ 11E03/11E05/11E07/11E09/ 1lEl1/1IF02/1IFN/lIF06/ 1IF08/lIF10/1IF12/1IG01/ 11G03/!:'105/11G07/11G09/ 11G11/1IG13/11H02/11H04/ 11H06/11H08/lIH10/11H12/ 11J03/11J05/11107/11J09/ 11Jl1/11K02/11KN/I1K06/ I 11K08/lIK10/11K12/11LO3/ 11LOS/liLO7/11LO9/11L11/ 11MN/11M06/11M08/l1M10/ 11N07 1 Incore Instrument Guide Tubes (38 IIS-JT- Containment ! Core Locations) G01 through G38 Source Range Detectors (4) RXS-JE-NE001A/NE001B/ Containment l NE001C/NE001D Intermediate Range Detectors (4) RXS-JE-NE002A/NE002B/ Containment ; NE002C/NE002D Power Range Detectors Lower (4) RXS-JE-NE003A/NE003B/ Containment NE003C/NE003D Power Range Detectors - Upper (4) RXS-JE-NE004A/NE004B/ Containment 1 NEONC/NE004D 0 2.1.3-11 W8Stingt)00S8 o:\lTAACSvev6\it020103.wp':071698 u__-_ _ - - - - - _ _ _ - - - _ - - - - - _ _ - - - _ - -
Tizr 1 Mit: rial REACTOR SYSTEM "6* Revision: 6 Effective: July 1998 _ 1 I Table 2.1.3-4 i Key Dimensions and Acceptable Variations of the Reactor Vessel and Internals 1 (Figure 2.1.3.2 and Figure 2.1.3-3) I Description Dimension Nominal Acceptable I or Value Variation l Elevation (inches) (inches) l (inches) l RV inside diameter at beltline (inside cladding) A 157.0 + 1.0/-1.0 l RV wall thickness at beltline (without cladding) B 8.0 + 1.0/-0.12 I RV wall thickness at bottom head (without cladding) C 6.0 + 1.0/-0.12 l RV inlet nozzle inside diameter at safe end D 22.0 +0.35/-0.10 i RV outlet nozzle inside diameter at safe end E 31.0 +0.35/-0.10 l Elevation from RV mating surface to centerline of F 62.5 +0.25/-0.25 I inlet nozzle l Elevation from RV mating surface to centerline of G 80.0 +0.25/-0.25 I outlet nozzle l Elevation from RV mating surface to centerline of H 100.0 +0.25/-0.25 i direct vessel injection nozzle i Elevation from RV mating surface to inside of RV I 378.1 + 1.0/-0.50 i bottom head (inside cladding) l Elevation from RV mating surface to top of lower J 308.8 +0.50/-0.50 l core support plate l Separation distance between bottom of upper core K 171.3 +0.20/0.20 l plate and top of lower core support with RV head in I place O 2.1.3-12 W85tirigh0use o:MTAACSVev6Vt020103 wpf:0729 8
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l Tier 1 Material CONTAINMENT SYSTEM " " " ~ ' fm Revision: 6 - E (J) Effective: July 1998 _ . 1 2.2.1 Containment System l l Design Description I The containment system (CNS) is the collection of boundaries that separates the containment l atmosphere from the outside environment during design basis accidents. l 1 The CNS is as shown in Figure 2.2.1-1 and the component locations of the CNS are as shown in i Table 2.2.14.
- 1. The functional arrangement of the CNS and associated systems is as described in the Design Description of this Section 2.2.1.
- 2. a) 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 *s designed and constructed in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.1-1 as ASME Code Section III meet ASME Code Section III requirements.
V) b) Pressure boundary welds in piping identified in Table 2.2.1-2 as ASME Code Section III meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.2.1-1 as ASME Code Section III retain their pressure boundary integdty 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.
- 6. a) The 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.
l b) The Class IE components identified in Table 2.2.1-1 are powered from their respective Class 1E division. i c) Separation is provided between CNS Class IE divisions, and between Class IE divisions and non-Class lE cable. LJ 2.2.1-1 WB5tiligh0LISB o:MTAACSvev6Vt020201.wpf:1b-o71798 s
Tier 1 Material i CONTAINMENT SYSTEM = Revision: 6 2 Effective: July 1998 -
- 7. The CNS provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere.
- 8. Containment electrical penetration assemblies are protected against currents that are greater than the continuous ratings.
- 9. Safety-related displays identified in Table 2.2.1-1 can be retrieved in the main control room (MCR).
- 10. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions.
b) The valves identified in Table 2.2.1-1 as having 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.
- 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. O 2.2.12 3 W85tinghouse o:\lTAACS\rev6\it020201.wpf:1 b-071798
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Revision: 6 Effective: July 1998 g ! Table 2.2.12 ASME Code ' Line Name Line Number Section III Instrument Air In CAS-PL-L0l6 Yes Service Air In CAS-PL-L2N Yes Component Cooling Water Supply to Containment CCS-PL-L201 Yes Component Cooling Water Outlet from Containment CCS-PL-L207 Yes Demineralized Water In DWS-PL-L245 Yes Fire Protection Supply to Containment FPS-PL-L107 Yes Spent Fuel Pool Cooling Discharge SFS-PL-L017 Yes Spent Fuel Pool Cooling Suction from Containment SFS-PL-LO38 Yes Containment Purge Inlet to Containment VFS-PL-L104, L105 L106 Yes Containment Purge Discharge from Containment VFS-PL-L203, L2N, L205 Yes I Fan Cooler Supply Line to Containment VWS-PL-LO32 Yes Fan Cooler Return Line from Containment VWS-PL-LO55 Yes RCDT Gas Out WLS-PL-LO22 Yes Waste Sump Out WLS-PL-LO73 Yes 1 \ l l h O k./ [ WBStingh00S8 o:MTAACSVev6Vt020201.wpf:1t>0 79 l
Tier 1 Material CONTAINMENT SYSTEM "= ~;;i Revision: 6 - Effective: July 1998 _ Table 2.2.13 Inspections, Tests, Analyses, and Acceptance Criteria j _ 1 Design Commitment Inspections, Tests, Analyses Acceptance Criteria I. The functional arrangement of Inspection of the as-built system The as-built CNS conforms with the CNS and associated systems will be performed. the functional arrangement as is as described in the Design described in the Design Description of this Section 2.2.1. Description of this Section 2.2.1. 2.a) 'Ihe 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 repons. 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 pipiag identified in Table 2.2.1-2 boundary welds will be performed the ASME Code Section III as ASME Code Section III meet in accordance with the ASME requirements are met for non-ASME Code Section III Code Section III. destructive examination of requirements. Pressure boundary welds. y l l l 2.2.1-10 W Westinghouse oWAACSVev6Vt020201.wpt i t>-071798 [
Tier 1 Mit: rial CONTAINMENT SYSTEM - Revision: 6 : Effective: July 1998 i Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria P 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 confinn the ASME Code Section III. fracture toughness of the materials. l 4.b) The piping identified in A hydrostatic or pressure test will A report exists and concludes that l O Table 2.2.1-2 as ASME Code be perfonned on the piping the results of the pressure test of Section III retains its pressure required by the ASME Code 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. l
- 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 j 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 r: port 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. D U l 2.2.1 11 [ W86tirigt100S8 o:VTAACSVev6Vt020201.wpf:1b-071798
Tier 1 M terial
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CONTAINMENT SYSTEM Revision: 6 Effective July 1998 _ l Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
=
6.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.2.1-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.2.1-1 as being environment can withstand the Class 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. 6.b) The Class IE 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 IE equipment identified powered from their respective in each Class IE division. in Table 2.2.1-1 when the Class IE division. assigned Class IE division is provided the test signal. l 6.c) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material, Section 3.3, between CNS Class IE divisions, Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class IE cable.
- 7. The CNS provides the safety- i) A containment integrated leak i) The leakage rate from related function of containment rate test will be performed. containment for the integrated isolation for containment leak rate test is less than L,.
boundary integrity and provides a barrier against the release of ii) Testing will be performed to ii) The containment purge fission products to the demonstrate that remotely isolation valves close within I atmosphere. operated containment iso'ation 20 seconds, SGS valves SGS-PL-I valves close within the required V040A/B and SGS-PL-V057A/B l response times, are covered in Tier 1 Material, I subsection 2.2.4, Table 2.2.4-4 I (item 11.b.ii) and all other containment isolation valves close within 60 seconds upon receipt of l an actuation signal. l e l l 2.2.1-12 W8Stiflgh0tlSe o nlTAAC S\rev6\it020201.wpf:1 b-073098 J
Tier 1 Materill CONTAINMENT SYSTEM = Revision: 6
' Effective: July 1998
~
Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria f Design Commitment Inspections, Tests Analyses Acceptance Criteria
- 8. Containment electrical An analysis for the as-built Analysis exists for the as-built penetration assemblies are containment electrical penetration containment electrical penetration I
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. l the containment electrical penetration assembly, or (2) that i 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 taermal capacity data and l prevent current from exceeding the continuous current rating of the containment electrical penetration assembly.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.1-1 can be retrievability of the safety-related in Table 2.2.1-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause those remotely operated on remotely operated valves cause remotely operated valves 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. t he controls in the MCR. perform active safety functions. 1 10.b) The valves identified in Testing will be performed on The remotely operated valves Table 2.2.1-1 as having PMS remotely operated valves listed in ] identified in Table 2.2.1-1 as l control perform an active safety Table 2.2.1-1 using real or having PMS control perform the I 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. 10.c) 'Ihe 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 control perform an active safety Table 2.2.1-1 using real or having DAS control perform the l function after receiving a signal simulated signals into the DAS. active function identified in the from DAS. table after receiving a signal from DAS. 2.2.1-13 W85tiflgh00S8 o:9T AAC Svev6Vt020201.wpf:1 b-071798
Tier 1 Material
~~
CONTAINMENT SYSTEM Revision: 6 5 Effective: July 1998 _ Table 2.2.13 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 11.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 2.2.1-1 perform an active to demonstrate the capability of operated valve changes position safety-related function to change each valve to operate under design as indicated in Table 2.2.1-1 position as indicated in the table. conditions. under design conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-verifying that the as-installed operated valves are bounded by motor-operated valves are the tests or type tests. bounded by the tests or type tests. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be charges position as indicated in performed under preoperational Table 2.2.1-1 under pre-flow, differential pressure, and operational test conditions. temperature conditions. iv) Exercise testing of the check iv) Each check valve changes valves with active safety functions position as inideated in rable identified in Table 2.2.1-1 will be 2.2.1 - 1. performed under preoperational test pressure, temperature and fluid flow conditions. 11.b) After loss of motive power, Testing of the installed valves will After loss of motive power, exh the remotely operated valves be performed under the conditions remotely operated valve identified identified in Table 2.2.1-1 assume of loss of motive power. in Table 2.2.1 1 assumes the the indicated loss of motive indicated loss of motive power power position. position. Table 2.2.1-4 Component Name Tag.No. Component Location Containment Vessel CNS-MV-01 Shield Building O W65tillg!)0USB oNTAACSVev6bt020201.wpf:1 b-0 1798 l 1
- _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___-_______-___J
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' CASSIVE CONTAINMENT COOUNG SYSTEM -
i Revision: 6 [V Effective: July 1998 1t a J 2.2.2 Par,sive Containment Cooling System Design Description The passive containment cooling system (PCS) provides heat removal from the containment during design basis events. The PCS is as shown in Figure 2.2.21 and the component locations of the PCS are as shown in Table 2.2.2-4.
- 1. The functional arrangement of the PCS is as described in the Design Description of this Section 2.2.2.
- 2. a) The components identified in Table 2.2.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.2-2 as ASME Code Section III is designed and constructed l in accordance with ASME Code Section III requirements.
- 3. a) Pressure bounday welds in components identified in Table 2.2.2-1 as ASME Code Section III 1 s meet ASME Code Section III requirements. I b) Pressure boundary welds in piping identified in Table 2.2.2-2 as ASME Code Section III meet ASME Code Section III requirements.
- 4. a) The components identified in Table 2.2.2-1 as ASME Code Section III retain their pressure l 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.
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- 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.
b) Each of the lines identified in Table 2.2.2-2 for which fun ~ional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability. c) The passive containment cooling ancillag water storage tank (PCCAWST) can withstand a seismic event.
- 6. a) The Class IE 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 function.
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I 1 Tier 1 Material PASSIVE CONTAINMENT COOLING SYSTEM
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Revision: 6 Effective: July 1998 b) The Class lE components identified in Table 2.2.2-1 are powered from their respective Class lE division. c) Separation is provided between PCS Class lE divisions, and between Class IE divisions and z non-Class lE cable.
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- 7. The PCS provides the following safety-related functions:
a) The PCS provides the . delivery of water to the outside of the containment vessel. I b) The PCS provides wetting of the outside surface of the containment vessel and the inside and I outside of the containment vessel above the operating deck is coated with an inorganic zinc 1 material. I c) The PCS provides air flow over the outside of the containment vessel by a natural circulation air flow path from the air inlets to the discharge structure. d) The PCS provides drainage of the excess water from the outside of the containment vessel through the two upper annulus drains. e) The PCS provides a flow path for long-term makeup to the passive containment cooling water storage tank (PCCWST). f) The PCS provides for long-term makeup from the PCCWST to the spent fuel pool.
- 8. The PCS provides the following nonsafety-related functions:
a) The PCS provides a PCCAWST initial inventory of cooling water for PCS delivery from hour 72 through day 7. b) The PCS provides the delivery of water from the PCCAWST to the PCCWST. c) The PCS provides water inventory for the fire protection system.
- 9. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the main control room (MCR).
- 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.2-1 to perform active functions.
b) The valves identified in Table 2.2.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS. c) The valves identified in Table 2.2.2-1 as having diverse actuation system (DAS) control perform an active safety function after receiving a signal from the DAS. [ Wes'.Inghouse owu.cswveyto202o2.wpf o
Tier 1 Mtt;ri:1 PASSIVE CONTAINMENT COOLING SYSTEM == "E Revision: 6 ~ 5 (~')s x_ Effective: July 1998 11.a) 'Ihe motor-operated and check valves identified in Table 2.2.2-1 perform an active safety- l related function to change position as indicated in the table. b) After loss of motive power, the remotely operated valves identified in Table 2.2.2-1 assume the indicated loss of motive power position. 1 Inspections, Tests, Analyses, and Acceptance Criteria l Table 2.2.2-3 specifies the inspections, tests, analyses, and associated acceptance criteria for the PCS. 1 I
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PASSIVE CONTAINMENT COOLING SYSTEM Revision: 6 = Effective: July 1998 _ Table 2.2.2-2 Functional ASME Code Capability Line Name Line Number Section 111 Required PCCWST Discharge Lines PCS-PL-LO01 A/B/C/D Yes Yes PCCWST Discharge Crossconnect PCS-PL-LOO 2 Yes Yes Line PCCWST Discharge Header Lines PCS-PL-LOO 3A, LOO 3B Yes Yes Post-72-hour PCCWST Makeup PCS-PL-LOO 4 Yes Yes Supply Line Connection PCS-PL-LO51 Post-72-hour FCCWST Makecp PCS-PL-LO29 Yes Yes Supply Line PCS-PL-LO54 Post-72-hour SFS Makeup PCS-PL-L017 Yes Yes PCS-PL-LO49 9 1 l O WBStingh00S8 oNTAACSVev6Mt020202.wpf 0 798 l
Tier 1 Miterial PASSIVE CONTAINMENT COOLING SYSTEM _ . - . _ Revision: 6 - Effective: July 1998 i Table 2.2.2 3 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement Inspection of the as-built system The as-built PCS conforms with of the PCS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.2.2. Description of this Section 2.2.2.
2.a) The components identified Inspection will be conducted of The ASME Code Section III 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. 2.b) 'Ihe 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 ASMB design reports. built piping identified in constructed in accordance with Table 2.2.2-2 as ASME Code ASME Code Section III Section III. s 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 l 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 j Section III requirements. pressure boundary welds. 3.b) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that piping identified in Table 2.2.2-2 boundary welds will be performed the ASME Code Section III I as ASME Code Section III meet in accordance with the ASME requirements are met for non-i ASME Code Section III Code Section III. destructive examination of requirements. pressure boundary welds. 4.a) The components identified A hydrostatic test will be A report exists and concludes that j 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 l requirements of the ASME Code Section III. D 0 2.2.2-7 Westinghouse o \lTAACS\rev6\it020202.wpf.071798
Tier 1 M:teri:1 PASSIVE CONTAINMENT COOLING SYSTEM - - Revision: 6 E Effective: July 1998 Table 2.2.2-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.2.2-2 as ASME Code 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 2.2.2-2 as ASME Code pressure. Section III confctm with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.2.2-1 can withstand equipment and valves identified in Table 2.2.2-1 is located on the seismic design basis loads Table 2.2.2-1 are located on the Nuclear Island. without loss of safety function. Nuclear Island. ii) Type tests, analyses, or a ii) A report exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed iii) The report exists and for the existence of a report concludes that the as-installeet verifying that the as-installed equipment including anchorare is equipment including anchorage is seismically bounded by the tested seismically bounded by the tested or analyzed conditions. or analyzed conditions. 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that in Table 2.2.2-2 for which the existence of a report each of the as-built lines functional capability is required concluding that the as-built piping identified in Table 2.2.2-2 for is designed to withstand meets the requirements for which functional capability is combined normal and seismic functional capability. required meets the requirements design basis loads without a loss for functional capability, of its functional capability. 5.c) The PCCAWST can Inspection will be performed for A report exists and concludes that withstand a seismic event. the existence of a report verifying the as-installed PCCAWST and that the as-installed PCCAWST its anchorage are designed using and its anchorage are designed seismic Category 11 methods and using seismic Category 11 methods criteria. and criteria. O W Westinghouse 2.2.2 8 o:WAACSvee020202.wpf:071798
Tier 1 Mat: rial PASSIVE CONTAINMENT COOLING SYSTEM - Revision: 6 - ( Effective: July 1998 Table 2.2.2-3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 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 IE equipment identified being qualified for a harsh performed on Class IE equipment in Tables 2.2.2-1 as being environment can withstand the located in a harsh environment. qualified for a harsh environment environmental conditions that can withstand the environmental would exist before, during, and conditions that would exist before, following a design basis accident during, and following a design without loss of safety function basis accident without loss of for the time required to perform safety function for the time the safety function. required to perform the safety function. 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 lE division. in Table 2.2.2-1 when the Class IE division. assigned Class lE division is provided the test signal. I 6.c) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material, Section 3.3, between PCS Class lE divisions, Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class IE cable. i 2.2.2-9 W85tiflgh0US8 o:VTAACSVev6Vt020202.wpf.071798
Tier 1 Materill PASSIVE CONTAINMENT COOLING SYSTEM -- - Revision: 6 1 Effective: July 1998 _ 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 parallei greater than or equal to: flow paths.
- 442 gpm at a PCCWST water i l level of 23.70 ft 0.25 ft above the lowest standpipe l -
123.5 gpm at a PCCWST water level of 20.65 ft 0.25 ft above the lowest standpipe l - 72.5 gpm at a PCCWST I water level of 13.05 ft 0.25 ft above the lowest standpipe, ii) Testing and or analysis will be performed to demonstrate the ii) When tested and/or analyzed PCWST inventory provides with both flow paths delivering 72 hours of cooling. and an initial water level at 24.25 + 0.25, - 0.00 ft, the water inventory provides greater than or equal to 72 hours of flow with a flow rate greater than or equal to 62 gpm. iii) Inspection will be performed to determine the PCCWST iii) The elevations of the standpipes elevations. standpipes above the bottom i standpipe are: 6.1 ft 0.25 ft 14.0 ft 0.25 ft
- 21.6 ft 0.25 ft O'
2.2.2-10 g W85tilighouse o:MTAACSvev6Vt020202.wpf:071798 l l 1
l l Tier 1 Matirill l m PASSIVE CONTAINMENT COOLING SYSTEM _ l I Revision: 6 5 V Effective: July 1998 Table 2.2.2 3 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment laspections, Tests, Analyses Acceptance Criteria 1 7.b) The PCS provides wetting i) Testing will be performed to i) A report exists and concludes I of the outside surface of the measure the wetted surface of the that with water in the PCCWST I containment vessel and the inside containment vessel from either of at the following levels, water j l and the outside of the the two parallel flow paths to the delivery to the containment shell l containment vessel above the containment vessel. provides coverage measured at the I operating deck is coated with an spring line that is equal to or I inorganic zine material, greater than the corresponding coverage used to calculate peak containment pressure in the safety analysis. l - 23.70 0.25 ft above the lowest standpipe 20.65 0.25 ft above the l lowest standpipe I - 13.05 0.25 ft above the (p*/ lowest standpipe ii) Inspection of the containment ii) A report exists and concludes i vessel exterior coating will be that the containment vessel conducted. exterior surface is coated with an I inorganic zine coating above i elevation 135'-3" l lii) Inspection of the containment iii) A report exists and concludes I vessel interior coating will be that the containment vessel I conducted. interior surface is coated with an I inorganic zine coating above 7' I above the operating deck. 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 performed. following locations: I containment vessel 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 7.d) The PCS provides drainage Testing will be performed to With a water level within the l 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.
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Tier 1 Materici PASSIVE CONTAINMENT COOUNG SYSTEM _ E= Flevision: 6 5 Effective: July 1998 _ 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-term makeup connection to makeup connection, each PCS the PCCWST. recirculation pump delivers greater than or equal to 62 gpm when tested separately.
7.f) 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 equal to 50 gpm. ii) Inspection of the PCCWST ti) The volume of the PCCWST will be performed. is greater than 400,000 gallons. 8.a) Ae PCS provides a Inspection of the PCCAWST will ~ihe volume of the PCCAWST is PCCAWST initial inventory of be performed. greater than 363,000 gallons. cooling water for PCS delivery from hour 72 through day 7. 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 Tier 1 Material, subsection See Tier 1 Material, subsection inventory for the fire protection 2.3.4, Fire Protection System. 2.3.4, Fire Protection System. system.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.2-1 can be retrievability of the safety-related in Table 2.2.2-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause the remotely operated on the remotely operated valves cause remotely operated valves valves identified in Table 2.2.2-1 identified in Table 2.2.2-1 using identified in Table 2.2.2-1 to to perform active functions. the controls in the MCR. perform active functions. 1 1 0 2.2.2-12 l W Westinghouse o:MTAACSVev6Mt020202.wpf:071798 l . . _ _ _ _ _ _ _ _ _ _ _ _ -
Tier 1 Miterial PASSIVE CONTAINMENT COOLING SYSTEM y.- Revision: 6
- Effective: July 1998 Table 2.2.2-3 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 10.b) The valves identified in Testing will be performed on the The remotely operated valves Table 2.2.2-1 as having PMS remotely opo ed valves in identified in Table 2.2.2-1 as control perform an active safety Table 2.2.1 I using real or having PMS control perform the function after receiving a signal simulated signals into the PMS. active function identified in the from the PMS. table after receiving a signal from the PMS. 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. 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
.O position as indicated in the table. design conditions under design conditions.
O ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-verifying that the as-installed operated valves are bounded by motor-operated valves are bounded the tested conditions. by the tested conditions. iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under preoperational Table 2.2.2-1 under preoperational flow, differential pressure, and test conditions. temperature conditions. iv) Exercise testing of the check iv) Each check valve changes 1 valves with active safety functions position as indicated in l identified in Table 2.2.2-1 will be Table 2.2.21.
- performed under preoperational test pressure, temperature and fluid flow conditions.
11.b) After loss of motive Testing of the installed valves will After loss of motive power, each power, the remotely operated be performed under the conditions remotely operated valve identified i valves identified in Table 2.2.2-1 of loss of motive power, in Table 2.2.2-1 assumes the assume the indicated loss of indicated loss of motive power motive power position. position. O 2.2.2-13 W8Stingh0US8 oNTAACS\rev6\it020202.wpt071798 w________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _
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PASSIVE CONTAINMENT COOLING SYSTEM Revision: 6 - 7 Effective: July 1998 - Table 2.22 4
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Component Name Tag No. Component Location PCCWST PCS-MT-01 Shield Building PCCAWST PCS-MT-05 Yvd Recirculation Pump A PCS-MP-01A Auxiliary Building Recirculation Pump B PCS-MP-Ol B Auxiliary Building O t i l O w ==e-Se . _ . _ _ J: l
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Tier 1 Material /3 PASSIVE CORE COOLING SYSTEM ._ c () Revision: 6 Effective: July 1998 1 , 2.2.3 Passive Core Cooling System Design Description The passive core cooling system (PXS) provides emergency core cooling during design basis events. The PXS is as shown in Figure 2.2.3-1 and the component locations of the PXS are as shown in Table 2.2.3-5.
- 1. The functional arrangement of the PXS is as described in the Design Description of this Section 2.2.3.
- 2. a) The components identified in Table 2.2.3-1 as ASME Code Section III are designed and constructed in ucordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.3-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.
V b) Pressure boundary welds in piping idemified in Table 2.2.3-2 as ASME Code Section III meet ASME Code Section III requirements.
- 4. a) "Ihe components identified in Figure 2.2.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
I b) The piping identified in Table 2.2.3-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.3-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
- 6. Each of the as-built lines identified in Table 2.2.3-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
- 7. a) The Class IE equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required (3
V to perform the safety function. , l 2.2.3-1 T Westinghouse oNTAACSVevfNt020203,wpf:1 t>-073098 i l i
I l Tier 1 Material {
==
PASSIVE CORE COOLING SYSTEM - Revision: 6 - 5: Effective: July 1998 _ . I I b) The Class IE components identified in Table 2.2.3-1 are powered from their respective Class IE division. c) Separation is provided between PXS Class IE divisions, and between Class lE divisions and non-Class IE cable.
- 8. The PXS provides the following safety-related functions:
a) Ihe PXS provides containment isolation of the PXS lines penetrating the containment. b) The PRHR HX provides core decay heat removal during design basis events. c) The CMTs, accumulators, in-containment refueling water storage tank (IRWST) and containment recirculation provide reactor coolant system (RCS) makeup, boration, and safety injection during design basis events. d) The PXS provides pH adjustment of water flooding the containment following design basis accidents.
- 9. The PXS has the following features:
a) The PXS provides a function to cool the outside of the reactor vessel during a severe accident. b) The accumulator discharge check valves (PXS-PL-V028A/B and V029A/B) are of a different check valve type than the CMT discharge check valves (PXS-PL-V016A/B and V017A/B). I c) The equipment listed in Table 2.2.3-6 has sufficient thranal lag to withstand the effects of I identified hydrogen bums associated with severe accidents.
- 10. Safety-related displays of the parameters identified in Table 2.2.3-1 can be retrieved in the main control room (MCR).
I1. a) Controls exist in the MCR to cause the remotely operated valves identified in l Table 2.2.3-1 to perform their active function (s). b) The valves identified in Table 2.2.3-1 as having protection and safety monitoring system (PMS) control perform their active function after receiving a signal from the PMS. c) The valves identified in Table 2.2.3-1 as having diverse actuation system (DAS) control perform their active function after receiving a signal from the DAS.
- 12. a) The motor-operated and check valves identified in Table 2.2.3-1 perform an active safety- i related function to change position as indicated in the table.
2.2.3-2 W Westinghouse oWAACSVev6%t020203 wpf:1b-072998 L _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - . - _ _ - - - -
TI:r 1 Mat:ri:1 PASSIVE CORE COOLING SYSTEM ~~ ::= Revision: 6 :- q ,/ Effective: July 1998 _ 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.
- 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. i ! 3 V l l l U 2.2.3-3 3 W85tingh00S8 o:VTAACSvev6\it020203.wpf:1 b-071798
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m *:$; 9-g-} Ea, l y at d ni el oi r s s s ib i e e e o n ap ue q Y Y t c Y N u a FC R k rek a a o o o o o ef e N N N N L eBBr l l E e n I s s s s Md S oi o e e e e - Y Y Y Y A Ct ce S A B 2 2 3 3 - l 2- 1 3 L L- - 2 S S 2 r e X P P X le b b m A, B , B B a u 1 1 2 1 T N 3 1 3 1 4 l 4 l e n L L L - - L - i S S S S L XP PX P XP X A, B A, A, 3 3 2 1 1 l 4 4 i l l L - Li - L- L - S S S S X X X X P P P P A B e e i i n n l l n n e e o o i n m i ai L t t a a l l n N u u c c ia e r r r n i c ic D i e e r L r r te t t n n t u e e m mG ina n T ia S t t n n o o W C C R I i EE :g s Em 0 NC8ll!amhIe od e
- _ _ - _ - _ - _ - _ _ _ _ - - - - - - - ~ Tirr 1 Mitzrill PASSIVE CORE COOLING SYSTEM 67 T Revision: 6 O Effective: July 1998 5 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-V021 B Yes (Position) - (Position) Accumulated A Discharge Isolation Valve PXS-PL-V027A Yes (Position) - (Position) O Accumulator B Discharge isolation Valve (Position) PXS-PL-V027B Yes (Position) - PRHR HX Control Valve (Position) PXS-PL-V108 A Yes (Position) - PRHR HX Control Valve (Position) PXS-PL-V108B Yes (Position) - Containment Recirculation A Isolation PXS-PL-Vi l 8 A Yes (Position) - Valve (Position) Containment Recirculation B Isolation PXS-PL-Vi l 8B Yes (Position) - Valve (Position) Containment Recirculation A Isolation PXS-PL-V120A Yes (Position) - Valve (Position) Containment Recirculation B Isolation PXS-PL-V1208 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 (-) indicates not applicable. O 3 Westingh0use 2.2.3-13 oNTAACSVev6\it020203 wpf.1b-071798
Tier 1 Mat:ri:.1 PASSIVE CORE COOLING SYSTEM == Revision: 6 Effective: July 1998 l Table 2.2.3-3 (cont.) Equipment Tag No. I Display Control Function IRWST Injection B Isolation Squib PXS-PL-V123B Yes (Position) - (Position) IRWST Injection A Isolation Squib PXS-PL-V125 A Yes (Position) - (Position) IRWST Injection B Isolation Squib PXS-PL-V125B Yes (Position) - (Position) IRWST Gutter Bypass Isolation Valve PXS-PL-V130A Yes (Position) - (Position) IRWST Gutter Bypass Isolation Valve PXS-PL-V130B Yes (Position) - (Position) Accumulator A Level Sensor PXS-021 Yes - Accumulator B Level Sensor PXS-022 Yes - Accumulator A Level Sensor PXS-023 Yes - Accumulator B Level Sensor PXS-024 Yes - PRHR HX Inlet Temperature Sensor PXS-064 Yes - IRWST Surface Temperature Sensor PXS-041 Yes - IRWST Surface Temperature Sensor PXS-042 Yes - IRWST Bottom Temperature Sensor PXS-043 Yes - IRWST Bottom Temperature Sensor PXS-044 Yes - Note Dash (-) indicates not applicable. O' [ W8Stingh00S8 o:\lTAACSVev6\it020203.wpf:1 071798 , l l
Tier 1 Mst:ri1I PASSIVE CORE COOLING SYSTEM ; Revision: 6 =5
=
t Effective: July 1998 I Table 2.2.3-4 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 PXS conforms with the PXS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.2.3. Description of this Section 2.2.3.
2.a) The components identified Inspection will be conducted of The ASME Code Section III in Table 2.2.3-1 as ASME Code the as-built components as design reports exist for the as-built Section III are 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) The piping identified in Inspection will be conducted of The ASME Code Section III Table 2.2.3-2 as ASME Code the as-built piping as design reports exist for the as-built Section III is designed and documented in the ASME design piping identified in Table 2.2.3-2 constructed in accordance with reports. as ASME Code Section III. ASME Code Section III requirements. O 3.a) Pressure boundary welds in components identified in Table 2.2.3-1 as ASME Code Inspection of the as-built pressta boundary welds will be A report exists and concludes that the ASME Code Section III 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-ASME Code Section III the ASME Code Section III. destructive examination of pressure requirements. boundary welds. O [ W85tiflgil0t!Se 2.2.3-15 o:VTAAC Svev6Vt020203.wpf:1 b-071798
Tier 1 Materici PASSIVE CORE COOLING SYSTEM == 7= Revision: 6 Effective: July 1998 - l 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 l Figure 2.2.3-1 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 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. 5.b) Each of the lines identified Inspection will be performed A report exists and concludes that in Table 2.2.3-2 for which verifying that the as-built piping each of the as. built lines identified functional capability is required is meets the requirements for in Table 2.2.3-2 for which designed to withstand combined functional capability, functional capability is required normal and seismic design basis meets the requirements for loads without a loss of its functional capability, functional capability. O 2.2.3-16 3 Westinghouse oMAACSvev6M320203.wpf;1b-071798
_ - _ _ _ _ _ _ - - - _ - - - _ - - - - - - - - - - - - -- - -- -~- ~ Tist 1 Mstzrill PASSIVE CORE COOLING SYSTEM - Revision: 6 ~
=
Effective: July 1998 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation report exists identified in Table 2.2.3-2 as the existence of an LBB and concludes that the LBB designed for LBB meets the LBB evaluation report or an acceptance criteria are met by the criteria, or an evaluation is evaluation repon on the as-built RCS piping and piping performed of the protection from protection from dynamic effects materials, or a pipe break I the dynamic effects of a rupture of a pipe break. Tier 1 Material, evaluation report exists and of the line. Section 3.3, Nuclear Island concludes that protection from the Buildings, contains the design dynamic effects of a line break is descriptions and inspections, provided.
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 environment can withstand the Class IE equipment located in a for a harsh environment can environmental conditions that harsh environment. withstand the environmental would exist before, during, and conditions that would exist before, following a design basis accident during, and following a design without loss of safety function for basis accident without loss of the time required to perform the safety function for the time safety function. required to perform the safety function. 7.b) The Class lE 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 lE division. Table 2.2.3-1 when the assigned Class IE division. Class IE division is provided the test signal. I 7.c) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material, Section 3.3, between PXS Class IE divisions, Nuclear Island Buildings. Nuclen Island Buildings. and between Class lE divisions and non-Class IE cable. I 8.a) The PXS provides See Tier 1 Material, subsection See Tier 1 Material, subsection containment isolation of the PXS 2.2.1. Containment System. 2.2.1, Containment System. lines penetrating the containment. W85tiflgh0L'Se 2.2.3-17 o:\lTAACSVevmit020203 wpf.1b-071798
Tier 1 Mat:ri;l PASSIVE CORE COOLING SYSTEM : EE Revisiori: 6 = Effective: July 1998 _ Table 2.2.3-.t (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design 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 basis events. will be performed to determine with the design basis number of the heat transfer from the HX. PRHR HX tubes plugged is: For the test, the reactor coolant hot leg temperature will be 21.06 x 10" Blu/hr with 520 F HL initially at 2 540*F with the and 120*F IRWST temperatures reactor coolant pumps stopped. The IRWST water level for the 2 4.34 x 10' Bru/hr with 420 F HL test will be above the top of the and 212*F IRWST temperatures HX. The JRWST water temperature is not specified for the test. The test will continue until the hot leg temperature decreases below 420*F. 8.c) The PXS provides RCS i) A low-pressure injection test i) The injection line flow makeup, boration, and safety and analysis for each CMT, each resistance from each source is as injection during design basis accumulator, each IRWST follows: events. injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve (s) in the line being tested. Test fixtures may be used to simulate squib valves. CMTs: CMTs: Each CMT will be initially filled The calculated flow resistance with water. All valves in these between each CMT and the lines will be open during the reactor vessel is test. 2 3.07 x 10 5 ft/gpm2 and 5 3.84 x 10-5 ft/gpm'. Accumulators: Accumulators: Each accumulator will be The calculated flow resistance partially filled with water and between each accumulator and pressurized with nitrogen. All the reactor vessel is 21.49 x 10 5 valves in these lines will be ft/gpm and s 1.86 x 10 ft/gpm 2. open during the test. Sufficient flow will be provided to fully open the check valves. 1 ) O 2.2.3-18 W Westinghouse o:VTAACS\rev6Mt020203.wpt 1 b-071798
Tisr 1 M tsrial PASSIVE CORE COOLING SYSTEM == Revision: 6 Is Effective: July 1998 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 calcular:d flow resistance filled with water. All valves in for each IRWST injection line these lines will be open during between the IRWST and the the test. Sufficient flow will be reactor vessel is 21.33 x 10 5 provided to fully open the check ft/gpm and valves. 5 2.66 x 10'5 ft/gpm 2. 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 vessei is Sufficient flow will be provided 5 2.17 x 10 ft/gpm 2, to fully open the check valves. ii) A low. pressure test and ii) The flow resistance from analysis will be conducted for the cold leg to the CMT is O each CMT to determine piping flow resistance from the cold leg to the CMT. The test will be 5 7.69 x 10 ft/gpm 2, performed by filling the CMT via the cold leg balance line by operating the normal residual
; heat removal pumps.
3 W8Stingh0058 2.2.3-19 oNT AACSirev6\it020203.wpf:1 b-071798
Tier 1 M:t: rial
===
PASSIVE CORE COOLING SYSTEM Revision: 6 - Effective: July 1998 Table 2.2.3 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria iii) Inspections of the routing of lii) These lines have no downward the following pipe lines will be sloping sections between the conducted: connection to the RCS and the high point of the line.
- CMT inlet line, cold leg to high point
- PRHR HX inlet line, hot leg to high point iv) Ir.spections of the elevation iv) The maximum elevation of the of the following pipe lines will top inside surface of these lines is be conducted: less than the elevation of:
- IRWST injection lines; - IRWST bottom inside surface IRWST connection to DVI nozzles
- Containment recirculation - IRWST bottom inside surface lines; containment to IRWST lines
- CMT discharge lines to DVI - CMT bottom inside surface connection
- PRHR HX outlet line to SG - PRHR HX lower channel head connection top inside surface v) Inspections of the elevation v) The elevation of the bottom of the following tanks will be inside tank surface is higher than conducted: the direct vessel injection nozzle I centerline by 6e following:
- CMTs - CMTs 2 7.5 ft
- IRWST - IRWST 2 3.4 ft vi) Inspections of each of the vi) The calculated volume of each following tanks will be of the following tanks is as conducted: follows:
- CMTs - CMTs 2 2000 ft'
- Accumulators - Accumulators 2 2000 ft'
- IRWST - IRWST 2 75,000 ft' between the tank outlet connection and the tank overflow 1 1
O O 80 oNTAACS\rev6\it020203.wpt1 07 79
i Tier 1 M t: rial PASSIVE CORE COOLING SYSTEM == =E Revision: 6 7 E (mj Effective: July 1998 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment Inspections, Tests, Analyses Acceptance Criteria e vii) Inspection of the as-built vii) Plates located above each components will be conducted containment recirculation screen for plates located above the are no more than 10 ft above the containment recirculation top of the screen and extend out at screens. least 10 ft from the trash rack portion of the screen. I viii) Inspections of the IRWST viii) The screen surface area and containment recirculation (width x height) of each screen is 2 screens will be conducted. 20 7 ft . The bottom of the containment recirculation screens is 2 2 ft above the loop compartment floor. ix) Inspections will be ix) The type ofinsulation used on I conducted of the insulation used these lines and equipment is a 1 inside the containment on ASME metal reflective type or a suitable i Class I lines and on the reactor equivalent. p) i vessel, reactor coolant pumps, pressurizer and steam generators. x) Inspections will be conducted x) A report exists and concludes of the as-built nonsafety-related that the coatings used on these coatings or of plant records of surfaces has a dry film density of the nonsafety-related coatings 2100 lb/ft'. used inside containment on walls, floors, ceilings, structural steel which is part of the building structure and on the polar crane. xi) Inspection of the as-built xi) The CMT inlet diffuser has a CMT inlet diffuser will be flow area 2165 in 2, conducted. xii) Inspections will be xii) The centerline of each upper conducted of the CMT level level tap line at the lee for each j sensors (PSX-11 A/B/D/C, - level sensor is located I" 1" 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. lines. v W85tingh0tlS8 onlTAACSvev691020203.wpf.1 071798 L____________________________
1 l Tier 1 Mit: rial , l l l PASSIVE CORE COOLING SYSTEM - Revision: 8 E i Effective: July 1998 _ Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria l l Design Commitment Inspections, Tests, Analyses Acceptance Criteria I xiii) Inspections will be xiii) A report exists and concludes I conducted of the materials used that these surfaces are stainless I in the vicinity of the steel or that coatings used on these I containment recirculation screens surfaces are qualified to remain I or analysis, type tests, or a attached to these surfaces during I combination of analysis and type design basis events. I tests will be performed on I coatings used on surfaces in the I vicinity of the containment i recirculation screens. In the I vicinity of the containment I recirculation screens includes i surfaces located above the l bottom of the recirculation i screens up to and including the I bottom surface of the plate I discussed in Table 2.2.3-4, I item 8.c.vii, out to 10 feet in I front and 10 feet to the side of I the screen face. 8.d) The PXS provides pH Inspections of the pH adjustment Two pH adjustment baskets exist, adjustment of water flooding the baskets will be conducted. cach with a calculated volume containment following design 2107 ft'. basis accidents. The pH baskets are located below plant elevation 107 ft,2 in. 9.a) The PXS provides a i) A flow test and analysis for i) The calculated flow resistance function to cool the outside of the each IRWST drain line to the for each IRWS*1 drain line reactor vessel during a severe containment will be conducted. between the IRWST and the accident. The test is initiated by opening containment is s 1.38 x 104 isolation valves in each line. ft/gpm 2 Test fixtures may be used to simulate squib valves. ii) Inspections of the as-built ii) The combined total flow area reactor vesselinsulation will be of the water inlets is not less than j performed. 6 ft 2. The combined total flow l area of the steam outlet (s) is not less than 7.5 ft . l 1 2.2.3-22 [ W8Stiflgt100S8 oNT AACSvev6\it020203.wpt:1 b-073098 l
Tier 1 Material PASSIVE CORE COOLING SYSTEM Revision: 6 ~s
- E
! Effective: July 1998 Table 2.2.3-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria A report exists and concludes that the minimum flow area between the vessel insulation and reactor vessel for the flow path that vents steam is not less than 7.5 ft: considering the maximum deflection of the vesselinsulation with a static pressure of 12.95 ft of water. iii) Inspections will be iii) A flow path with a flow area conducted of the flow path (s) not less than 6 ft exists from the from the loop compartments to loop compartment to the reactor the reactor vessel cavity. vessel cavity. 9.b) The accumulator discharge An inspection of the accumulator The accumulator discharge check check valves (PXS-PL-V028A/B and CMT discharge check valves valves are of a different check and V029A/B) are of a different is performed. valve type than the CMT discharge O check valve type than the CMT discharge check valves (PXS-PL-check valves. V016A/B and V017A/B). I 9.c) The equipment listed in Tests, analyses, or a combination A report exists and concludes that i Table 2.2.3-6 has sufficient of tests and analyses will be the thermal lag of this equipment I thermal lag to withstand the performed to determine the is greater than the value required. I effects of identified hydrogen thermal lag of this equipment. I burns associated with severe I accidents.
- 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 2.2.31 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 l to perfotm 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. 2.2.3-23 W85tlI1gt100S8 o:\lTAACS\rev6\it020203 wpf;1b-071798
Tier 1 Materict i
* "E PASSIVE CORE COOLING SYSTEM Revision: 6 Effective: July 1998 Table 2.2.3-4 (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) Squib valves receive an Table 2.2.31 as having PMS the squib valves identified in electrical signal at the valve control perform their active Table 2.2.3-1 using real or electrical leads that is capable of function after receiving a signal simulated signals into the PMS actuating the ulve 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. iii) Testing will be perfc,rmed to iii) These valves open within demonstrate that remotely 20 seconds after receipt of an operated PXS isolation valves actuation signal. PXS-V014A/B, V015A/B, V108A/B open within the required response times. I1.e) The valves identified in i) Testing will be performed on i) Squib valves receive an Table 2.2.3-1 as having DAS the squib valves identified in electrical signal at the valve control perform their active Table 2.2.3-1 using real or electrical leads that is capable of function after receiving a signal simulated signals into the DAS actuat - the valve after a signal is from the DAS. without stroking the valve. input ! the DAS. ii) Testing will be performed on ii) Remottiy operated valves other die 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 2.2.31 perform are 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-inv.alled valves are bounded by the tests or motor-operated valves are type tests. bounded by the tests or type tests. 1 O l 2.2.3-24 j W Westinghouse omTAAcsvevevto2o203.wpf;1 b-072998 l l
Tier 1 Mat: rial PASSIVE CORE COOLING SYSTEM - g Revision: 6 . Effective: July 1998 j 1 Table 2.2.3-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l iii) Tests of the as-instenea iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under preoperational Table 2.2.3-1 under preoperational 4 flow, differential pressure, and test conditions. temperature conditions. iv) Exercise testing of the check iv) Each check valve changes valves with active safety position as indicated in functions identified in Table 2.2.3-1. Table 2.2.3-1 will be performed under preoperational test pressure, temperature and fluid flow conditions. 12.b) After loss of 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 of loss of motive in Table 2.2.3-1 assumes the the indicated loss of motive power, indicated loss of motive power [N power position. position.
- 13. Displays of the parr. meters 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. i I l , l l l i l 2.2.3-25 W W85tiflgh0US8 o NTAACSVev6'Jt020203.wpf:1 b-071798
Tier 1 Material PASSIVE CORE COOLING SYSTEM ]E Revision: 6 Effective: July 1998 l l Table 2.2.3-5 I Component Name Tag No. Component Location Passive Residual Heat Removal Heat PXS-ME-01 Containment Building Exchanger (PRHR HX) Accumulator Tank A PXS-MT-01 A Containment Building Accumulator Tank B PXS-MT-OlB Containment Building i Core Makeup Tank (CMT) A PXS-MT-02A Containment Building CMTB PXS-MT-02B Containment Building IRWST PXS-MT-03 Containment Building IRWST Screen A PXS-MY-YOI A Containment Building IRWST Screen B PXS-MY-Y0lB Containment Building Containment Recirculation Screen A PXS-MY-Y02A Containment Building Containment Recirculation Screen B PXS-MY-Y02B Containment Building pH Adjustment Basket A PXS-MY-YO3A Containment Building pH Adjustment Basket B PXS-MY-YO3B Containment Building I h 2.2.3-26 [ W8Sti!1gh0US8 0:MTAACSVev6Mt020203 wpf;1t>071798
Tier 1 Matirial PASSIVE CORE COOLING SYSTEM : _. Revision: 6 :: I Effective: July 1998 i , I Table 2.2.3-6 l Equipment Tag No. Function l Containment Air Sample Containment PSS-PL-V008 Transfer open i Isolation Valve IRC I Containment Pressure Sensors PCS-005, 006, 007, 008 Sense pressure i RCS Wide Range Pressure Sensors RCS-140A, B, C, D Sense pressure l I SGI Wide Range Level Sensors SGS-Ol l, 012,013,014 Sense level ' l SG2 Wide Range Level Sensors SGS-016, 017, 018, 019 Sense level i Hydrogen Ignitors VLS-EH-01 through 64 Ignite hydrogen l Electrical Penetrations VUS-JY-E01, 02, 06, 09, Maintain containment i 10, 11, 12, 13, 14, 15, 16, boundary i 17, 18, 21, 22, 23, 24, 25, i 26,27,28,29,30,31,32 O V l 1 i (
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2.2.3-27 3 W8Stingh00S8 oNTAACSvev6Vt020203 wpf:1t>071798
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1 Tier 1 Material l 1 STEAM GENERATOR SYSTEM () A Revision: 6
- Effective: July 1998 i 2.2.4 Steam Generator System Design Description t
l The steam generator system (SGS) and portions of the main and startup feedwater system (FWS) transport and control feedwater from the condensate system to the steam generators during normal j operation. The SGS and ponions of the main steam system (MSS) and turbine system (MTS) ' transpon and control steam from the steam generators to the turbine generator during normal operations. These systems also isolate the steam generators from the turbine generator and the condensate system during design basis accidents. The SGS is as shown in Figure 2.2.4-1, sheets 1 and 2, and portions of the FWS, MSS, and MTS are as shown in Figure 2.2.4-1, sheet 3. and the locations of the components in these systems is as shown l in Table 2.2.4-5.
- 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. j
- 2. a) The components identified in Table 2.2.4-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements. i 3
l (b b) The piping identified in Table 2.2.4-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements. 1
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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.
- 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.
- 5. a) The seismic Category I equipment identified in Table 2.2.4-1 can withstand seismic design j 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 designed to withstand combined normal and seismic design basis loads without a loss of its functional capability. O 2.2.4-1 W85tiflgh00S8 c:VTAACSvev6Vt020204.wpt1b 071798
Tier 1 Materi-1 STEAM GENERATOR SYSTEM ~= Revision: 6 5 Effective: July 1998 1
- 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 a rupture of the line.
- 7. a) The Class IE equipment identified in Table 2.2.4-1 as being qualified for a harsh environment i can withstand the environmental conditions that would exist before, during, and following a !
design basis accident without loss of safety function for the time required to perfonn the safety function. b) The Class IE components identified in Table 2.2.4-1 are powered from their respective Class IE division. c) Separation is provided between SGS Class 1E divisions, and between Class lE divisions and non-Class IE 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 ac. ordance with Section III of the ASME Boiler and Pressure Vessel Code. b) During design basis events, the SGS limits steam generator blowdown and feedwater flow to the steam generator. c) The SGS preserves containtnent 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 ft:nctions:
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 delivery of startup feedwater to the steam generator and venting of steam from the steam generators to the atmosphere.
- 10. Safety-related displays identified in Table 2.2.4-1 can be retrieved in the main control room (MCR).
- 11. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.4-1 to perform active functions.
O 2.2.4-2 [ WBSilflgh0USB o:\lTAACSirev6 Tit 020204.wpf:1 b-071798
Tier 1 Mat:ri:1 STEAM GENERATOR SYSTEM - - - - m Revision: 6 O ; Effective: July 1998 1 b) The valves identified in Table 2.2.4-1 as having PMS control perform an active safety function i after receiving a signal from PMS. l
- 12. a) The motor-operated valves identified in Table 2.2.4-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.4-1 assume the indicated loss of motive power position. Inspections, Tests, Analyses, and Acceptance Criteria Table 2.2.4-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the SGS. 1 l I 1 O 2.2.4-3 ! W85tingh00S8 o:VTAACSVev6%it020204.wpf:1 b-071798
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Tier 1 Matri:1 STEAM GENERATOR SYSTEM -T Revision: 6 E Effective: July 1998 _ Table 2.2.4 3 E,quipment Name Tag No. Control Function Turbine Stop Valve MTS-PL-V001 A Close Turbine Stop Valve MTS-PL-V001B Close Turbine Control Valve MTS-PL-V002A Close Turbine Control Valve MTS-PL-V002B Close Turbine Stop Valve MTS-PL-V003A Close Turbine Stop Valve MTS-PL-V003B Close Turbine Control Valve MTS-PL-V004A Close Turbine Control Valve MTS-PL-V004B Close Turbine Bypass Control Valve MSS-PL-V001 Close Turbine Bypass Control Valve MSS-PL-V002 Close Turbine Bypass Control Valve MSS-PL-V003 Close Turbine Bypass Control Valve MSS-PL-V004 Close Moisture Separator Reheat Supply Steam Control Valve MSS-PL-V016 Close Min to Startup Feedwater Crossover Valve FWS-PL-097 Close Main Feedwater Pump FWS-MP-02A Trip Main Feedwater Pump FWS-MP-02B Trip Startup Feedwater Pump FWS-MP-03A Trip Startup Feedwater Pump FWS-MP-03B Trip ll ) l l O l 2.2.4-14 l W Westinghouse oMAACSVev6Mt020204 wpMb-071798
Tier 1 M:terial STEAM GENERATOR SYSTEM ---=-- p Revision: 6 = E! Effective: July 1998 1 t Table 2.2.4 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 SGS and portions of the SGS and portions of the will be performed. the FWS, MSS, and MTS conform FWS, MSS, and MTS are as with the functional arrangement as described in de Design defined in the Design Description Description of this Section 2.2.4. of this Section 2.2.4.
2.a) The components identified Inspection will be conducted of The ASME Code Section III in Table 2.2.4-1 as ASME Code the as-built components as design reports exist for the as-built Section III are designeo 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 Inspectivn will be conducted of The ASME Code Section III Table 2.2.4-2 as ASME Code the as. built piping as documented design reports exist for the as-built Section III is designed and in the ASME design reports. piping identified in Table 2.2.4-2 constructed in accordance with as ASME Code Section III. ASME Code Section III O V 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 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 I I I 2.2.4-15 Westinghouse oNTAACSvevfNt020204.wpf:1 b.071798
Tier 1 Material STEAM GENERATOR SYSTEM i= - Revision: 6 - Effective: July 1998 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 hydrosta;ic test Section III retain their pressure required by the ASME Code of the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.2.4-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.2.4-2 as ASME Code performed on the piping required the results of the hydrostatic test Section III retains its pressure by the ASME Code Section III to of the piping identified in boundary integrity at its design be hydrostatically tested. Table 2.2.4-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) The seismic Category I equipment identified in verify that the seismic Category I equipment identified in Table 2.2.4-1 can withstand equipment identified in Table Table 2.2.4-1 is located on the seismic design basis loads 2.2.4-1 is located on the Nuclear Nuclear Island. without loss of safety function. Island. ii) Type tests, analyses, or a ii) A repon exists and concludes combination of type tests and that the seismic Category I analyses of seismic Category I equipment can withstand seismic equipment will be performed. design basis loads without loss of safety function. iii) Inspection will be performed lii) A report exists and concludes for the existence of a report that the as. installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage is bounded by the tested or analyzed seismically bounded by the tested . conditions. or analyzed conditions. 5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that in Table 2.2.4-2 for which the existence of a report each of the as. built lines functional capability is required concluding that the as-built piping identified in Table 2.2.4-2 for is designed to withstand meets the requirements for which functional capability is combined normal and seismic functional capability. required meets the requirements design basis loads without a loss for functional capability. of its functional capability. O W Westinghouse o:siTAAcssrev6Vt020204.wpf:1 07I798
l l Tier 1 Material 7, STEAM GENERATOR SYSTEM _ =g ( ; Revision: 6 - E v Effective: July 1998 _ .. Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria l Design Commitment l inspections, Tests. Analyses Acceptance Criteria l
- 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 LDB and concludes that the L.BB 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 I performed of the protection from effects of a pipe break. Tier 1 materials, or a pipe break
, the dynamic effects of a rupture Material, Section 3.3, Nuclear evaluation report exists and 4 of the line. Island Buildings, contains the concludes that protection from the design descriptions and dynamic effects of a line break is inspections, tests, analyses, and provided.
acceptance criteria for protection from the dynamic effects of pipe rupture. 7.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.2.4-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.2.4-1 as being qualified m environment can withstand the Class lE equipment located in a for a harsh environment can environmental conditions that harsh environment. withstand the environmental (V)' would exist before, during, and conditions that would exist before, following a design basis accident during, and following a design without loss of safety function basis accident without loss of for the time required to perform safety function for the time the safety function. required to perform the safety function. 7.b) The Class lE components Testing will be performed by A simulated test signal exists at identified in Table 2.2.4-1 are providing a simulated test signal ti.e Class IE equipment identified powered from their respective in each Class IE division. in Table 2.2.4-1 when the Class lE division. assigned Class 1E division is provided the test signal. 7.c) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material, Section 3.3, between SGS Class lE divisions, Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class lE cable. l (g) v l 2.2.4-17 [ W8Stiligh00S8 o AITAACSvev6Mt020204.wpf.1 b-072998
Tier 1 Mcterial l l STEAM GENERATOR SYSTEM EE Revision: 6 = Effective: July 1998 Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria j
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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 III of steam generator safety valves is generator safety valves exceeds the ASME Boiler and Pressure greater than or eq.:al to system 4,600,000 lb/hr per steam Vessel Code. relief requirements. generator. ii) Testing and analyses in ii) A report exists to indicate the accordance with ASME Code set pressure of the valves is less Section III will be performed to than 1195 psig. determine set pressure. 8.b) During design basis events, i) Testing will be performed to See item 11 in this table. the SGS limits steam generator confirm isolation of the main blowdown and feedwater flow to feedwater, startup feedwater, the steam generator. blowdown, and main steam lines. See item 11 in this table. ii) Inspection will be performed ii) A report exists to indicate the for the existence of a report installed flow limiting orifice confirming that the area of the within the SG main steam line flow limiting orifice within the SG discharge nozzle does not exceed main steam outlet nozzle will limit 1.4 sq. ft. releases to the containment. 8.c) The SGS preserves See Tier 1 Material, subsection See Tier 1 Material, subsection containment integrity by isolation 2.2.1, Containment System. 2.2.1, Containment System. of the SGS lines penetrating the 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 confirm 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. O 2.2.4-18 3 WeSilligh0LISO o AITAACSVevmit020204.wpf:1 t> 071798
l I Tiir 1 MitirlIl n STEAM GENERATOR SYSTEM a Q Revision: 6 _ E Effective: July 1998 )
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Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria ! l Design Commitment Inspections, Tests, Analyses Accepance Criteria l l 9.b) During shutdown i) Tests will be performed to i) See Tier 1 Material, operations, the SGS removes demonstrate the ability of the subsection 2.4.1, Main and I decay heat by delivery of startup startup feedwater system to Startup Feedwater System. feedwater to the steam generator provide feedwater to the steam { l 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 10 psi. atmosphere.
- 10. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.4-1 can be retrievability of the safety-rebted in Table 2.2.4-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
I1.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to l D to cause the remotely operated on the remotely operated valves cause the remotely operated j valves identified in Table 2.2.4-1 listed in Table 2.2.41 using valves to perform active safety to perform active functions. controls in the MCR. functions. II.b) 'Ile 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 demonstrate that remotely following times after receipt of an operated SGS i olation valves actuation signal: SGS V027A/B, V040A/B, V057A/B, V250A/B close within V027A/B < 44 see the required response times. V040A/B, V057A/B < 5 sec V250A/B < 5 sec l i O V 2.2.4-19 W _ W85tilighouse oNTAACSvev6Nt020204.wpf:1 b-072998
s Tier 1 Mat:ri;l 1 STEAM GENERATOR SYSTEM = -:=
= l Revision: 6 Effective: July 1998 ,
l Table 2.2.4-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 12.a) The mot -operated valves i) Tests or type tests of motor- i) A test report exists and identified in Taole 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 motor-operated valves are bounded the tests or type tests. by the tests or type tests. iii) Tests of the as-installed motor- iii) Each motor-operated valve operated valves will be performed changes position as indicated in under pre-operational flow, Table 2.2.4-1 under pre-differential pressure, and operational test conditions. 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 ofloss of motive power. in Table 2.2.4-1 assumes the assume the indicated loss of indicated loss of motive power motive power position. position. , l I l l l i O 2.2.4-20 W Westinghouse oNTAACS\rev6iit020204.wpf: 1 tF071798
Tier 1 Materi:1 STEAM GENERATOR SYSTEM (] Revision: 6 () Effective: July 1998 Table 2.2.4 5 Component Name Tag No. Component Location Main Steam Line Isolation Valve SGS-PL-V040A Auxiliary Building Main Steam Line Isolation Valve SGS-PL-V040B Auxiliary Building Main Feedwater Isolation Valve SGS-PL-V057A Auxiliary Building Main Feedwater Isolation Valve SGS-PL-V057B Auxiliary Building Main Feedwater Control Valve SGS-PL-V250A Auxiliary Building Main Feedwater Control Valve SGS-PL-V250B Auxiliary Building Turbine Stop Valves MTS-PL-V001 A Turbine Building MTS-PL-V001B MTS-PL-V003A MTS-PL-V003B Turbine Control Valves MTS-PL-V002A Turbine Building MTS-PL-V002B MTS-PL-V004A p MTS-PL-V004B t 1
'U Main Feedwater Pumps FWS-MP-Ol A Turbine Building FWS-MP-01B Feedwater Booster Pumps FWS-MP-02A Turbine Building FWS-MP-02B i
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Tier 1 Materi:1 J l MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM == ~ n Revision: 6
- 5 d Effective: July 1998 _
3 { 2.2.5 Main Control Room Emergency Habitability System Design Description The main centrol room emergency habitability system (VES) provides a supply of breathable air for the main control room (MCR) occupants and maintains the MCR at a positive pressure with respect to the surrounding areas whenever ac power is not available to operate the nuclear island nonradioactive ventilation system (VBS) or high radioactivity is detected in the MCR air supply. (See CDM Section 3.5 for Radiation Monitoring). The VES also limits the heatup of the MCR, the instrumentation and control (I&C) equipment rooms, and the Class IE de equipment rooms by using the heat capacity of surrounding structures. The VES is as shown in Figure 2.2.5-1 and the component locations of the VES are as shown in Table 2.2.5-6.
- 1. The functional arrangement of the VES is as described in the Design Description of this Section 2.2.5.
- 2. a) The components identified in Table 2.2.5-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
[] V b) he 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. I
- 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. I b) The piping identified in Table 2.2.5-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.2.5-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.5-2 for which functional capability is required is , designed to withstand combined normal and seismic design basis loads without a loss of its ( functional capability. [O 2.2.5-1 l 3 Westinghouse o%p60WTAACSvee020205.wpf;071798
Tier 1 Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM ==- == Revision: 6 E Effective: July 1998 _
- 6. a) The Class lE components identified in Table 2.2.5-1 are powered from their respective Class lE division.
b) Separation is provided between VES Class 1E divisions, and between Class IE divisions and non-Class IE cable.
- 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 IE de equipment rooms are within design basis assumptions to limit the heatup of the rooms identified in Table 2.2.5-4.
- 8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.
- 9. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.5-1 to perform their active functions.
b) The valves identified in Table 2.2.5-1 as hr.ving protection and safety monitoring system O (PMS) control perform their active safety function after receiving a signal from the PMS.
- 10. After loss of motive power, the remotely operated valves identified in Table 2.2.5-1 assume the indicated loss of motive power position.
- 11. Displays of the parameters identified in Table 2.2.5-3 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.2.5-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the VES. l l l l O' l [ WB5tiligh0USB onapsooslTAAcsvevsyto20205.wpf 0 9 I I
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Tier 1 Mat ^ rial MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM == m Revision: 6 E I Effective: July 1998 _ l l Table 2.2.5 2 ASME Code Functional Capability Line Name Line Number Section III Required MCR Relief Line VES-PL-022A Yes Yes i MCR Relief Line VES-PL-022B Yes Yes Table 2.2.5-3 Equipment Tag No. Display Air Storage Tank Pressure VES-001A Yes Air Storage Tank Pressure VES-001B Yes Table 2.2.5-4 Heat Load 0 to 24 Hours Heat Load 24 to 72 Room Name Room Numbers (Btu /s) Hours (Bru/s) MCR Envelope 12401 12.8 (hour 0 through 3) 3.9 5.1 (hour 4 through 24) I&C Rooms 12301,12305 8.8 0 I&C Rooms 12302,12304 13.0 4.2 de Equipment Rooms 12201,12205 3.7 (hour 0 through 1) 0 2.4 (hour 2 through 24) . l de Equipment Rooms 12203,12207 5.8 (hour 0 through 1) 2.0 l 4.5 (hour 2 through 24) l l Oll 2.2.5-8 I We $ 0US8 o:\ap600\lTAACS\rev6;it020205.wpf;071798
Tier 1 Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM ~r O Revision: 6 E V Effective: July 1998 1 .. 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 the VES is as described in the will be performed. the functional arrangement Design Description of this described in the Design i 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 Ill 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-I as ASME Code ASME Code Section III Section III. requirements. j l 2.b) The piping identified in Inspection will be conducted of The ASME Code Section III I 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. 3.a) Pressure boundary welds in Inspection of the as-built pressure A report exists and concludes that b 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 nca-Section III meet ASME Code 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 2.2.5-2 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 2.2.51 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-I as ASME Code pressure. tested. Section 111 conform with the requirements of the ASME Code Section 111. 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 Section III.
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Tier 1 Material MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM F-"Z
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Revision: 6 E Effective: July 1998 _ Table 2.2 5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 5.a) The seismic Category I i) Inspection will be performed 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 funct ion. 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 Categori ; I analyses of seismic Category I equipment can withstand seismic equipment will be perfonned. design oasis 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.
5.b) Each of the lines identified Inspection will be performed for A report exists and concludes that in Table 2.2.5-2 for which the existence of a report each of the as-built lines identified functional capability is required is verifying that the aa-built piping in Table 2.2.5-2 for which designed to withstand combined meets the requirements for functional capability is required normal and seismic design basis functional capability. meets the requirements for loads without a loss of its functional capability. functional capability. 6.a) The Class IE components Testing will be performed by A simulated test signal exists at 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 Tier 1 Material Section 3.3, See Tier 1 Material, Section 3.3, between VES Class IE divisions, Nuclear Island Buildings. Nuclear Island Buildings. and netween Class IE divisions and non-Class IE cable. I O 2.2.5-10 W85flflgil0LISO onapsoosrrAACSvev6bt0202o5.wpf.071798
Tier 1 Mit; rill O MAIN CONTROL ROOM EMERGEN0Y HABITABILITY SYSTEM Revision: 6
\ds Effective: July 1998 Table 2.2.5-5 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.a) The VES provides a 72-hour i) Testing will be performed to i) The air flow rate from the VES supply of breathable quality air confirm that the required amount is at least 60 scfm and not more for the occupants of the MCR. of air flow is delivered to the than 70 scfm. MCR. ii) The calculated storage capacity ii) Analysis of storage capacity is greater than or equal to will be performed based on as- 314,132 scf. built manufacturers data. iii) MCR air samples will be iii) The MCR air is of breathable taken during VES testing and quality, analyzed for quality. 7.b) The VES maintains the i) Testing will be performed The MCR pressure boundary is MCR pressure boundary at a with VES flowrate between 60 pressurized to greate. than or equal positive pressure with respect to and 70 sefm to confirm that the to 1/8-in, water gauge with respect the surrounding areas. MCR is capable of maintaming to the surrounding area. T the required pressurization of the presst re boundary. ii) Air leakage ir.:o the MCR ii) Analysis of air leakage will be measured during VES measurements indicate that VES testing using a tracer gas. operation limits MCR air infiltration consistent with operator dose analysis. l I l l 2.2.5-11 W eum Westinghouse o:\ap600\lTAACS\rev6\it020205.wpf:072998
Tier 1 Mat;ri;l MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM EF ~~
~
- Revision: 6 Effective: July 1998 _
Table 2.2.5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7.c) The heat loads withir. 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 1E de equipment from as-built equipment within identificci in Table 2.2.5-4 are less rooms are within design basis the rooms identified in than or equal to the specified assumptions to hmit the heatup of Table 2.2.5-4 are less than or values or that an analysis report the rooms identified in equal to the design basis exists that concludes: Table 2.2.5-4. assumptions
- The temperature and humidity in the MCR remain within limits for reliable human performance for the 72 hour s criod.
- 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 120 F.
- 8. Safety-related displays Inspection will be performed for Safety-related displays ihntified in identified in Table 2.2.5-1 can be retrievability of the safety-related Table 2.2.5-1 can be retrieved in retrieved in the MCR. displays in the MCR. the MCR.
9.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause remotely operated valves on remotely operated valves cause remotely operated valves identified in Table 2.2.5-1 to identified in Table 2.2.5-1 using identified in Table 2.2.5-1 to perform their active functions. the controls in the MCR. perform their active safety functions. 9.b) The valves identified in Testing will be performed on The remotely operated valves Table 2.2.51 as having PMS remotely operated valves listed identified in Table 2.2.5-1 as control perform their active safety in Table 2.2.5-1 using real or having PMS control perform the function after receiving a signal simulated signals into the PMS. active safety function identified in from the PMS. the tabic after receiving a signal from the PMS.
- 10. After loss of motive power, Testing of the installed valves After Icas of motive power, each the remotely operated valves will be performed under the remotely operated valve identified identified in Table 2.2.5-1 assume conditions of loss of motive in Table 2.2.5-1 assumes the the indicated loss of motive power. indicated loss of motive power power position. position.
I 2.2.5-12 3 Westinghouse osapsoc/JTAACSirev6'Jt020205 wpf 072998
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Tier 1 Mat: rial MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM Ei= == T'N Revision: 6 *~ E b) Effective: July 1998 _ Table 2.2.5-5 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 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.
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Tier 1 M:t: rial MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM . Revision: 6 E Effective: July 1998 _ Table 2.2.5 6 Component Name Tag Number Component Location Emergency Air Storage Tank 01 VES-MT-01 Auxiliary Building Emergency Air Storage Tank 02 VES-MT-02 Auxiliary Building Emergency Air Storage Tank 03 VES-MT-03 Auxiliary Building Emergency Air Storage Tank 04 VES-MT-04 Auxiliary Building Emergency Air Storage Tar.k 05 VES-MT-05 Auxiliary Building Emergency Air Storage Tank 06 VES-MT-06 Auxiliary Building Emergency Air Storage Tank 07 VES-MT-07 Auxiliary Building Emergency Air Storage Tank 08 VES-MT-08 Auxiliary Building Emergency Air Storage Tank 09 VES-MT-09 Auxiliary Building Emergency Air Storage Tank 10 VES-MT 10 Auxiliary Building Emergency Air Storage Tank 11 VES-MT-11 Auxiliary Building Emergency Air Storage Tank 12 VES-MT-12 Auxiliary Building Emergency Air Storage Tank 13 VES-MT-13 Auxiliary Building Emergency Air Storap Tank 14 VES-MT-14 Auxiliary Building Emergency Air Storage Tank 15 VES-MT- 15 Auxiliary Building Emergency Air Storage Tank 16 VES-MT-16 Auxiliary Building Emergency Air Storage Tank 17 VES MT-17 Auxiliary Building Emergency Air Storage Tank 18 VES-MT-18 Auxiliary Building Emergency Air Storage Tank 19 VES-MT-19 Auxiliary Building Emergency Air Storage Tank 20 VES-MT-20 Auxiliary Building Emergency Air Storage Tank 21 VES-MT-21 Auxiliary Building Emergency Air Storage Tank 22 VES-MT-22 Auxiliary Building Emergency Air Storage Tank 23 VES-MT-23 Auxiliary Building Emergency Air Storage Tank 24 VES-MT-24 Auxiliary Building Emergency Air Storage Tank 25 VES-MT-25 Auxiliary Building Emergency Air Storage Tank 26 VES-MT-26 Auxiliary Building Emergency Air Storage Tank 27 VES-MT 27 Auxiliary Building Emergency Air Storage Tank 28 VES-MT-28 Auxiliary Building 2.2.5-14 W Westinghouse oMp600WAACSveet020205.wpf:071798
Tier 1 M:teri:1 MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM "e-Revision: 6 -
=
C)N, Effective: July 1998 Table 2.2 5-6 (cont.) Component Name Tag Number Component Location Emergency Air Storage Tank 29 VES-MT-29 Auxiliary Building Emergency Air Storage Tank 30 VES-MT-30 Auxiliary Building Emergency Air Storage Tank 31 VES-MT-31 Auxiliary Building Emergency Air Storage Tank 32 VES-MT-32 Auxiliary Building b) L
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Tier 1 Mat: rill MAIN CONTROL ROOM EMERGENCY HABITABILITY SYSTEM = Revision: 6 - Effective: July 1998 _ l vts-ev ma i "* " CD% e33" vts-A-votta twegge ain I s' anna taws vgs .0;teu j X]p VE 8'"'* 800 8
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Tier 1 Material COMPONENT COOLING WATER SYSTEM == ==:
/'^'N Revision: 6
- E!
(,/ Effective: July 1998 2.3.1 Component Cooling Water System Design Description i The component cooling water system (CCS) removes heat from various plant components and transfers this heat to the service water system (SWS) during normal modes of plant operation including power generation, shutdown and refueling. The CCS has two pumps and two heat exchangers. The CCS is as shown in Figure 2.3.1-1 and the CCS component locations are as shown in Table 2.3.1-3.
- 1. The functional arrangement of the CCS is as described in the Design Description of this Section 2.3.1.
- 2. The CCS preserves containment integrity by isolation of the CCS lines penetrating the containment.
- 3. The CCS provides the nonsafety-related functions of transferring heat from the normal residual heat removal system (RNS) during shutdown and the spent fuel pool cooling system during all modes of operation to the SWS.
t
'-) 4. Controls exist in the main control room (MCR) to cause the pumps identified in Table 2.3.1-i 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. I O l w 2.3.1 1 W Westinghouse o:VT AACSVev6Mt020301.wpf:1 b-071798
l 1 Tier 1 Mat:ri:1 I
==
COMPONENT COOLING WATER SYSTEM
- Revision: 6 M Effective: July 1998 Table 2.3.11 Equipment Name Tag No. Display Control Function CCS Pump A CCS-MP-01 A Yes Start (Run Status)
CCS Pump B CCS-MP-OlB Yes Start (Run Status) CCS Discharge Header Flow Sensor CCS-101 Yes - CCS to Nortnal 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) l A Valve (Position Indicator) CCS Flow to RCP IB Valve (Position CCS-PL-V256B Yes - Indicator) CCS Flow to RCP 2A Valve (Position CCS-PL-V256C Yes - Indicator) CCS Flow to RCP 2B Valve (Position CCS-PL-V256D Yes - Indicator) Note: Dash (-) indicates not applicable. O 2.3.12 3 WBStingh0USB o:m AAcsvevssito20301.wpf.1b-071798
I Tier 1 Mit:ri;l i rm () COMPONENT COOLING WATER SYSTEM = = Revision: 6 - Effective: July 1998 Table 2.3.1-2 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 CCS conforms with the CCS is as described in the will be performed. the functional arrangement Design Description of tin described in the Design Section 2.3.1. Description of this Section 2.3.1.
I 2. The CCS preserves containment See Tier 1 Material, See Tier 1 Material, integrity by isolation of the CCS subsection 2.2.1, Containment subsection 2.2.1, Containment lines penetrating the containment. System. System.
- 3. The CCS provides the i) Inspection will be performed for i) A report exists and concludes nonsafety-related functions of the existence of a report that that the UA of each CCS heat transferring heat from the RNS determines the heat transfer exchanger is greater than or equal during shutdown and the spent fuel capability of the CCS heat to 9.4 million Btu /hr *F.
pool cooling system during all exchangers. modes of operation to the SWS. ii) Testing will be performed to ii) Eac pump of the CCS can con 5rm that the CCS can provide provide at least 2520 gpm of cooling water to the RNS HXs cooling water to one RNS HX ('s while providing cooling water to and at least 720 gpm of cooling
!,j the SFS HXs. water to one SFS HX while providing at least i160 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 identi5ed in cause pumps listed in Table 2.3.1-1 to perform :he listed Table 2.3.1-1 using controls in the Table 2.3.1-1 to perform the listed functions. MCR. functions.
- 5. Displays of the parameters Inspection will be performed for Displays identified in Table 2.3.1-1 identified in Table 2.3.1-1 can be retrievability of the parameters in can be retrieved in the MCR.
retrieved in the MCR. the MCR. I l CT U l 2.3.1-3 W WOStiflgh0USB oNTAACSVev6Vt020301.wpf it>-072998 L_______-..___.-
Tier 1 Materict COMPONENT COOLING WATER SYSTEM E: == Revision: 6 = Effective: July 1998 _ Table 2.3.1-3 Component Name Tag No. Component Location CCS Pump A CCS-MP-01 A Turbine Building CCS Pump B CCS-MP-Ol B Turbine Building CCS Heat Exchanger A CCS-ME-01 A Turbine Building CCS Heat Exchanger B CCS-ME-Ol B Turbine Building O O [ WBSilligh00S8 o:\lTAACS\rev6\it020301.wpf:1 b-0 79
l i Tier 1 Mat: rial COMPONENT COOLING WATER SYSTEM --~ Revision: 6 i Effective: July 1998 sws c_________,
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CVS LETCOWN MX g g g 3 il lh ._ d$ "f _ _"*_ _ j __ CCS MEAT EXCHANCER A CCS-uC-C1 A p p CCS-MP-01 A SwS e4
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CCS HEAT EXC NCER 8 CCS-ME-010 CCS PUMP B CCS-MP-018
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I ' f CVS MINIFLOWS MxS ' l RNS PUM*S SEALS i i P5S SAMPLE COOLER I i vws CH!LLERS ' t CAS l CDS PuMD A!R COMPRESSORS MOTCR l' RNS
- 88
- SFS ctg g"3 SFS
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I HX A M ll l, HX B HX A M l h MX B C,3 C D C C3 o u o jfROM CONTAINMENT \ l MEAT LOADS / I 1 l Figure 2.3.1-1 ;
, Component Cooling Water System l 2.3.1-5 W8Stingh00S8 o:\lTAACSVev6\it020301.wpf;1 b-071798 l
E_________
Tier 1 Mit:ri I CHEMICAL AND VOLUME CONTROL SYSTEM "" O Revision: 6 Effective: July 1998 M l 2.3.2 Chemical and Volume Control System Design Description The chemical and volume control system (CVS) provides reactor coolant system (RCS) purification, RCS inventory control and makeup, chemical shim and chemical control, and oxygen control, and provides for auxiliary pressurizer spray. The CVS performs these functions during nonnal modes of operation including power generation and shutdown. The CVS is as shown in Figure 2.3.2-1 and the component locations of the CVS are as shown in Table 2.3.2-5.
- 1. The functional arrangement of the CVS is as described in the Design Description of this 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 requi: ments, b) The piping identified in Table 2.3.2-2 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 2.3.2-1 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 ASME Code Section III requirements.
- 4. a) He components identified in Table 2.3.2-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) He piping identified in Table 2.3.2-2 as ASME Code Section III retains its pre sure boundary integrity at its design pressure.
- 5. The seismic Category I equipment identified in Table 2.3.2-1 can withstand seismic design basis loads without loss of safety function.
- 6. a) The Class IE equipment identified in Table 2.3.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a 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 2.3.2-1 are powered from their respective Class lE division. O [ W85tingh0USB 2.3.2-1 o:\lTAACS\revGt020302.wpf:1 t>-071798
l l Tier 1 MCterial I CHEMICAL AND VOLUME CONTROL SYSTEM " l Revision: 6 -
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E1fective: July 1998 _ c) Separation is provided between CVS Class IE divisions, and between Class lE divisions and non-Class IE cable. 4 I
- 7. The CVS provides the following safety-related functions: 1 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.
- 8. The CVS provides the fcilowing nonsafety-related functions:
a) The CVS provides makeup water to the RCS. b) The CVS provides the pressurizer auxiliary spray.
- 9. Safety-related displays in Table 2.3.2-1 can be retrieved in the main control room (MCR).
- 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.3.2-1 to perform active functions.
b) The valves identified in Table 2.3.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS.
- 11. a) The motor-operated and check valves identified in Table 2.3.2-1 perform an active safety-related 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.
- 12. a) Controls exist in the MCR to cause the pumps identified in Table 2.3.2-3 to perform the listed function.
b) The pumps identified in Table 2.3.2-3 start after receiving a signal from the PLS.
- 13. Displays of the parameters identified in Table 2.3.2-3=dn be retrieved in the MCR.
- 14. The nonsafety-related piping located inside containment and designated as reactor coolant pressure boundary, as identified in Table 2.3.2-2 (pipe lines with "No" in the ASME Code column), has been designed to withstand a seismic design basis event and maintain structural integrity.
O 2.3.2-2 [ W85tingh0USB onlT AACSVev6Vt020302.wpf: 1 b-071798 l
Ti:r 1 Mitiritt I CHEMICAL AND VOLUME CONTROL SYSTEM - - O Revision: 6 Effective: July 1998 Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.2-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the CVS. l . O O W85tingh00S8 oNTAACS\rev6\it020302.wpf:1b-0 79
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Table 2.3.2-2 Lim: Name Line Number ASME Code Section III CVS Purification Line BTA L001 Yes CVS Purification Line Return BTA LO38 Yes CVS Makeup Containment Penetration Line BBB LO53 Yes CVS Supply Line to Regenerative Heat BBD LOO 2 No Exchanger CVS Return Line from Regenerative Heat BBD L018 No Exchanger BBD LO73 No CVS Line from Regenerative Heat Exchanger to BBD LOO 3 No Letdown Heat Exchanger BBD LO72 No CVS Lines from Letdown Heat Exchanger to BBD LOO 4 No Demin. Tanks BBD LOO 5 No CVS Lines from Demin Tanks to RC Filters BBD LO20 No BBD LO21 No O BBD LO22 BBD LO29 BBD LO37 No No No CVS Lines from RC Fihers to Regenerative BBD LO30 No Heat Exchanger BBD LO31 No BBD LO34 No CVS Resin Fill Lines to Demin. Tanks BBD LOO 8 No BBD L013 No BBD LO25 No O 3 Westinghouse 2.3.2 7 oNTAACSvev6bt020302.wpf:15071798
Tier 1 Mat:ri;1 CHEMICAL AND VOLUME CONTROL SYSTEM s-Revision: 6 a: Effective: July 1998 _ I l Table 2.3.2-3 Control Equipment Tag No. Display Function CVS Makeup Pump A CVS-MP-01 A Yes Start (Run Status) CVS Makeup Pump B CVS-MP-OlB Yes Start (Run Status) Letdown Flow Sensor CVS-001 Yes - Letdown Flow Sensor CVS-025 Yes - CVS Purification Return Line (Position CVS-PL-V081 Yes - Indicator) Auxiliary Spray Line Isolation Valve CVS PL-V084 Yes - (Position Indicator) Boric Acid Tank Level Sensor CVS-109 Yes - Boric Acid Flow Sensor CVS-l !5 Yes - Makeup Blend Valve (Position Indicator) CVS-PL-V115 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 Yes - Makeup Flow Control Valve (Position CVS-PL-V157 Yes - Indicator) t Note: Dash (-) indicates not apphcable. 1 0 2.3.2-8 [ W8Stiflghotise oNTAAC Svev6Vt020302.wpf:1 b-071798
Tisr 1 M:ttrid CHEMICAL AND VOLUME CONTROL SYSTEM HE: Revision: 6 F Effective: July 1998 Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria I. The functional arrangement of Inspection of the as-built system The as-built CVS conforms with the CVS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design 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 2.3.2-1 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 2.3.2-2 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. 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 as ASME Code Section III meet performed in accordance with requirements are met for non-ASME Code Section III the ASME Code Section III. destructive examination of pressure requirements. boundary welds. 4.a) The cornponents identified A hydrostatic test will be A report exists and concludes that in Table 2.3.2-1 as ASME Code performed on the components the results of the hydrostatic test of Section III retain their pressure required by the ASME Code the components identified in boundary integrity at their design Section III to be hydrostatically Table 2.3.2-1 as ASME Code pressure. tested. Section III conform with the requirements of the ASME Code Section III. [ W8Silligh00S8 2.3.2-9 o:\lT AACS\rev6ut020302.wpf:1 t>071799
l Tier 1 M t: rial CHEMICAL AND VOLUME CONTROL SYSTEM - j Revision: 6 E Effective: July 1998 Table 2.3.2 4 (cont.) l l Inspections, Tests, Analyses, and Acceptance Criteria ' Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.b) The piping identified in A hydrostatic test will be A report exists and concludes that Table 2.3.2-2 as ASME Code performed on the piping required the results of the hydrostatic test of Section III retains its pressure by the ASME Code Section III the piping identified in boundary integrity at its design to be hydrostatically tested. Table 2.3.2-2 as ASME Code pressure. Section III conform with the requirements of the ASME Code Section III.
- 5. The seismic Category I i) Inspection will be performed i) The seismic Category I equipment identified in to verify that the seismic equipment identified in Table 2.3.2-1 can withstand Category I equipment identified Table 2.3.2-1 is located on the seismic design basis loads in Table 2.3.2-1 is located on the Nuclear 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. 6.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Table 2.3.2-1 as combination of type tests and the Class IE equipment identified being qualified for a harsh analyses will be performed on in Table 2.3.2-1 as being qualified environment can withstand the Class IE equipment located in a for a harsh environment can environmental conditions that harsh environment. withstand the environmental would exist before, during, and conditions that would exist before, following a design basis accident during, and following a design without loss of safety function for basis accident without loss of the time required to perform the safety function for the time safety function. required to perform the safety function. 6.b) 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 lE in Table 2.3.2-1 when the assigned Class IE division. division. Class IE division is provided the test signal. Oi 2.3.2-10 3 Westirighouse oNTAACSirev6\it020302.wpf:1t> 071798
- - - - - - - - - - - - - d
Tier 1 M;tirial CHEMICAL AND VOLUME CONTROL SYSTEM Z-C Revision: 6 3 Effective: July 1998 i 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 Tier 1 Material, Section 3.3, See Tier i Material, Section 3.3, between CVS Class 1E divisions, Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class lE cable. I 7.a) The CVS preserves See Tier 1 Material, See Tier 1 Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the CVS lines penetrating the System. System. containment. 7.b) The CVS provides See item 10b in this table. See item 10b in this table. termination of an inadvertent RCS boron dilution by isolating demineralized water from the RCS. 7.c) The CVS provides isolation See item 10b in this table. See item 10b in this table. of makeup to the RCS. 8.a) The CVS provides makeup i) Testing will be performed by i) Each CVS makeup pump water to the RCS. aligning a flow path from each provides a flow rate of greater thrn CVS makeup pump, actuating or equal to 100 gpm. makeup flow to the RCS at pressure greater than or equal to 2000 psia, and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid tank. ii) Inspection of the boric acid ii) The volume in the boric acid tank volume will be performed. tank is at least 55,000 gallons between the tank outlet connection and the tank overflow. j iii) Testing will be performed to iii) The total CVS makeup flow to j measure the delivery rate from the RCS is less than or equal to ! the DWS to the RCS. Both 200 gpm. l CVS makeup pumps will be operating and the RCS pressure will be below 6 psig. 2.3.2-11 W85tiligt100SB o:\lTAACSVev6\it020302.wpf:1b-072998
Tier 1 Material CHEMICAL AND VOLUME CONTROL SYSTEM =
;EE Revision: 6 ~
5 Effective: July 1998 . Table 2.3.2 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 8.b) The CVS provides the Testing will be performed by Each CVS makeup pump provides pressurizer auxiliary spray. aligning a flow path from each spray flow to the pressurizer. CVS makeup pump to the pressurizer auxiliary spray and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid tank and with RCS pressure greater than or equal to 2000 psia.
- 9. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.3.2-1 can be retrievability of the safety-related Table 2.3.2-1 can be retrieved in retrieved in the MCR. displays in the MCR. the MCR.
10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause the remotely operated on the remotely operated valves cause the remotely operated valves valves identified in Table 2.3.2-1 identified in Table 2.3.2-1 using identified in Table 2.3.21 to to perform active functions. the controls in the MCR. perform active functions. 10.b) He 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. ii) Testing will be performed to ii) These valves close within the demonstrate that the remotely following times after receipt of an operated CVS isolation valves actuation signal: CVS-V090, V091, V136A/B close within the required V090,V091 < 10 sec response time. V136A/B < 20 sec 11.a) he motor-operated i) Tests or type tests of i) A test report exists and and check valves identified in motor-operated valses will be concludes that each motor-Table 2.3.2-1 perform an active performed that demonstrate the operated valve changes position safety-related function to change capability of the valve to operate as indicated in Table 2.3.2-1 position as indicated in the table, under its design conditions. under design conditions. ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the as-installed motor-operated verifying that the as-installed valves are bounded by the tests or l motor-operated valves are type tests. i bounded by the tested conditions. I 2.3.2-12 Westinghouse osiTAAcSirev6'dt020302.wpf.1 t>071798 1
l Tier 1 Material l CHEMICAL AND VOLUME CONTROL SYSTEM -- - O Revision: 6 5~ i ( _fl Effective: July 1998 , l Table 2.3.2-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria iii) Tests of the as-installed iii) Each motor-operated valve motor-operated valves will be changes position as indicated in performed under pre-operational Table 2.3.2-1 under pre-operational flow, differential pressure, and test conditions. temperature conditions, iv) Exercise testing of the check iv) Each check valve changes valves with active safety position as indicated in 3 functions identified in Table 2.3.2-1. Table 2.3.2-1 will be performed under pre-operational test pressure, temperature and fluid flow conditions. I1.b) After loss of motive power, Testing of the installed valves Upon loss of motive power, each the remotely operated valves will be performed under the remotely operated valve identified identified in Table 2.3.2-1 assume conditions ofloss of motive in Table 2.3 2-1 assumes the the indicated loss of motive power. indicated loss of motive power power position. position. (w.)' 12.a) Controls exist in the MCR Testing will be performed to Controls in the MCR cause pumps to cause the pumps identified in actuate the pumps identified in identified in Table 2.3.2-3 to Table 2.3.2-3 to perform the Table 2.3.2-3 using controls in perform the listed function. listed function. the MCR. l 12.b) The pumps identified in Te:iting will be performed to The pumps identified in Table 2.3.2-3 start after receiving confirm starting of the pumps Table 2.3.2-2 start after a signal is a signal from the PLS. identified in Table 2.3.2-3. generated by the PLS.
- 13. Displays of the parameters Inspection will be performed for Displays identified in Table 2.3.2-3 identified in Table 2.3.2-3 can be retrievability of the displays can be retrieved in the MCR.
retrieved in the MCR. identified in Table 2.3.2-3 in the MCR.
- 14. The nonsafety-related piping inspection will be conducted of The CVS Seismic Analysis located inside containment and the as-built components n Repons exist for the non-safety designated as reactor coolant documented in the CVS Seismic related piping located inside pressure boundary, as identified Analysis Report. containment and designated as in Table 2.3.2-2, has been reactor coolant pressure boundary designed to withstand a seismic as identified in Table 2.3.2-2.
design basis event and maintain l structural integrity. l lO i 2.3.2-13 Westilighatise oNTAACSvev6\it020302.wpf.1 b-071798
Tier 1 M;terial CHEMICAL AND VOLUME CONTROL SYSTEM == == Revision: 6 Effective: July 1998 _ Table 2.3.2-5 Component Name Tag No. Component Location CVS Makeup Pump A CVS MP-01 A Auxiliary Building CVS Makeup Pump B CVS-MP-Ol B Auxiliary Building Boric Acid Ta9 CVS-MT-02 Yard Regenerative Heat Exchanger CVS-ME-01 Containment Letdown Heat Exchanger CVS-ME 02 Containment Mixed Bed Demineralized A CVS-MV-Ol A Containment Mixed Bed Demineralized B CVS-MV OlB Containment Cation Bed Demineralized CVS-MV-02 Containment Reactor Coolant Filter A CVS-MV-03A Containment Reactor Coolant Filter B CVS-MV 03B Containment O O 2.3.2-14 W Westirlghouse oNTAACSvev6\it020302.wpf:1 b-071798
Tier 1 Material CHEMICAL AND VOLUME CONTROL SYSTEM =*=== (^T Revision: 6 E E (./ Effective: July 1998 1 .e E.
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r Tier 1 Materi:1 l STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM - ;-.- i Revision: 6 l (V Effective: July 1998 _ l 2.3.3 Standby Diesel and Auxiliary Boiler Fuel Oil System ' Design Description The standby diesel and auxiliary boiler fuel oil system (DOS) supplies diesel fuel oil for the onsite standby power system. 'ibe diesel fuel oil is supplied by two above-ground fuel oil storage tanks. The DOS also provides fuel eil for the ancillary diesel generators. A single fuel oil storage tvik services both ancillary diesel gecerators. i r The DOS is as shown in Figure 2.3.3-1 and the component locations of the DOS are as shown in Table 2.3.3-3.
- 1. The functional arrangement of the DOS is as described in the Design Description of this '
Section 2.3.3.
- 2. The ancillary diesel generator fuel tank can withstand a seismic event.
- 3. The DOS provides the following nonsafety-related functions:
a) Each fuel oil storage tank provides for at least 7 days of continuous operation of the associated
- standby diesel generator.
('3) b) Each fuel oil day tank provides for at least four hours of continuous operation of the ' associated standby diesel engine generator. c) The fuel oil flow rate to the day tank of each standby diesel generator provides for continuous operation of the associated diesel generator. d) The ancillary diesel generator fuel tank is sized to supW power to long-term safety-related post-accident monitoring loads and control room lighting through a regulating transformer and one PCS recirculation pump for a period of 4 days.
- 4. Controls exist in the main control room (MCR) to cause the components identified in Table 2.3.3-1 to perform the listed function.
- 5. Displays of the parameters identified in Table 2.3.3-1 can be retrieved in the MCR.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.3-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the DOS. i ( ) v 2.3.3-1 W85tifighouse o:MTAACSvev6\it020303.wpf:1t> o71798 c_________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
Tier 1 Material STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM == "ig Revision: 6 = Effective: July 1998 Table 2.3.31 Control Equipment Name Tag No. Display Function Diesel Fuel Oil Pump 1 A (Motor) DOS-MP-01 A Yes Start I (Run Status) . Diesel Fuel Oil Pump IB (Motor) DOS-MP-Ol B 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 - N>te: Dash (.) indicates not appbcable. O l O 3 W85tingh00S8 oNTAACSVev69t020303 wptib-0 9
Tier 1 Mat:ri;l STANDBY DIESEL AND AUXlLIARY BOILER FUEL OlL SYSTEM - mg O Revision: 6 Effective: July 1998 1 l
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Table 2.3.3-2 ; Inspections Tests, Analyses, and Acceptance Criteria ' Design Comr. ent Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built DOS conforms with the the DOS is as described in the will be performed. functional arrangement described in Design Description of this the Design Description of this Section 2.3.3. Section 2.3.3.
- 2. The ancillary diesel generator Inspection will be performed for A report exists and concludes that fuel tank can withstand a seismic the existence of a report verifying the as-installed ancillary diesel event. that the as-installed ancillary generator fuel tank and its diesel generator fuel tank and its anchorage are designed using anchorage are designed using seismic Category 11 methods and scismic Category 11 methods and criteria.
criteria. 3.a) Each fuel oil storage tank Inspection of each fuel oil storage The volume of each fuel oil storage T ovides 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.
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3.b) Each fuel oil storage day tank Inspection of the fuel oil day tank The volume of each fuel oil day provides for at least 4 hours of will be performed. tank is greater than or equal to 1300 operation of the associated standby gallons. diesel generator. 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. generator provides for continuous operation of the associated diesel generator. 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 to long-term safety-related post performed. equal to 450 gallons. accident monitoring loads and control room lighting through a regulating transformer and one PCS recirculation pump for four days.
- 4. Controls exist in the MCR to Testing will be performed on the Controls in the MCR operr to cause the components identified in components in Table 2.3.3-1 using cause the components listed in Table Table 2.3.31 to perform the listed controls in the MCR. 2.3.3-1 to perform the listed function. functions.
- 5. Displays of the parammis Inspection will be performed for The displays identified in identified in Table 2.3.31 can be retrievability of parameters in the Table 2.3.3-1 can be retrieved in the 3 retrieved in the MCR. MCR. MCR.
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Tier 1 M:teri:1 STANDBY DIESEL AND AUXILIARY BOILER FUEL OIL SYSTEM == == Revision: 6 _.- Effective: July 1998 _ Table 233-3 Component Name Tag No. Component Location Diesel Oil Transfer Package A DOS-MS-01 A Yard Diesel Oil Transfer PacL_, a DOS-MS-Ol B Yard Fuel Oil Storage Tank A DOS-MT-01 A Yard Fuel Oil Storage Tank 5 DOS-MT-OlB Yard Diesel Generator A Fuel Oil Day Tank DOS-MT-02A Diesel Building Diesel Generator B Fuel Oil Day Tank DOS-MT-02B Diesel Building Ancillary Diesel Fuel Oil Storage Tank DOS-MT-03 Annex Building 9 O [ WB5tilighouse o:vTAAcsvevesto203o3 wpt:1o-o
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Tier 1 Material , FIRE PROTECTION SYSTEM = 1. f\ d Revision: 6 Effective: July 1998 i 2.3.4 Fire Protection System Design Description The fire protection system (FPS) detects and suppresses fires in the plant. The FPS consists of water distribution systems, automatic and manual suppression systems, a fire detection and alarm' system, and portable fire extinguishers. The FPS provides fire protection for the nuclear island, the annex building, the turbine building, the radwaste building and the diesel generator building. The FPS is as shown in Figure 2.3.4-1 and the component locations of the FPS are as shown in Table 2.3.4-3.
- 1. The functional arrangement of the FPS is as described in the Design Description of this Section 2.3.4.
- 2. The FPS piping identified in Fipre 2., .-l remains functional following a safe shutdown earthquake.
- 3. The FPS provides the safety-related function of preserving containment integrity by isolation of the FPS line penetrating the containment.
1 4. The FPS provides for manual fire fighting capability in plant ater, containing safety-related V I equipment.
- 5. Displays of the parameters identified in Table 2.3.4-1 can be retrieved in the main control room (MCR).
- 6. The FPS provides nonsafety-related containment spray for severe accident management.
- 7. The FPS provides two fire water storage tanks, each capable of holding at least 300,000 gallons of water.
- 8. Two FPS fire pumps provide at least 2000 gpm each at a total head of at least 300 ft.
- 9. The fuel tank for the diesel-driven fire pump is capable of holding at least 240 gallons.
I 10. hdividual fire detectors provide fire detection capability and can be used to initiate fire alarms in i Meas containing safety-related equipment.
.. The FPS seismic standpipe subsystem can be supplied from the FPS fire main by opening the l normally closed cross-connect valve to the FPS plant fire main.
I Inspections, Tests, Analyses, and Acceptance Criteria (i Table 2.3.4-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the FPS. d 2.3.4-1 [ W85tlDgh00S8 oWAACSvev6\it0203o4.wpf:1 b-071498
Tier 1 Material l FIRE PROTECTION SYSTEM = = Revision: 6 ~ 5 Effective: July 1998 _ Table 2.3.41 Equipment Name Tag No. Display Control Function Motor-driven Fire Pump FPS-MP-01 A Yes (Run Status) Start Diesel-driwa Fire Pump FPS-MP-OlB Yes (Run Status) Start Jockey Pump FPS-MP-02 Yes (Run Status) Start O l l l l O WB5tingh0tlSB o:\lTAACSVev6Nt020304.wpf:1b-0 1 98
Tier 1 Materill l FIRE PROTECTION SYSTEM 3= == O Revision: 6 i = b Effective: July 1998 _ Table 2.3.4-2 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 FPS conforms with the FPS is as described in the will be performed. the functional LTangement Design Description of this described in the Design Section 2.3.4. Description of this Section 2.3.4.
- 2. The FPS piping depicted in i) Inspection will be performed i) The piping depicted in Figure 2.3.4-1 remains functional to verify that the piping depicted Figure 2.3.4-1 is located on following a safe shutdown in Figure 2.3.4-1 is located on the Nuclear Island.
earthquake. the Nuclear Island. ii) A reconciliation analysis ii) ne as-built piping stress report using the as-designed and as- exists and concludes that the built piping information will be piping remains functional performed, or an analysis of the following a safe shutdown as-built piping will be earthquake. performed, A i ) i 3. The FPS provides the safety- See Tier 1 Material, subsection See Tier 1 Material, subsection related function of preserving 2.2.1, Containment System. 2.2.1, Containment System. containment integrity by isolation of the FPS line penetrating the containment.
- 4. He FPS provides for manual i) Inspection of the passive i) The volume of the PCS tank fire fighting capability in plant containment cooling system above the standpipe feeding the I areas containing safety-related (PCS) storage tank will be FPS and below the overflow is at i equipment. performed. least 18,000 gal.
ii) Testing will be performed by measuring the water flow rate as ii) Water is simultaneously it is simultaneously discharged discharged from each of the two from the two highest fire-hose highest fire-hose stations at not stations and when the water for less than 75 gpm. the fire is supplied from the PCS storage tank. ' 0 lV 2.3.4-3 T Westinghouse oWAACSVevWM0304.wpf:1b-071498
Tier 1 M;t; rial FIRE PROTECTION SYSTEM fr Revision: 6 - Effective: July 1998 _ . l Table 2.3.4-2 (cont.) Inspections Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l l
- 5. Displays of the parameters inspection will be performed for The displays identified in Table l identified in Table 2.3.41 can be retrievability of the parameters in 2.3.4-1 can be retrieved in the retrieved in the MCR. the MCR. MCR.
- 6. The FPS provides nonsafety- Inspection of the containment The FPS has spray headers and related containment spray for spray headers will be performed. nozzles as follows:
severe accident management. At least 44 nozzles at plant elevation of at least 235 feet, and 24 nozzles at plant elevation of at l least 250 feet.
- 7. The FPS provides two fire Inspection of each fire water The volume of each fire water water storage tanks, each capable storage tank will be performed. storage tank supplying the FPS is of holding at least 300,000 at least 300,000 gallons.
gallons of water.
- 8. Two FPS fire pumps provide Testing and/or analysis of each The tests and/or analysis concludes at least 2000 gpm each at a total fire pump will be performed. that each fire pump provides a head of at least 300 ft. flow rate of at least 2000 gpm at a total head of at least 300 ft.
- 9. The fuel tank for the diesel- Inspection of the diesel-driven The volume of the diesel driven driven fire pump is capable of fire pump fuel tank will be fire pump fuel tank is at least holding at least 240 gallons. performed. 240 gallons.
- 10. Individual fire detectors Testing will be performed on the The tested individual fire detectors provide fire detection capability as-built individual fire detectors respond to simulated fire I and can be used to initiate fire in the fire areas identified in Tier conditions.
I alanns in areas containing safety- 1 Material, subsection 3.3, Table i related equipment. 3.3-3. (Individual fire detectors will be tested using simulated fire conditions.) I 11. The FPS seismic standpipe Inspection for the existence of a Valve FPS-PL-V101 exists and can subsystem can be supplied from cross-connect valve from the connect the FPS seismic standpipe the FPS fire main by opening the FPS seismic standpipe subsystem subsystem to the FPS plant fire normally closed cross-connect to FPS plant fire main will be main. valve to the FPS plant fire main. performed.
=-
0 2.3.4-4 W Westinghouse oMAAC S\reve'. iO20304.wpf: 1 b-071498
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Tier 1 Material FIRE PROTECTION SYSTEM - O Revision: 6 Effective: July 1998 i Table 2.3.4 3 Component Name Tag No. Location Motor-driven Fire Pump FPS-MP-01 A Turbine Building Diesel-driven Fire Pump FPS-MP-01B Yard Jockey Pump FPS-MP-02 Turbine Building Primary Fire Water Tank FPS-MT-01A Yard Secondary Fire Water /Clearwell Storage Tank FPS-MT-OlB Yard Fire Pump Diesel Fuel Day Tank FPS-MT-02 Turbine Building A U
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Ti:r 1 Material MECHANICAL HANDLING SYSTEM = l Revision: 6 -n [') (_ - Effective: July 1998 _ 2.3.5 Mechanical Handling System Design Description l The mechanical handling system (MHS) provides for lifting heavy loads. The MHS equipment can be ! operated during shutdown and refueling. The component locations of the MHS are as shown in Table 2.3.5-3.
- 1. The functional arrangement of the MHS is as desenbed in the Design Description of this Section 2.3.5.
- 2. The seismic Category I equipment identified in Table 2.3.5-1 can withstand seismic design basis loads without loss of safety function.
- 3. The MHS provides the following safety-related functions:
a) The containment polar crane prevents the uncontrolled lowering of a heavy load. b) The equipment hatch hoist prevents the uncontrolled lowering of a heavy load.
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) 4. The spent fuel shipping cask crane cannot move over the spent fuel pool.
(J~ Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.5-2 specifies the inspections, tests, analyses, and associated acceptance criteria for the MHS. i i l l
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2.3.5-1 [ WBStirighouse o:\lT AAC Svev6Mt020305.wpf;1 b-071498
Tier 1 Mcterial MECHANICAL HANDLING SYSTEM -
== l Revision: 6 -
Effective: July 1998 _ Table 2.3.51 Class IE/ 4 Seismic Qual. for Equipment Name Tag No. Cat. I Harsh Envir. Safety Function Containment Polar Crane MHS-MH-Ol Yes No/No Avoid uncontrolled I lowering of heavy load { Equipment Hatch Hoist MHS-MH-05 Yes No/No Avoid uncontrolled lowering of heavy load O 1 l O 2.3.5-2 W-W85tingh0llS8 o:\lTAACSVevfiut020305.wpf.1 b-071498 l _________w
Tier 1 Mit: rill MECHANICAL HANDLING SYSTEM m~ ( Revision: 6 ~ z
\, Effective: July 1998 1 t Table 2.3.5 2 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria l 1. The functional arrangement of Inspection of the as-built system The as-built MHS conforms with I the MHS is as described in the will be performed.' the functional arrangement as Design Description of this described in the Design Section 2.3.5. Description of this Section 2.3.5.
- 2. The seismic Category 1 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. m 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. 3.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 vesse: head and integrated heac package. 3.b) The equipment hatch hoisi 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.
- 4. The spent fuel shipping cask Testing of the spent fuel The spent fuel shipping cask crane crane cannot move over the spent shipping cask crane is does not move over the spent fuel fuel pool. performed. pool.
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Tier 1 M'.t: rill MECHANICAL HANn!JNG SYSTEM bT ~ ~ Revision: 6 Effective: July 1998 Table 2.3.5 3 Component Name Tag No. Component Location Containment Polar Crane MHS-MH-01 Containment Equipment Hatch Hoist MHS.MH-05 Containment Spent Fuel Shipping Cask Crane MHS-MH-02 Auxiliary Building O O 2.3.5-4 W85tingh0USB o:\lTAACSVevmit020305.wpf:1 b-071498 l
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Tier 1 M;terial NORMAL RESIDUAL HEAT REMOVAL SYSTEM == - /O Revision: 6 - 5 V Effective: July 1998 _ 2.3.6 Normal Residual IIeat Removal System The normal residual heat removal system (RNS) e .. oves hett from the core and eactor coolant system (RCS) and provides RCS low temperr .e over-pressure (LTOP) protection at reduced RCS pressure and temperature conditions after thatdown. The RNS also provides a means for cooling the in-containment refueling water storage tank (IRWST) during normal plant operation. The RNS is es shown in Figure 2.3.6-1 and the RNS component locations are as shown in Table 2.3.6-5.
- 1. The functional arrangement of the RNS is as described in the Design Description of this Section 2.3.6.
- 2. a) The components identified in Table 2.3.6-1 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 accordance with ASME Code Section III requirements.
- 3. a) Pressure boundary welds in components identified in Table 2.3.6-1 as ASME Code Section III 3 meet ASME Code Section III requirements.
)
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 bounda2y integrity at its design pressure.
- 5. a) The seismic Category I equipment identified in Table 2.3.6-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.3.6-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss ofits functional capability.
- 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.
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Tier 1 Mit:rici NORMAL RESIDUAL HEAT REMOVAL SYSTEM == -" Revision: 6 5 Effective: July 1998 _
- 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 1E 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) The RNS provides heat removal from the reactor coolant dunng shutdown operations. c) The 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). 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) Controlr exist in the MCR to cause those remotely operated valves identified in Table 2.3.6-1 l 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. )
l b) After loss of motive power, the remotely operated valves identified in Table 2.3.6-1 assume I the indicated loss of motive power position. 2.3.6-2 3 WB5tilighouse o:\lTAACSVev6Vt020306.wpt:1 b-071798
Tier 1 Mat: rill l NORMAL RESIDUAL HEAT REMOVAL SYSTEM - " Revision: 6 - { E i s , Effective: July 1998
- 13. Controls exist in the MCR to cause the pumps identified in Table 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 D 1 l l O LJ 2.3.6-3 [ W85tiligh00SB o vTAACSvev64020306.wpf:1 b-071798
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I l Tier 1 M:terial I i l
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Revision: 6 =g [ u/ Effective: July 1998 Table 2.3.6 3 i Equipment Name Tag No. Display Control Function RNS Pump 1 A (Motor) RNS-MP-01 A Yes Start (Run Status) RNS Pump IB (Motor) RNS-MP-Ol B Yes Start (Run Status) RNS Flow Sensor RNS-Ol A Yes . RNS Flow Sensor RNS-OlB Yes . Note: Dash (-) mdicates not applicable. f~, r i
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Om 0:\lTAACS\rev6\it020306 wpf:1b-0 9
1 Tier 1 Material l NORMAL RESIDUAL HEAT REMOVAL SYSTEM = EE Revision: 6 5 Effective: July 1998 Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria j 1 Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built RNS confonns with the RNS is as described in the will be performed. the functional arrangement Design Description of this described in the Design 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 as-built components as design repons 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 The ASME Code Section III Table 2.3.6-2 as ASME Code the as-built piping as design reports exist for the as-built Section III is designed and documented in tha ASME design piping identified in Table 2.3.6-2 constructed in accordance with reports. as ASME Code Section III. ASME Code Section III requirements. 3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes that components identified in pressure boundary welds will be the ASME Code Section III Table 2.3.6-1 as ASME Code performed in accordance with requirements are met for non-Section III meet ASME Code the ASME Code Section III. destructive examination of pressure 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 2.3.6-2 pressure boundary welds will be the ASME Code Section III as ASME Code Section 111 meet performed in accordance with requirements are met for non-ASME Code Section 111 the ASME (.aic Section III. destructive examination of pressure requirements. bo'mdary welds. 4.a) The components identified A hydrostatic test ;tli25 psi will A report exists and concludes that in Table 2.3.6-1 as ASME Code be performed on the 900 psi the results of the hydrostatic test of Section III retain their pressure design pressure components the components identified in boundary integrity at their design required by the ASME Code Table 2.3.6-1 as ASME Code pressure. Section Ill to be hydrostatically Section III conform with the tested. requirements of the ASME Code Section III. O 2.3.6-10 [ W8Stiflgh00S8 o:VT AACSVev6M020306.wpf:1 tH)71798 l
Tier 1 Mr.t: rill i fn) NORMAL RESIDUAL HEAT REMOVAL SYSTEM Revision: 6 Effective: July 1998
== =
E Ei f Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.b) The piping identified in A hydrostatic test 21125 psi will A report exists and concludes that Table 2.3.6-2 as ASME Code be performed on the 900 psi the results of the hydrostatic test of Section III retains its pressure design pressure piping required by the piping identified in Table 2.3.6-2 boundary integrity at its design the ASME Code Section III to be as ASME Code Section III confona pressure. hydrostatically tested. with the requirements of the ASME Code Section III. 5.a) The seismic Category I i) Inspection will be performed to i) 'Ihe seismic Category I equipment identified in verify that the seismic Category I equiptrent 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 Island. ii) Type tests, analyses, or a ii) A repon exists and coricludes 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. O iii) Inspection will be performed iii) A report exists and concludes for the existence of a report that the as-installed equipment verifying that the as-installed including anchorage is seismically equipment including anchorage is bounded by the tested or analyzed seismically bounded by the tested conditions. or analyzed conditions. 5.b) Each of the lines identified in Inspection will be performed for A report exists and concludes that Table 2.3.6-2 for which functional the existence of a 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 withstand combined normal and requirements for functional functional capability is required seismic design basis loads without capability. meets the requirements for a loss of its functional capability. functional capability.
- 6. Each of the as-built lines Inspection will be performed for An LBB evaluation 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 I the dynamic effects of a rupture of Tier 1 Material, Section 3.3, and concludes that protection from the line. Nuclear Island Buildings, contains the dynamic effects of a line break the design descriptions and is provided.
inspections, tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture. V j 2.3.6-11 [ W85tiflgh0USB oNT AACSvev6Vt020306.wpf:1 t>072998 , J t 1 L_________. _ _ _ . l
l TIGr 1 Materid NORMAL RESIDUAL HEAT REMOVAL SYSTEM EE ~3 Revision: 6 ' Effective: July 1998 - Table 2.3.6-4 (cont.) Inspections. Tests, Analyses, and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 7.a) The Class IE equipment Type tests, analyses, or a A report exists and concludes that identified in Tables 2.3.61 as combination of type tests and the Class IE equipment identified in being qualified for a harsh analyses will be perfonned 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 IE equipment identified in powered from their respective signal in each Class IE division. Teble 2.3.6-1 when the assigned Class 1E division. Class IE division is provided the test signal. I 7.c) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material, Section 3.3. between RNS Class IE divisions. Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class IE cable. I 8.a) The RNS preserves See Tier 1 Material, See Tier 1 Material, containment integrity by isolation subsection 2.2.1, Containment subsection 2.2.1, Containment of the RNS lines penetrating the System. Sy stem. 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 the RCS during shutdown on the low temperature the valve vendor code plate is not 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 i relief requirements. ) l ii) Testing and analysis in ii) A report exists and concludes ) accordance with the ASME Code that the relief valve opens at a ! Section III will be performed to pressure such that the relief capacity determine set pressure, is not less than 555 gpm at a pressure of 621 psig. O 2.3.6-12 W_ Westinghouse oMAACSVev6Vt020306 wpf:1t>072998
Tier 1 Mat: rial NORMAL RESIDUAL HEAT REMOVAL SYSTEM Em HE: Revision: 6 = -! Q(/ Effective: July 1998 _ 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 Bru/hr *F. ii) Testing will be performed to ii) Each RNS pump provides at confirm that the RNS can provide least 900 gpm net flow to the RCS flow through the RNS heat when the hot leg water level is at an exchangers when the pump elevation 15.5 inches 2 inches suction is aligned to the RCS hot above the bottom of the hot leg. leg and the discharge is aligned to both PXS DVI lines with the RCS at atmospheric pressure. iii) Inspection will be performed iii) The RCS cold legs piping of the reactor coolant loop piping. centerline is 17.5 inches 2 inches above the hot legs piping centerline. iv) Inspection will be performed iv) The RNS pump suction piping of the RNS pump suction piping. from the hot leg to the pump suction pining low point does not form a local high point (defined as an upward slope with a vertical rise greater than 3 inches). v) Inspection will be performed v) The RNS suction line connected of the RNS pump suction nozzle to the RCS is constructed from 20-connection to the RCS hot leg. inch Schedule 160 pipe. 9.c) The RNS provides le e Testing will be performed to Each RNS pump provides at least pressure makeup flow fom the confirm that the RNS can provide 925 gpm net flow to the RCS when IRWST to the RCS for scenarios low pressure makeup flow from the water level above the bottom of following actuation of the ADS. the IRWST to the Rd when the the IRWST is 4 feet 212 inches, pump suction is aligned to the IRWST and the discharge is aligned to both PXS DVIlines with RCS at atmospheric pressure. O \
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J 2.3.6-13 MNSO oNTAACSvev6Nt020306 wpf:1tF071798 L _ _ _ _ _ _ _ _ _ .__ - --
Tier 1 MateriCl I NORMAL RESIDUAL HEAT REMOVAL SYSTEM EE r Revision: 6 E I Effective: July 1998 _ Table 2.3.6-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 9.d) The RNS provides heat Testing will be performed to Each RNS pump provides at least removal from the in-containment confirm that the RNS can provide 925 gpm to the IRWST. refueling water storage tank flow through the RNS heat (IRWST). exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST.
- 10. Safety-related displays Inspection will be performed for Safety-related displays identified in identified in Table 2.3.6-1 can be retrievability of the safety-related Table 2.3.6-1 can be retrieved in the retrieved in the MCR. displayr, in the MCR. MCR.
Il a) Controls exist in the MCR Stroke testing wi.'l be performed Controls in the MCR operate to to cause er.ose remotely operated on the remotely operated valves cause those remotely operated valves identified in Table 2.3.61 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. 11.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 sigral identified in the table after receiving from the PMS a signal from the PMS.
O 2.3.6-14 W Westinghouse exTAAesveveut0203%.wpN071798 L _ ________
Tier 1 Material NORMAL RESIDUAL HEAT REMOVAL SYSTEM EE Revision: 6 b Effective: July 1998 Table 2.3.5-.1 (cent.) 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 espability of changes posi* inn 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. iii) Tests of the as-installed iii) Each motor-operated valve moto . operated valves will be changes position as indicated in performed under preoperational Table 2.1.2-1 under preoperational flow, differential pressure and test conditions. temperature conditions. O. iv) Exercise testing of the check
;O 4 valves active safety functions iv) Each check valve changes position as indicated in identified in Table 2.3.61 will be Table 2.3.6-1.
performed under preoperational test pressure, temperature and fluid flow conditions. 12.b) After loss of motive power, Testing of the installed valves will Upon loss of motive power, each the remotely operated valves be performed under the conditions remotely operated valve identified in identified in Table 2.3.6-1 assume 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. l
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2.3.6-15 l WB5tlfigh00S8 oNTAACSvev6M020306 wpf;1b-071798 l
Tier 1 Material
- =
NORMAL RESIDUAL HEAT HEMOVAL SYSTEM [:E Revision: 6 - Effective: July 1998 _
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Table 2.3.6 5 I Component Name Tag No. Component Location RNS Pump A RNS-MP-Ol A Auxiliary Building RNS Pump B RNS MP-OlB Auxiliary Building RNS IIcat Exchanger A RNS-ME-01 A Auxiliary Building RNS Heat Exchanger B RNS-ME-OlB Auxiliary Building O O T Westinghouse on TAAcsveveJt020306 wpf:1b O7 79
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Tier 1 Material l SPENT FUEL POOL COOLING SYSTEM "* ~~:
/O Revision: 6 ..
() Effective: July 1998 _ 2.3.7 Spent Fuel Pool Cooling System Design Description The spent fuel pool cooling system (SFS) removes decay heat from the water in the spent fuel pool and transfers the heat to the component cooling water system during normal modes of operation. The SFS purifies the water in the spent fuel pool, fuel transfer canal, and in-containment refueling water storage tank during normal modes of operation. The SFS is as shown in Figure 2.3.7-1 and the component locations of the SFS are as shown in Table 2.3.7 5.
- 1. The functional arrangement of the SFS is as described in the Design Description of this Section 2.3.7.
- 2. The piping identified in Table 2.3.7-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
- 3. Pressure boundary welds in piping identified in Table 2.3.7-2 as ASME Code Section Ill meet ASME Code Section III requirements.
O) i V
- 4. The piping identified in Table 2.3.7-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
- 5. The seismic Category I equipment identified in Table 2.3.7-1 can withstand seismic design basis loads without loss of safety function.
- 6. a) The Class IE components identified in Table 2.3.7-1 are powered from their respective Class lE division.
b) Separation is provided between SFS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable. 1 l
- 7. The SFS provides the following safety-related functions:
l 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 makeup water from safety-related sources. i 8. The SFS provides the nonsafety-related function of removing spent fuel decay heat using pumped l flow through a heat exchanger.
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i 2.3.7-1 W85t@0US8 o:\lTAACS\revfAit020307.wpf:1 b-071498 I l b_ __ ___ ___ ____ _
Tier 1 Materica l l
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SPENT FUEL POOL COOLING SYSTEM
- E Revision: 6 Effective: July 1998
- 9. Safety-related displays identified in Table 2.3.7-1 can be retrieved in the main control room (MCR).
- 10. Controls exist in the MCR to cause the pumps identified in Table 2.3.7-3 to perform their listed functions.
I1. 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 i l O l j W85tingh00SB o:VTAACSVev6\it020307.wpf:1b- 1 98 l l
i Tier 1 Materi:1 SPENT FUEL POOL COOLING SYSTEM EE == Revision: 6 = = s Effective: July 1998 _ l I Table 2.3.71 ' Class IE/ Seismic Qual. far Equipment Name Tag No. Cat.I Harsh Envir. Safety Related Display Spent Fuel Pool Level Sensor SFS-019A Yes Yes/No Yes Spent Fuel Pool Level Sensor SFS-019B Yes Yes/No Yes Spent Fue! Pool Level Sensor SFS-019C Yes Yes/No Yes Table 2.3.7 2 Line Name Line Number ASME Code Section 111 Fuel Transfer Canal Drain LO47 Yes Cask Washdown Pit Drain LO68 Yes Cask Loading Pit Drain LO43 Yes O- Transfer Branch Line LO45 Yes Reactor Cavity Drain LO30 Yes Table 2.3.7 3 Equipment Name Tag No. Display Control Function SFS Pump 1 A SFS-MP-01 A Yes Start (Run Status) SFS Pump IB SFS-MP-OlB Yes Start (Run Status) SFS Flow Sensor SFS-13A Yes - SFS Flow Sensor SFS-13B Yes - Spent Fuel Pool Temperature Sensor SFS-018 Yes - l Note: Dash (-) indicates not apphcable. I l ! 2.3.7-3 ! [ W85tiflgh00S8 o:\lT AACSVev6\it020307.wpf:1 b-071498
Tier 1 Mcterial j SPENT FUEL POOL COOLING SYSTEM == Hg Revision: 6 = Effective: July 1996 - Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptanee Criteria l Design Commitment Inspections, Tests, AnaI Jses Acceptance Criteria
- 1. The functional arrangement of Inspection of the as-built system The as-built SFS conforms with l the SFS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design l Section 2.3.7. Description of this Section 2.3.7.
- 2. The 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 III is designed and in the ASME design reports. built piping identified in constructed in accordai ce 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 i 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 rnet 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. 1 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. O W WBSilIlgh00SB 2.3.7-4 ans. o:'.lTAACS\rev6Vt020307.wpf:1 b-071498
l l Tier 1 Materi:1 l l SPENT FUEL POOL COOLING SYSTEM =Z l Revision: 6 = E Effective: July 1998 1 1 Table 2.3.7 4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment Inspections, Tests, Analyses Acceptance Criteria 6.a) The 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 division. the assigned Class IE division is provided the test signal. l 6.b) Separation is provided See Tier 1 Material, Section 3.3, See Tier 1 Material, Section 3.3, between SFS Class IE divisions. Nuclear Island Buildings. Nuclear Island Buildings. and between Class IE divisions and non-Class IE cable. l l 7.a) The SFS preserves contain- See Tier 1 Material, subsection See Tier 1 Material, subsection ment integrity by isolation of the 2.2.1, Containment System. 2.2.1, Containment System. SFS lines penetrating the containment. 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 water in the pool and providing includes a sufficient volume of the fuel and to the elevation makeup water from safety-related water. 6 feet below the operating deck is sources. greater than or equal to 46,700 gallons ii) Inspection will be performed ii) The volume of the cask to verify the cask washdown pit washdown pit is greater than or l includes sufficient volume of equal to 30,900 gallons. water. iii) A safety-related flow path lii) See item 1 of this table. exists from the cask washdown pit to the spent fuel pool. I iv) See Tier i Material iv) See Tier i 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 fcr the makeup water supply line from the passive containment from the PCS water storage tank cooling system (PCS) water to the spent fuel pool. storage tank to the spent fuel pool. l 2.3.7 5 [ W85tiflgh00S8 oNTAACSVev69t020307.wpf:1 b-071498 i l
Tier 1 Mat;ri:1 SPENT FUEL POOL COOLING SYSTEM i EE Revision: 6 - Effective: July 1998 . Table 2.3.7-4 (cont.) Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria
- 8. The SFS provides the i) Inspection will be performed i) A report 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 Bru/hr *F.
ii) Testing will te performed to ii) Each SFS pump produces at confirm that each SFS pump least 675 gpm through its heat provides flow through its heat exchanger. exchanger when taking suction from the SFP and returning flow to the SFP.
- 9. Safety-related displays inspection will be performed for Safety-related displays identified identified in Table 2.3.7-1 can be retrievability of the safety-related in Table 2.3.7-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.
- 10. Controls exist in the MCR to Testing will be performed to Controls in the MCR cause cause the pumps identified in actuate the pumps identified in pumps identified in Table 2.3.7-3 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. I1. Displays of the SFS Inspection will be performed for Displays of the SFS parameters parameters identified in retrievability in the MCR of the identified in Table 2.3.7-3 are Table 2.3.7-3 can be retrieved in displays identified in Table 2.3.7-3. retrieved in the MCR. the MCR. Table 2.3.7 5 Component Name Tag No. Component Location SFS Pump A SFS-MP-01A Auxiliary Building SFS Pump B SFS-MP-Ol B Auxiliary Building SFS Heat Exchanger A SFS-ME-01 A Auxiliary Building SFS Heat Exchanger B SFS-ME-OlB Auxiliary Building 2.3.7-6 [ WB5tingh0USB ONTAACSVev6iit020307.wpt i b-071498
1 Tier 1 Material l SPENT FUEL POOL COOLING SYSTEM EE == i Revision: 6
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Tier 1 Material SERVICE WATER SYSTEM - Revision: 6 ' V Effective: July 1998 1 2.3.8 Service Wales System Design Description The service water system (SWS) transfers heat from the component cooling water heat exchangers to the atmosphere. The SWS operates during normal modes of plant operation, including startup, power operation (full and partial loads), cooldown, shutdown, and refueling. The SWS is a. shown in Figure 2.3.8-1 and the component locations of the SWS are as shown Table 2.3.8-3.
- 1. The functional arrangement of the SWS is as described in the Design Description of this Section 2.3.8.
- 2. The SWS provides the following nonsafety-related functions:
a) 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.
- 3. Controls exist in the main control room (MCR) to cause the components identified in 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. l O 2.3.8-1 3 W8Stingh00S8 o:VTAACSVev6Mt020308.wpf:b-071798
Tier 1 Material SERVICE WATER SYSTEM p UI;; Revision: 6 = E Effective: July 1998 1 .ee Table 2 3.8-1 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-Ol A Yes Start (Run Status) Service Water Pump 1 A Flow Sensor SWS-004A Yes - Service Water Pump IB Flow Sensor SWS-004B Yes - Service Water Fump A Discharge Valve SWS-PL-V002A Yes Open (Valve Position) Servic. Water Pump B Discharge Valve SWS-PL-V002B Yes Open (Valve Position) Service Water Pump A Discharge SWS-005A Yes - Temperature Sensor Service Water iw 1p B Discharge SWS-005B Yes - Temperature Sensor Note: Dash (-) indicates not applicable. O 2.3.8-2 W Westinghouse o:\lTAACS\rev6'Jt020308.wpf:b-071798
Tier 1 Material
- SERVICE WATER SYSTEM =s Revision: 6 E Effective: July 1998 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 the SWS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design 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 componerit 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) De 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 Cont ols in the MCP. operate to
\ cause the components identified in components in Table 2.3.8-1 cause the components listed in Table 2.3.8-1 to perform the listed using controls in the MCR. 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.
2.3.8-3 M 5t @ 00S8 c:\lTAACSirev6\it020308.wpf.t)-071798 I
Tier 1 Msterial SERVICE WATER SYSTEM E === Revision: 6 E l Effective: July 1998 _ Table 2.3.8-3 Component Name Tag No. Component Location Service Water Pump A SWS-MP-01 A Turbine Building or yard Service Water Pump B SWS-MP-01B Turbine Building or yard Service Water Cooling Tower SWS ME-01 Yard O O 2.3.8-4 W Westinghouse oMAACSVev6bt020308.wpfbO71798 _ _ _ _ _ _ _ _ _ _ _ _ ~
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