ML20196K634

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Rev 2 to AP600 Design Control Document. with Page Change Instructions
ML20196K634
Person / Time
Site: 05200003
Issue date: 03/31/1999
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20196K633 List:
References
NUDOCS 9904020283
Download: ML20196K634 (25)
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Enclosure 2 toletter DCP/NRC1454 AP600 DESIGN CONTROL DOCUMENT MARCH 1999 PAGE CHANGE INSTRUCTIONS O

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AP600 DESIGN CONTROL DOCUMENT- 3/99 REVISION PAGE CHANGE INSTRUCTIONS Remove Present oaoes Insert Paoes VOLUMEt AP600 Document Cover Sheet, Revision 1 AP603 Document Cover Sheet, Revision 2 List of effective pages - page 1 List o effective pages -page 1 List of effective pages -page 17 List of effective pages -page 17 List of effective pages -page 31 List of effective pages -page 31 Intro-1 Intro-1 Intro-7 through Intro-10 Intro-7 through Intro-10 VOLUME 2 Page 1.4-1 through 1.4 3 Page I A-1 through 1.4-3 VOLUME 5 Page 4.3-17 Page 4.3-17 VOLUME 9 Page 14.2-7 Page 14.2-7 Page 14.4-2 Page 14.4-2 I

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i AP600 DOCUMENT COVER SHEET Form 58202G(3/99) AP600 CENTRAL FILE USE ONLY: TDC: IDS: I S RFS#: RFS ITEM #:

APEDO DOCUMENT NO. REVISION NO. ASSIGNED TO

' GW-GL 700 2 Page 1 of 2 --

ALTERNATE DOCUMENT NUMBER: WCAP-15150 WORK BREAKDOWN #: 3.4.1 DESIGN AGENTORGANIZATION: Westinghouse TITLE: AP600 Design Control Document ATTACHMENTS: DCP #/REV. INCORPORATED IN THIS DOCUMENT None REVISION:

Incorporates changes requested by NRC and Company CALCULATION / ANALYSIS

REFERENCE:

name change into Revision 1 (2/99)

None ELECTRONIC FILENAME ELECTRONIC FILE FORMAT ELECTRONIC FILE DESCRIPTION Wordperfect (C) WESTINGHOUSE ELECTRIC COMPANY LLC 1999 WESTINGHOUSE PROPRIETARY CLASS 2 This document contains information proprietary to Westinghouse Electric Company LLC: it is submitted in confglence and is to be used solely for the purpose for which it is fumished and retumed upon request. This document and such information is not to be reproduced, transmitted, disclosed or used otherwise in whole or in part without prior written authorization of Westinghouse Electric Company LLC, subject to the legends contained hereof.

WESTINGHOUSE PROPRIETARY CLASS 2C This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreemer,t under which it was provided to you.

X WESTINGHOUSE CLASS 3 (NON PROPRIETARY)

COMPLETE 1 IF WORK PERFORMED UNDER DESIGN CERTIFICATION QB COMPLETE 2 IF WORK PERFORMED UNDER FOAKE.

1 DOE DESIGN CERTIFICATION PROGRAM - GOVERNMENT LIMITED RIGHTS STATEMENT [see page 2)

Copyright statement: A license is reserved to the U.S. Govemment under contract DE-ACO3-90SF18495.

X DOE CONTRACT DELIVERABLES (DELIVERED DATA)

Subject to specified exceptions, disclosure of this data is restncted until September 30,1995 or Design Certification under DOE cuntract DE-ACO3-90SF18495, whichever is later.

EPRI CONFIDENTIAL: NOTICE: 1X 2 3 4 5 CATEGORY: AX B C D E F 2_ ARC FOAKE PROGRAM - ARC LIMITED RIGHTS STATEMENT [See page 21 Copyright statement: A license is reserved to the U.S. Govemment under contract DE-FCO2-NE34267 and subcontract ARC-93 3-SC-001.

_ ARC CONTRACT DELIVERABLES (CONTRACT DATA)

Subject to specified exceptions, disclosure of this data is restricted under ARC Subcontract ARC-93-3-SC-001.

ORIGINATOR SIGNATqRE/DATE Susan V. Fanto C%.M A 3/4 9i AP600 RESPONSIBLE MANAGER SIGNATURE

  • APPROVAL DATE Brian A. McIntyre .

[g g g (V released for use., Approval of the responsible manager signifies that document is complete, all required rdiews are complete, electro %c file ape 00.COVERDOC

AP600 DOCUMENT COVER SHEET Page3 Form 58202GR/94) LIMITED RIGHTS STATEMENTS DOE GOVERNMENT LIMITED 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 permission of the contractor, be used for purposes of I manufacturer nor disclosed outside the government; except that the govemment may disclose these data outside the government for the following purposes, if any, provided that the government rnakes sucn disclosure subject to prohibition against further use and disclosure:

(I) This

  • Proprietary Data' may be disclosed for evaluation purposes under the restrictions above.

(II) The " Proprietary Data' may be disclosod to the Electric Power Research Instrtute (EPRI), eletric utility representativu and their direct consultants, excluding direct w.sw.idiJ competitors, and the DOE National Laboratories under the prohibitions and restrictions above.

(B) This notice shall be marked on any reproduction of these data, in whole or in part.

ARC UMITED RIGHTS STATEMENT:

This proprietary data, fumished under Subcontract Number ARC-93-3-SC-001 with ARC may be duplicated and used by the government and ARC, subject to the limitations of Article H-17.F. of that subcontract, with the express limitations that the proprietary data may not be d;sclosed outside the govemment or ARC, or ARC's Class 1 & 3 mernbers or EPRI or be used for purposes of rnar.ufacture without prior permission of the Subcontractor, except that further disclosure or use may be made solely for the fullowing 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 propnetary 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 no background proprietary data.

EPRI CONFIDENTIALITY / OBLIGATIONNOTICES NOTICE 1: The data in this document is subject to no s T.hality obligations.

NOTICE 2: The data in this document is propnetary and confidential to Westinghouse Electric Company LLC and/or its Contractors, it is forwarded to recipient under an obligation of Confidence and Trust for limited purposes only. Any use, disclosure to unauthorized persons, or copying of this document or parts thereof is prohibited except as agreed to in advance by the Electric Power Research institute (EPRI) and Westinghouse Electric Company LLC. Recipient of this data has a dt.'.ty to inquire of EPRI and/or Westinghouse as to the uses of the information contained herein that are permitted.

NOTICE 3: The data in this document is proprietary and confidential to Westinghouse Electric Company LLC and/or its Contractors. It is forwarded to recipient under an obligation of Confidence and Trust for use only in evaluation tasks specifically authorized by the Electric Power Research institute (EPRI). Any use, disclosure to unauthorized persont, or copying this document or parts thereof is prohibited except as agreed to in advance by EPRI and Westinghouse Electric Cornpany LLC. 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, directfy or through EPRI, when requestod to do so.

NOTICE 4: The data in this document is proprietary and confidential to Westinghouse Electre Comrany LLC and/or its Contractors. It is being revealed in MTh,6 and trust only to Employees of EPRI and to certain contractors of EPRI 'or li'nited evaluation task: authorized by EPRI. l Any use, disclosure to unauthorized persons, or copying of this document or pa'ts thereof is p0nibited. This Document and any copies or excerpts thereof that may have been generated are to be retumed to Westinghouse, directly or through EPRI, wten requested to do so.

NOTICE 5: The data in this document is proprietary and confidential to Westinghouse Electric Company LLC and/or its Contrac. ors. Access to this data is given in Confidence and Trust only at Westinghouse facilities for limited evaluation tasks assigned by EPRL Any use, disclosure to unauthoaized persons, or copying of this document or parts thereof is prohibited. Neither this document nor any excerpts therefrom are to be removed from Westinghouse facilities.

EPRI CONFIDENTIALITY / OBLIGATION CATEGORIES .

CATEGORY 'A"- (See Delivered Data) Consists of CONTRACTOR Foreground Data that is contained in an issued reported. l CATEGORY *B" - (See Delivered Data) Consists of CONTRACTOR Foreground Data that is not contained in an issued report, except for computer programs.

CATEGORY *C"- Consists of CONTRACTOR Background Da except for computer programs.

CATEGORY 'D'- Consists of computer programs developed in the course of perfonWng the Work.

CATEGORY *E'- Consists ed computer programs developed prior to the Effective Date or after the Effective Date but outside the scope of the Work.

CATEGORY *F"- Consists of administrative plans and administrative reports.

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AP600 Design ControlDocument f\ * '

1 AP600 List of Effective Pages Volume 1 Page Revision Page Revision Page Revision Page Revision Intro-i original 2.1.2-3 original 2.1.3-14 original 2.2.3-9 original Intro-il original 2.1.2-4 original 2.1.3-15 original 2.2.3-10 original 2.1.2-5 original 2.2.3-11 original l Intro-1 (3S9) 2.1.2-6 original 2.2.1-1 original 2.2.3-12 original Intro-2 original 2.1.2-7 original 2.2.1-2 original 2.2.3-13 original Intro-3 original 2.1.2-8 original 2.2.1-3 original 2.2.3-14 original Intro-4 (2/99) 2.1.2-9 original 2.2.1-4 original 2.2.3-15 original Intro-5 (2S9) 2.1.2-10 original 2.2.1-5 original 2.2.3-16 original Intro-6 (2/99) 2.1.2-11 original 2.2.1-6 original 2.2.3-17 original Intro-7 (3S9) 2.1.2-12 original 2.2.1-7 original 2.2.3-18 original Intro-8 (3/99) 2.1.2-13 original 2.2.1-8 original 2.2.3-19 original Intro-9 (3/99) 2.1.2-14 original 2.2.1 9 original 2.2.3-20 original Intro-10 (3/99) 2.1.2-15 original 2.2.1-10 original 2.2.3-21 original 2.1.2-16 original 2.2.1-11 original 2.2.3-22 original i original 2.1.2-17 original 2.2.1-12 original 2.2.3-23 original li original 2.1.2-18 original 2.2.1-13 original 2.2.3-24 original lii original 2.1.2-19 original 2.2.1-14 original 2.2.3-25 original iv original 2.1.2-20 original 2.2.1-15 original 2.2.3-26 original G v original 2.1.2-21 original 2.2.3-27 original 2.1.2-22 original 2.2.2-1 original 2.2.3-28 original 1.1-1 original 2.1.2-23 original 2.2.2 2 original 2.2.3-29 original 1.1-2 original 2.1.2-24 original 2.2.2-3 original.

2.1.2-25 original 2.2.2-4 original 2.2.4-1 original 1.2-1 original 2.1.2-26 criginal 2.2.2-5 original 2.2.4-2 original 1.2-2 original 2.1.2-27 original 2.2.2-6 original 2.2.4-3 original 2.1.2-28 original 2.2.2-7 origint.1 2.2.4-4 original 1.3-1 original 2.1.2-29 original 2.2.2-8 original 2.2.4-5 original 1.3-2 original 2.1.2-30 original 2.2.2-9 original 2.2.4-6 original 1.3-3 original 2.1.2-31 original 2.2.2-10 original 2.2.4-7 original 1.3-4 original 2.2.2-11 original 2.2.4-8 original 2.1.3-1 original 2.2.2-12 original 2.2.4-9 original 1.4-1 (3/99) 2.1.3-2 original 2.2.2-13 (2/99) 2.2.4-10 original 1.4-2 (3/99) 2.1.3-3 original 2.2.2-14 (2/99) 2.2.4-11 original 1.4-3 (3/99) 2.1.3-4 original 2.2.2-15 original 2.2.4-12 original 2.1.3-5 original 2.2.4-13 original 2.1.3-6 original 2.2.3-1 original 2.2.4-14 original l 2.1.1-1 original 2.1.3-7 original 2.2.3-2 original 2.2.4-15 original 2.1.12 original 2.1.3-8 original 2.2.3-3 original 2.2.4-16 original 2.1.1-3 original 2.1.3-9 original 2.2.3-4 original 2.2.4-17 original 2.1.1 -4 original 2.1.3-10 original 2.2.3-5 original 2.2.4-18 original 2.1.3-11 original 2.2.3-6 origin i 2.2.4-19 original 2.1.2-1 original 2.1.3-12 original 2.2.3-7 original 2.2.4-20 original 2.1.2-2 original 2.1.3-13 original 2.2.3-8 original 2.2.4-21 original List of Effective Pages (3t99) Page 1

AP600 Design ControlDocument AP600 List of Effective Pages Volume 1 Page Revision Page Revision Page Revision Page Revision 2.2.4-22 original 2.3.3-1 original 2.3.7-7 original 2.3.13-6 original 2.2.4-23 original 2.3.3-2 original 2.3.13-7 original 2.2.4-24 original 2.3.3-3 original 2.3.8-1 original 2.3.13-8 original 2.3.3-4 original . 2.3.8-2 original 2.2.5-1 original 2.3.3-5 original 2.3.8-3 original 2.3.14-1 original 2.2.5-2 original 2.3.8-4 original 2.3.14-2 original 2.2.5-3 original 2.3.4-1 original 2.3.8-5 original 2.3.14-3 original 2.2.5-4 original 2.3.4-2 original 2.2.5-5 original 2.3.4-3 original 2.3.9-1 original 2.3.15-1 original 2.2.5-6 original 2.3.4-4 original 2.3.9-2 original 2.3.15-2 original 2.2.5-7 original 2.3.4-5 original 2.3.9-3 original 2.3.15-3 original J.2.5-8 original 2.3.4-6 original 2.3.9-4 original 2.2.5-9 original 2.3.4-7 original 2.3.9-5 original 2.3.16-1 original 2.2.5-10 original 2.3.9-6 original 2.2.5-11 original 2.3.5-1 original 2.3.9-7 original 2.3.17-1 original 2.2.5-12 original 2.3.5-2 original 2.3.9-8 original 2.2.5-13 original 2.3.5-3 original 2.3.9-9 original 2.3.18-1 original 2.2.5-14 original 2.3.5-4 or:ginal 2.2.5-15 original 2.3.10-1 original 2.3.19-1 original 2.2.5-16 original 2.3.6-1 onginal 2.3.10-2 original 2.3.19-2 original 2.3.6-2 original 2.3.10-3 original 2.3.19-3 original 2.3.1-1 original 2.3.6-3 original 2.3.10-4 original 2.3.1 -2 original 2.3.6-4 original 2.3.10-5 original 2.3.20-1 original 2.3.1-3 original 2.3.6-5 original 2.3.10-6 original 2.3.1 -4 original 2.3.6-6 original 2.3.10-7 original 2.3.21-1 original 2.3.1-5 original 2.3.6-7 original 2.3.10 8 original l 2.3.6-8 original 2.3.10-9 original 2.3.22-1 original  !

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List of Effective Pages (2/99) Page 2

AP600 Design Control Document AP600 List of ENective Pages Volume 5 Page Revision Page Revision Page Revision Page Revision 4-i original 4.2 . original 4.3-14 original 4.3-58 original 4-ii original 4.2-26 original 4.3-15 original 4.3-59 original 4-iii original 4.2-27 original original 4.3-60 original 4-iv original 4.2-28 original l 4.3-16 4.3-17 (3/99) 4.3-61 original 4-v original 4.2-29 original 4.3-18 original 4.3-62 original 4-vi original 4.2 30 original 4.3-19 original 4.3-63 original 4-vii original 4.2-31 original 4.3-20 original 4.3-64 original 4.2-32 original 4.3-21 original 4.3-65 original 4.1-1 original 4.2-33 original 4.3-22 original 4.3-66 original 4.1-2 original 4.2-34 original 4.3-23 original 4.3-67 original 4.1-3 original 4.2-35 original 4.3-24 original 4.3-68 original 4.1-4 original 4.2-36 original 4.3-25 original 4.3-69 original 4.1-5 original 4.2-37 original 4.3-26 original 4.3-70 original 4.1-6 original 4.2-38 original 4.3-27 original 4.3-71 original 4.1-7 original 4.2-39 original 4.3-28 original 4.3-72 original 4.1-8 original 4.2-40 original 4.3-29 original 4.3-73 original 4.1-9 original 4.2-41 original 4.3-30 original 4.3-74 original 4.1-10 original 4.2 43 original 4.3-31 original 4.3-75 original 4.1-11 original 4.2-44 original 4.3-32 original 4.3-76 original 4.2-45 original 4.3-33 original 4.3-77 original 4.2-1 original 4.2-46 original 4.3-34 original 4.3-78 original 4.2-2 original 4.2-47 original 4.3-35 original 4.3-79 origina 4.2-3 original 4.2-48 original 4.3-36 original 4.3-80 original 4.2-4 original 4.2-49 original 4.3-37 original 4.3-81 original 4.2-5 original 4.2-50 original 4.3-38 original 4.3-82 original 4.2-6 original 4.2-51 original 4.3-39 original 4.3-83 original 4.2-7 original 4.2-52 original 4.3-40 original 4.3-84 original 4.2-8 original 4.2-53 original 4.3-41 original 4.3-85 original 4.2-9 original 4.2-54 original 4.3-42 original 4.3-86 original 4.2-10 t original 4.2-55 original 4.3-43 (2/99) 4.3-87 original 4.2 11 original 4.3-44 original 4.3-88 original 4.2-12 original 4.3-1 original 4.3-45 original 4.3-9 original 4.2-13 original 4.3-2 original 4.3-46 original 4'30 original 4.2-14 original 4.3-3 original 4.3-47 original +.3-91 original 4.2-15 original 4.3-4 original 4.3-48 original 4.3-92 original 4.2-16 original 4.3-5 original 4.3-49 original 4.2-17 original 4.3-6 original 4.3-50 original 4.4-1 original 4.2-18 original 4.3-7 original 4.3-51 original 4.4-2 original 4.2-19 original 4.3-8 original 4.3-52 original 4.4-3 original 4.2-20 original 4.3-9 original 4.3-53 original 4.4-4 original 4.2-21. original 4.3-10 original 4.3-54 original 4.4-5 original 4.2-22 original 4.3-11 original 4.3-55 original 4.4-6 original 4.2-23 original 4.3-12 original 4.3-56 original 4.4-7 original 4.2-24 original 4.3-13 original 4.3 original 4.4-8 original List of EHective Pages (&99) Page 17

AP600 Design Control Document AP600 j List of Effective Pages i Volun e 5 Page Revision Page Revision Page Revision Page Revision l

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DESIGN CONTROL DOCUMENT INTRODUCTION 1.0 SCOPE AND PURPOSE OF THE DESIGN CONTROL DOCUMENT This Design Control Document (DCD) is a repository of information comprising the AP600*(*) Standard Plant Design. The design control document also provides that design-related information to be incorporated by reference into Appendix C to 10 CFR Part 52 (the AP600 design certification rule).

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Applicants for a combined license pursuant to 10 CFR 52 must ensure that Appendix C to 10 CFR Part 52 and the associated Statements of Consideration are used when making licensing decisions relevant to the AP600 Standard Plant Design Further sections of this introduction summarize the contents and use of the design control document. The design control document contains this introduction, the Tier 1 Information and the Tier 2 Information for the AP600 Standard Plant Design.

Detailed information on the application and use of the AP600 design control document may be found in Appendix C to 10 CFR Part 52.

If there is a conflict between this introduction and the AP600 design certification rule, the

O AP600 design certification rule controls.

V' 1.1 Tier 1 Information Tier 1 means the portion of the design-related infoiTnation contained in the AP600 design control document that is approved and certified by the NRC. Tier 1 infonnation inc!udes:

i Definitions and general provisions; Design descriptions; 1 Inspections, tests, analyses, and acceptance criteria (ITAAC); ,

  • Significant site parameters; and

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Significant interface requirements between the AP600 Standard Plant Design and systems that are wholly of partially outside the scope of the AP600 Standard Plant Design The Tier 1 Infonnation includes a table of contents, a figure legend and an abbreviation list.

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  • AP600 is a trademark of Westinghouse Electric Company LLC (3

f Desigri Control Document - Introductrxt (3/99) Page Intro-1

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1.2 Tier 2 Information Tier 2 means the portion of the design-related information contained in the AP600 Design Control Document that is approved but not certified by the NRC. Tier 2 information includes:

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Information required by 10 CFR 52.47, with the exception of generic technical specifications and conceptual design information;

  • Information required for a final safety analysis report under 10 CFR 50.34;
  • Supporting information on the inspections, tests, and analyses that will be performed to demonstrate that the acceptance criteria in the ITAAC have been met; and Combined license (COL) information items which identify certain matters that shall be addressed in the site-specific portion of the final safety analysis report (FSAR) by an applicant who references the AP600 design certification rule Each volume of the Tier 2 Information includes a master table of contents and each chapter contains a chapter specific table of contents.

1.3 Relationship of the Tier 1 Information to the Tier 2 Information The oesign descriptions, interface requirements, and site parameters in Tier 1 are derived from Tier 2 information.

Compliance with Tier 2 is required, but generic changes to and plant-specific departures from Tier 2 are governed by the AP600 design certification rule. Compliance with Tier 2 provides a sufficient, but not the only acceptable, method for complying with Tier 1. Compliance methods differing from Tier 2 must. satisfy the change process in Section VIII of the AP600 design certification rule.

1.4 Uses of the Design Control Document An applicant for a license that wishes to reference the AP600 design certification rule shall, in addition to complying with the requirements of 10 CFR 52.77, 52.78, and 52.79, comply with the following requirements:

Incorporate by reference, as part ofits application, the AP600 design certification mle; O

Design Control Document - Introduc00n Page intro-2

l l AP600 Design Control Document l Table 1-1 l Index of AP600 Tier 2 Infermation Requiring NRC approval for Change l

l Item Expiration at Tier 2 First Full Power Reference Dimensions for Nuclear Island Structures Yes Fig. 3.7.1-16 Nuclear Island Key Structural Dimensions Yes Fig. 3.7.2-12 ASME Code,Section III Edition, Addenda Yes 3.8.2.2 5.2.1.1 ASME Code Case N-284 Yes 3.8.2.5 App 3G Design Summary of Critical Sections Yes 3.8.3.5.8 3.8.4.5.4 3.8.5.4.5 App 3H t

l Use of ACI-318-95 Yes 3.8.4.4.1 3.8.5.5 I Use of ACI 349-90 Yes 3.8.4.5.1 3.8.5.5 Use of ANS/AISC N690 ' Yes 3.8.4.5.2 Definition of critical locations and thicknesses for shield Yes Table 3.8.4-7 and auxiliary buildings Definition of critical locations and thicknesses for nuclear Yes Table 3.8.5-3 l island basemat i Seismic Qualification Standards Yes 3.10.1.1 l Methods and Procedures for Qualifying Electrical Yes 3.10.2 Equipment, Instrumentation and Mechanical Components WCAP-12488-A, Fuel Criteria Evalutdon Process" No Chapter 4 Table 1.6-1 l Maximum Fuel Rod Average Burnup No 4.1 l Fuel Principal Design Requirements No 4.1.1 Reactor Core Description (First Cycle) Yes Table 4.3-1 Nuclear Design Parameters (First Cycle) Yes Table 4.3-2 O

Design Cortot Document- keoduction (3/99) Page intro-7

AP600 Design Control Document l Table 1-1 I Index of AP600 Tier 2 Information Requiring NRC approval for Change 1 Item Expiration at Tier 2 First Full Power Reference Reacdvity Requirements for Rod Cluster Control Yes Table 4.3-3 Assemblies MOV Design and Qualification Yes 5.4.8.1.2 POV Design and Qualification Yes 5.4.8.1.3 Motor Operated Valves Yes 5.4.8.5.2 Power Operated Valves Yes 5.4.8.5.3 WCAP-13383, "AP600 Instrumentation and Control Yes Chapter 7 Hardware & Software Design, Verification & Validation Table 1.6-1 Process Report", Rev 1.

WCAP-14605, " Westinghouse Setpoint Methodology for Yes Chapter 7 Protection Systems, AP600", Rev 0 Table 1.6-1 Verification and Validation Yes 7.1.2.15 Conformance with Industry Standards Yes 7.1.4.1.8 Nuclear Island Fire Areas No Figure 9A-1 Turbine Building Fire Areas No Figure 9A-2 Annex I & H Building Fire Areas No Figure 9A-3 Radwaste Building Fire Areas No Figure 9A-4 Diesel Generator Building Fire Areas No Figure 9A-5 Natural Circulation Test First Plant Only 14.2.5 Description of "First Three Plant Tests" Third Plant 14.2.5 Verification of proper operation of core makeup tanks in Third Plant 14.2.9.1.3 recirculation mode Verification of automatic depressurization during hot 'Ihird Plant 14.2.9.1.3 functional testing Verification of proper operation of core makeup tanks to Third Plant 14.2.9.1.3 transition to draindown mode O,

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AP600 Design Control Document l Table 1-1 (Cont.)

l Index of AP600 Tier 2 Information Requiring NRC approval for Change item Expiration at Tier 2 First Full Power Reference Passive residual heat removal heat exchanger natural First Plant Only 14.2.10.3.7 circulation test l First-Plant-Only and nree-Plant-Only Tests As Discussed 14.4.6 WCAP-14396, " Man-In-He Loop Test Plan Description", No Chapter 18 Rev 2 Table 1.6-1 WCAP-14401, " Programmatic Level Description of the No Chapter 18 AP600 Human Factors Verification and Validation Plan". Table 1.6-1 Rev 3 WCAP-14651, " Integration of Human Reliability Analysis No Chapter 18 with Human Factors Engineering Design Implementation Table 1.6-1 Plan". Rev 2 WCAP-14695, " Description of the Westinghouse Operator No Chapter 18 O Decision Making Model and Function Based Task Analysis Methodology", Rev 0 Table 1.6-1 WCAP-14701, " Methodology & Results of Defining No Chapter 18 Evaluation Issues for the AP600 Human System Interface Table 1.6-1 Design Test Program", Rev 1 WCAP-14822, "AP600 Quality Assurance Procuiures No Chapter 18 Supporting NRC review of AP600 SSAR Sections 18.2 and Table 1.6-1 18.8", Rev 0

\ Basis for Human Factors Engineering Program No 18.1 Applicable Facilities No 18.2.1.3 Applicable Human Systems Interfaces No 18.2.1.4 Applicable Plant Personnel No 18.2.1.5 Technical Basis No 18.2.1.6 Regulatory Requirements for HFE No 18.2.2 Responsibility No 18.2.2.1 Composition of HFE Design Team No 18.2.2.3 b

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i AP600 Design Control Document l l Table 1-1 (Cont.) l l Index of AP600 Tier 2 Information Requiring NRC approval for Change Item Expiration at Tier 2 First Full Power Reference General Process and Procedures for Design Review of HFE No 18.2.3.1 Products Human System Interface Design Team Process No Figure 18.2-1 HFE Technical Program and Milestones No 18.2.5 AP600 Task Analysis Implementation Plan No 18.5 Task Analysis Scope No 18.5.1 )

l Task Analysis Implementation Plan No 18.5.2 j Integration of Human Reliability Analysis with HFE No 18.7 Safety Parameter Display System No 18.8.2 Safety Parameter Display System HFE No 18.8.2.5 Mail Control Area Mission and Major Tasks No 18.8.3.2 Remote Shutdown Workstation Mission and Major Tasks No 18.8.3.4 Technical Support Center Mission and Major Tasks No 18.8.3.5 Human System Interface Design Test Program No 18.11 1

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O Design Control Document - Introducson (3/99) Page intro-10

AP600 Design Control Document 1.4 Identification of Agents and Contractors 1.4.1 Applicant - Program Manager 1 Westinghouse Electric Company LLC (Westinghouse), is responsible for the overall design and design certification of the AP600 nuclear power plant.

Westinghouse has designed, developed, and manufactured nuclear facilities since the 1950s, beginning with the world's first large central station nuclear plant (Shippingport), which produced power from 1957.

Westinghouse has designed and delivered more than 100 commercial nuclear power plants with a combined electrical generating capacity in excess of 90,000 MW. The company's manufacturing facilities include the commercial nuclear fuel fabrication facility at Columbia, i South Carolina; and nuclear component manufacturing facilities at Blairsville, Pennsylvania; and Cheswick, Pennsylvania.

Westinghouse has been involved with advanced light water reactor plant design efforts for over five " years. Included is the development of the advanced, passive pressurized water reactor known as the AP600.

Westinghouse has substantial, proven experience, knowledge, and capability to design, manufacture and furnish technical assistance for the installation, startup and service of nuclear power plants.

1.4.2 Other Cottractors and Participants Under the direction of Westinghouse, a number of highly qualified organizations provide design and analysis in support of the AP600 Each has a specific responsibility to Westinghouse as defined by various contracts and agreements. The major contributors are identified in this section.

'Ihroughout the design process, lines of communication have been established among all participants. Design information is generated using common formats, electronic tools and software. Common requirement and compliance documentation has been established and followed. This has allowed design to progress in a complete and consistent manner with interfaces explicitly managed.

1.4.2.1 . Bechtel North American Power Corporation Bechtel North American Power Corporation (Bechtel) is one of the foremost architect-engineering firms in the United States, with the design and construction of 150 nuclear power projects in 25 countries to its credit. In addition to new construction, Bechtel has first-hand Tier 2 Adaterial- inenduodion and General Descr$0lon of PAnnt (3/99) Page 1.4-1

AP600 Design Control Document experience in operating plant retrofit design and construction, as well as maintenance and management.

1.4.2.2 Southern Electric International Southern Electric International (SEI)is a wholly owned subsidiary of The Southern Company.

The Southern Company is comprised of Southem Company Services, Inc. (an engineering technical services company), six operating utility companies, and Southern Electric International (a commercial engineering consulting services company).

Southem Electric Intemational has benefitted from over 99 years of engineering and consulting services experience with the Southern electric utility system to apply to AP600.

This expertise is derived from experience in designing, constructing, operating, maintaining, and modernizing the 251 generating units of the Southem electric system and those of Southern Electric International's clients. Southern Electric International provides a unique perspective and expertise of an operating electric utility.

1.4.2.3 Burns & Roe Company Burns & Roe Company is an architect-engineering firm with considerable nuclear expertise.

Burns & Roe has provided design, construction management and modernization services to a wide variety of domestic and foreign operating utilities. Bums & Roe contributed to the design and installation of a number of commercial nuclear power plants. Burns & Roe has also been involved with the development of advanced light water reactors since their inception.

1.4.2.4 MK.Ferguson Company MK-Ferguson Company is one of the larger construction finns in the world. Their planning and construction management work extends to commercial and industrial projects as well as power generation units. They are a DOE-approved subcontractor on the defense waste processing facility at Savannah River and have worked on such diverse nuclear plant challenges as the replacement of the steam generator at the D.C. Cook Nuclear Plant, decommissioning of the Shippingport Plant and nuclear reactor modifications at Bettis Atomic Power Laboratory.

1.4.2.5 Avondale Industries, Inc.

Avondale Industries, Inc. is the United States pioneer and leader in modular constmetion.

Their modem shipyards prove ideally suited for the modular construction of industnal and commercial facilities. They have the sophisticated infrastructure in engineering, program management, materials and cost control needed to support large, complex projxts.

O Tier 2 Material- Introduchon and General Demiyi;00 B ? Ant (3/99) Page 1.4-2

AP600 Design Control Document D

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1.4.2.6 Chicago Bridge & Iron Services, Inc.

Gogo Brid;,e & Iron Services (CBI) is the leading designer and maker of nuclear reactor containment vessels and liners. They have successfully erected 107 containment structures, 70 percent of all conuinments built in the United States. Chicago Bridge & Iron Services also specializes in operating plant modification and maintenance upgrades; their service expenise includes planning, development, scheduling and implementation of work procedures, ALARA, and deco.a+mdnation.

1.4.2.7 Other Participants Westinghouse has also received support from a variety of engineeering and testing firms on a subcontract basis. The organizations providing important design or testing services include:

SOPREN/ANSALDO of Italy, University of Westem Ontario of Canada, ENEL of Italy, BATAN of Indonesia, ENEA of Italy, BRPT of Indonesia, FIAT of Italy, INITEC of Spain, UNESA of Spain, UTE of Spain, PLN of Indonesia, and Oregon State University.

1.4.3 Combined License Information f

This section has no requirement for additional information to be provided in support of the combined license application.

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Tier 2 Material- Irnrw* w*ws and General DescrQDon of Plant (3/99) Page 1.4-3

AP600 Design Control Document He second category assumes that the operator mispositions the AO and/or MSHIM rod banks in violation of the insertion limits and creates short-term conditions not included in normal operating conditions.

The third category assumes that the operator fails to take action to correct a power distribution limit violation (such as boration/ dilution transient) assuming automatic operation of the rod control system which will maintain constant reactor power.

For each of the above categories, the trip setpoints are designed so as not to exceed fuel I centerline melt criteria as well as fuel mechanical design criteria.

The appropriate hot channel factors qF and F5 for peak local power density and for DNB analysis at full power are based on analyses of possible operating power shapes and are addressed in the technical specifications.

The maximum allowable Fqcan be increased with decreasing power, as shown in the technical specifications. Increasing F5 with decreasing power is permitted by the DNB protection setpoints and allows radial power shape changes with rod insertion to the insertion limits, as described in subsection 4.4.43. The allowance for increased F5 pennitted is ad-dressed in the technical specifications.

This becomes a design basis criterion which is used for establishing acceptable control rod patterns and control bank sequencing. Likewise, fuel loading patterns for each cycle are selected with consideration of this design criterion. De worst values of F5 for possible rod configurations occurring in normal operation are used in verifying that this criterion is met.

The worst values generally occur when the rods are assumed to be at their insertion limits.

Operation with rod positions above the allowed rod insertion limits provides increased margin to the F5 criterion. As discussed in Section 3.2 of WCAP-7912-P-A (Reference 14), it has been determined that the technical specifications limits are met, provided the above conditions are observed. Dese limits are taken as input to the thermal-hydraulic design basis, as described in subsection 4.4.4.3.1.

When a situation is possible in normal operation which could result in local power densities in excess of those assumed as the precondition for a subsequent hypothetical accident, but which would not itself cause fuel failure,' administrative controls and alarms are provided for retuming the core to a safe condition. Dese alarms are described in Chapter 7.

De independence of the various individual uncertainties constituting the uncertainty factor on F nenables the uncertainty (F q") to be calculated by statistically combining the individual uncertainties on the limiting rod. The standard deviation of the resultant distribution of F"n is determined by taking the square root of the sum of the variances of each of the Tier 2 Afaferial- Resciar (3/99) Page 4.3-17 l l

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AP600 Design Control Document O

contributing distributions WCAP-7308-L-P-A (Reference 7). The values for Fj and FE are 1.03 and 1.05, respectively. The value for the rod bow factor, F8,is 1.056, which accounts for the maximum DNB penalty as a function of burnup due to rod bow effects.

43.2.2.7 Experimental Verification of Power Distribution Analysis This subject is discussed it. VCAP-7308-L-P-A (Reference 7) and WCAP-12472-P-A (Reference 4). A summary of these reports and the extension to include the fixed in-core instrumentation system is given below. Power distribution related measurements are incorporated into the evaluation of calculated power distribution information using the in-core instrumentation processing algorithms contained within the online monitoring system. The processing algorithms contained within the online monitoring system are functionally identical to those historically used for the evaluation of power distributions measurements in Westing-house PWRs. Advances in technology allow a complete functionalintegration of reaction rate measurement algorithms and the expected reaction rate predictive capability within the same software package. The predictive software integrated within the online monitoring system supplies accurate, detailed information of current reactor conditions. The historical algorithms are described in detail in WCAP-8498 (Reference 15).

The measured versus calculational cor.parison is performed continuously by the online monitoring system throughout the core life. 'Ihe online monitoring system operability requirements are specified in the technical rpedlications.

In a measurement of the reactor power distribution and the associated thermal margin limiting parameters, with the in-core instrumentation system described in subsections 7.7.1 and 4.4.6, the following uncertainties must be considered:

A. Reproducibility of the measured signal B. Errors in the calculated relationship between detector current and local power generation within the fuel bundle C. Errors in the detector current associated with the depletion of the emitter material, manu-facturing tolerances and measured detector depletion D. Errors due to the inference of power generation some distance from the measurement j thimble.

The appropriate allowance for category A has been accounted for through the imposition of strict manufacturing tolerances for the individual detectors. This approach is accepted industry practice and has been used in PWRs with fixed in-core instrumentation worldwide. Errors in category B above are quantified by calculation and evaluation of critical experiment data on arrays of rods with simulated guide thimbles, control rods, burnable absorbers, etc. These ,

critical experiments provide the quantification of errors of categories A and D above. Errors l O

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v change from plant to plant, are performed for the first plant only. Because of the stan'lardization of the AP600 design, these special tests (designated as first plant only tests) are not required on follow plants. These first plant only tests are identified in.the individual test descriptions. (See subsections 14.2.9 and 14.2.10.) The following is a listing of the first plant only tests, and the corresponding section in which they appear.

First Plant Only Test Section IRWST Heatup Test 14.2.9.1.3 Item (h) l Pressurizer Surge Line Stratification Evaluation 14.2.9.1.7 Item (d)

Reactor Vessel Internals Vibration Testing 14.2.9.1.9 - Prototype Test (Natural Circulation Tests}* 14.2.10.3.6,(14.2.10.3.7}*

Load Follow Demonstration 14.2.10.4.22 Other special tests which further establish a unique phenomenological performance parameter of the AP600 design feamres beyond testing performed for Design Certification and that will not change from plant to plant, are performed for the first three plants. Because of the standardization of the AP600 design, once these special tests have affirmed consistent passive systern function they are not required on follow plants. These tests required on the first three

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plants are identified in the individual test descriptions (See subsection 14.2.9). The following is a listing of the tests required on the first three plants, and the corresponding section in which they appear.

TFirst Three Plant Tests Section Core Makeup Tank Heated Recirculation Tests 14.2.9.1.3 Items (k) and (w)

ADS Blowdown Test 14.2.9.1.3 Item (s)

For subsequent plants, the COL applicant shall either perfonn the subject test, or shall provide ajustification that the results ofthefirst-plant-only tests orfirst-three-plant tests are applicable to the subsequent plant.}*

The justifications for the first-plant-only tests and the first-three-plant tests are provided l below:

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  • NRC staff approval is required prior to implementing a change in this informarion; see DCD Introduction section 3.5.

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AP600 Design ControlDoctanent g

IRWST Heatup Test (14.2.9.13 item (h)) i During preoperational testing of the passive core cooling system, a natural circulation test of the passive residual heat removal (PRHR) heat exchanger is conducted (item f). For the first plant only, thermocouples are placed in the IRWST to observe the thermal profile developed dunng the heatup of the IRWST water during PRHR heat exchanger operation. This test will be useful in confirming the results of the AP600 Design Certification Program PRHR tests with regards to IRWST mixing, and is useful in quantifying the conservatism in the Chapter 15 transient analyses.

Due to the standardization of the AP600, the heatup and thermal stratification characteristics of the IRWST will not vary from plant to plant. The PRHR heat exchanger design, and the size and configuration of the IRWST are standardized, such that the heatup characteristics will not significantly change from plant to plant.

Therefore, since the phenomenon to be tested (i.e., heatup ano mixing characteristics of the IRWST) will not vary significantly from plant to plant due to standardization, a first plant only test of the IRWST heatup characteristics is justified.

Core Makeup Tank Heated Recirculation Tests (14.2.9.13 Items (k) and (w))

During preoperational testing of the passive core cooling system, a test is performed for each plant to verify the CMT inlet piping resistances. In addition, cold draining tests of the CMTs are conducted that verify the discharge piping resistance and proper drain rate of the CMTs for each plant. For the fint three plants, two additional CMT tests are conducted during hot functional testing of the RCS. These tests are a natural circulation heatup of the ChfTs followed by a test to verify the ability of the CMTs to transition from a recirculation mode to a draindown mode while at elevated temperature and pressure.

Operation of the CMTs in their natural circulation mode is conducted on the first three plants only for the following reasons:

Natural circulation of the CMTs will not vary from plant to plant, provided that the other verifications discussed above are performed as specified.

Natural circulation testing of the CMTs was extensively tested as part of the Design Certification Tests.

Performance of this test results in significant thermal transients on Class I components including the CMTs and the direct vessel injection nozzle.s.

ADS Blowdown Test (14.2.9.13 Item (s))

During preoperational testing of the passive core cooling system, the resistance of the cutomatic depressurization system Stage 1,2,3 flowpath(s) is verified. For the first three Tier 2 Material- Initial Test Program (2/99) Page 14.2-8 I

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U 14.4 Combined License pplicant Responsibilities his section describes the Combined License applicant's and holders responsibilities required to perform the AP600 plant initial test program.

14.4.1 Organization and Staffing De specific staff, staff responsibilities, authorities, and personnel qualifications for performing the AP600 initial test program are the responsibility of the Combined License applicant. This test organization is responsible for the planning, executing, and documenting of the plant initial testing and related activities that occur between the completion of plant / system / component construction and commencement of plant commercial operation.

Transfer and retention of experience and knowledge gained during initial testing for the subsequent commercial operation of the plant is an objective of the test program.

14.4.2 Test Specifications and Procedures he Combined License applicant is responsible for providing test specifications and test procedores for the preoperational and startup tests, as identified in subsection 14.2.3, for review by the NRC.

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() 14.4.3 Conduct of Test Program De Combined License applicant is responsible for a r,tartup administration manual (procedure) which contains the administration procedures and requirements that govem the activities associated with the plant initial test program, as identified in subsection 14.2.3.

14.4.4 Review and Evaluation of Test Results he Combined License applicant and holder is responsible for review and evaluation of individual test results. Test exceptions or results which do not meet acceptance criteria are identified to the affected and responsible design organizations, and corrective actions and retests, as required, are performed.

14.4.5 Interface Requirements The combined license applicant is responsible for testing that may be required of structures j and systems which are outside the scope of this design certification. Test Specifications and acceptance criteria are provided by the responsible design organizations as identified in subsection 14.2.3. The interfacing systems to be considered for testing are taken from j Table 1.8-1 and include as a minimum, the following:

= storm drains a site specific seismic sensors e offsite ac power systems f

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. circulating water heat sink

= raw and sanitary water systems e individual equipment associated with the fire brigade e portable personnel monitors and radiation survey instruments e equipment associated with the physical security plan 14.4.6 First Plant-Only and Three-Plant-Only Tests l (The COL applicant or licenseefor thefirst plant and thefirst three plants will perform the l tests listed in subsection 14.2.5. For subsequent plants, the COL applicant or licensee shall l either perform the tests listed in subsection 14.2.5, or shall provide a justfication that the I results of thefirst-plant-only tests orfirst-three-plant tests are applicable to the subsequent l plant.}'

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9 Tier 2 Material- Initial Test Program {3/99) Page 14.4-2

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