ML20128P967

Requests Withholding Equipment Specs from Public Disclosure (Ref 10CFR2.790) Per Encl Affidavit AW-80-53

ML20128P967
Person / Time
Site:	South Texas
Issue date:	07/15/1985
From:	Wieseman R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20128P958	List: ML20128P967 ML20128P972 ML20128P981 ML20128Q008 ML20128Q028 ML20128Q058 ML20128Q072 ML20128Q081 ML20128Q107 NRC-85-3049, Forwards Listed Nonproprietary Documents Requested by NRC During 850517 & 0626 Audits & Application for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790
References
AW-85-040, AW-85-40, NUDOCS 8507260549
Download: ML20128P967 (52)

Text

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Westinghouse Water Reactor ex 355 Pittsburgh Pennsylvania 15230-0355 Electric Corporation Divisions t

July 15, 1985 AW-85-040 4

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20055 APPLICAfl0N FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

Subject:

Iransmittal of Westinghouse Documents Requested by the U.S. NRC at the South Texas Mechanical Engineering Branch Document Audit on May 17,1985, and June 26, 1985

References:

(1) Westinghouse Letter No. NS-NRC-85-3038, Rahe to Denton, dated May 30, 1985.

(2) Westinghouse Letter No. NS-NRC-85-3044, Rahe to Denton, dated July 3, 1985.

Dear Mr. Denton:

1 The application for withholding is submitted by Westinghouse Electric l Corporation (" Westinghouse") pursuant to the provisions of paragraph (b)(1) of

Section 2.790 of the Commission's regulations. It contains commercial i strategic information proprietary to Westinghouse and customarily held in l confidence.

The affidavit previously provided to justify withholding proprietary information in this matter was submitted as AW-80-53 with letter CAW-82-62

[

dated October 20, 1982, and is equally applicable to this material.

Accordingly, it is respectfully requested that the subject information which

, - is proprietary to Westinghouse be withheld from public disclosure in _

accordance with 10CFR Section 2.790 of the Commission's regulations.

8507260549 850715 i PDR ADOCK 05000498

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Mr. Harold R. Denton July 15,1985 AW-85-040 Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW-85-040 and should be addressed to the undersigned.

Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION R. A. Wiesemann, Manager Regulatory & Legislative Affairs

/wh Enclosure cc: E. C. Shomaker, Esq.

Office of the Executive Legal Director, NRC

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AW-85-040 July 15,1985 bec:

E. P. Rahe, Jr. , MNC 4-12 R. G. Saint-Paul, Brussels J. Cobian, Madrid J. M. Moore, PC 3 600 P. J. Docherty, Bethesda

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AW-80-53

!FFIDAVIT 4

COMMONWEALTH OF PENNSYLVANIA:.

ss COUNTY OF ALLEGHENY:

.Be' fore me, the endersigned authority, personally appeared Rotert A. Wiesemann, who, being by me duly sworn according to law,

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i deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the ,1verments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

S @j.bHfNtb:

Robert A. Wiesemann, Manager Regulatory and Legislative Affairs Sworn to and subscribed before me this I d ay

of d d 1980.

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AW-80-53 (1) I am Manager of Regulatory and Legislative Affairs in the Nuclear Technology Division of Westinghouse Electric Corporation, and as such, I have been specifically delegated the function'of reviewing i the proprietary infomation sought to be withheld from 'public dis-closure in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.

l (2) I am making this Affidavit in confomance with the provisions of l

10CFR Section 2.790 of the Comission's regulations and in conjunc-tion with the Westinghouse application for withholding accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized ,

by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privile'6ed or as confidential comercial or ,

financial information. ,

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.;790 of

.the;Comission's regulations, the following is furnished for con- .

sid& ration by the Comission in determining whether the information sought to be withheld from public disclosure should be withheld.

(i) The information sought to be withheld from public dis- -

closure is owned and has been held in confidence by Westinghouse.

(ii) The information is of a type customarily held in confi-dance by Westinghouse and not customarily discl.osed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by i it'and, in that connection, utilizes a system to determine when and whether to hold certain types of information in

AW-80-53 confidence. The application of that system and the sub- ,

stance of that system. constitutes Westinghouse policy and provides the rational basis required.

Under that system, infomation is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantag'e, as follows:

. (a) The information reveals the distinguishing aspects i

ofaprocess(orcomponent, structure, tool, method, etc.)wherepreventionofitsusebyanyofWestinghouse's competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companias.

m (b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method,etc.),theapplicationofwhichdatasecures a competitive economic advantage, e.g., by optimization or improved marketability.

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(c) Its use by a competitor would reduce his expenditure

' of' resources or improve his competitive' position in

- the design, manufacture, shipment, installation, assur-ance of quality, or licensing a similar product. .

(d) It reveals cost or price infomation, production capac- .

ities, budget levels, or consnercial strategies of Westinghouse, its customers or suppliers.

(e) It reveals aspects of past, present, or future Westinghouse

' or customer funded development plans and programs of potential commercial value to Westinghouse.

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, (f) It contains patentable' ideas, for which patent pro-taction may be desirable.

(g) It is not the property of Westinghouse, but'must be treated as proprietary by Westinghouse according to agreements with the owner.-

There are sound policy reasons behind the Westinghouse system which include the following:

l i (a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.

It is, therefore, withheld from disclosure to protect the Westinghouse competitive. position.

(b) ,It is information which is marketable in many ways.

The extent to which such information is.available to competitors diminishes the Westinghouse ahility to l sell products and services involving the use of the information.

(c) Use by our competitor would put Westinghouse at a l

- . competitive disadvantage by reducing his expenditure of resources at our expense. ,

(d) Each component of proprietary informa ion pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary infonna-tion, any one component may be the key to'the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

AW-80-53

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3 (e) Unrestricted disclosure wuld jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the'c,ompetition in those countries.

(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success

, in obtaining and mainta'ining a competitive advantage.

(iii) The information is being transmitted to the Commission in confidence and, undar the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.

(iv) The information sought to be protected is not available in put;lic sources to the best of our knowledge and belief.

(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked SE-SP-40(80)

" Southern California Edison Repair. Report" (Proprietary).

This report has been prepared for arjd is being submitted to theStaffattherequestofSoutherItCaliforniaEdison.

The repo'rt details the design of the sleeves that are to be -

installed in the San Onofre Unit 1 steam generators. The report also includes the design analysis, the test verifica-tion program and descriptions of the expanded mechanical plug, the rolled plug and the channel head decontamination process.

This information is part of that which will' enable Westinghouse 2:

(a) ,

Apply for patent protection.

.o I AW-80-53 i

(b) Optimize steam generator repair techniques to extend the service life of steam generators.

(c) Assist its customers to obtain NRC approval (d) Justify the design basis for the steam generator repairs and installation methods.

Further, this information has substantial commercial value

. as follows:

(a) Westinghouse plans to sell the repair techniques and equipment described in part by the information.

(b) Westinghouse can sell repair services based upon the experience gained and the installation equipment.

and methods developed.

Public disclosure of this information is likely to cause substantial harm to the compititive position of Westinghouse because (1) it would result in the loss of valuable patent

. . rights, and (2) it would enhance the ability of competitors to design, manufacture, verify and sell steam'genarator repair techniques for commercial power reactors without '

comensurate expenses.

Thedevelopmentofthemethodsandequipmentdescribe,i$

l part by the information is the result of applying the results of many years of experience in an intensive Wes.tinghouse effort and the expenditure of a considerable sum of noney.

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AW-80-53

.I In order for competitors of Westinghouse to duplicate this infonnation, similar engineering programs would have to be perfonned and a significant manpower effort, having the requisite talent and experience, would have to be expended for steam generator repair techniques.

Further the deponent sayeth not.

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( 1.2 Optional Equipment Furnished by the Supplier 1.3 Equipment and Services by Others 1.4 Documentation to be Furnished by the Supplier 2.0 APPLICABLE DOCUMENTS 2.1 Referenced Documents Not Attached

( 2.2 Referenced Documents Attached 3.0 DESIGN REQUIREMENTS 3.1 Arrangement 3.2 General Design Requirements 3.3 Operating Requirements 3.4 Mechanical Design Requirements 3.5 Electrical Design Requirements 4.0 MATERIALS OF CONSTRUCTION 5.0 MANUFACTURING REQUIREMENTS i

5.1 Special Requirements 5.2 Cleaning 6.0 QUALITY ASSURANCE 7.0 CLASSIFICATION OF COMPONENTS 8.0 PREPARATION FOR DELIVERY 8.1 Painting 8.2 Packaging and Packing Appendix A - System Design Transients l (. Appendix B - Motor Criteria l

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5.0 MANLTACTURING 5.1 Welding 5.2 Hardsurfacing 5.3 Heat Treatment 5.4 Cleaning 5.5 Marking 6.0 QUALITY ASSURANCE 6.1 Quality System 6.2 Non-destructive Examination 6.3 Production Tests

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7. 0 PREPARATION FOR SHIPMENT 7.1 Identification 7.2 Cleaning and Packaging 7.3 Quality Assurance Data Package APPENDIX A: Valve Specification Data APPENDIX B: Transients APPENDIX C: Design Load Combinations and Requirements APPENDIX D: Accident Environments 9EV1510N NO. E SPEC.

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• Pittsburgh, Pennsylvania 15230 DATED REVISION NO DATED ORIGIN AL ISSUE SUPERSEDES EQUIPMENT SPECIFICATION "* uS 10/20/78 0 R E J,foyS 953385 ATTACHMENTS PROJECT: TGX/THX None Piping Design Specification, ASME III Code Class NOTE: Coninents from the EOulPMENT: I, for Houston Lighting & Power Company - SOUTH TEXAS PROJECT Nuclear Power Plant Units 1 and 2 hIl0("9 y, e c ed and resolved:

SHOeOROEn: 137 Quality Assurance Primary Equipment RCS SYSTEM: Systems Application

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2.0 APPLICABLE DOCUMENTS 2.1 Referenced Westinghouse Documents 2.2 Additional Referenced Documents 3.0 DESIGN REQUIREMENTS AND PARAMETERS 3.1 Design Information '

3.1.1 Design Life '

3.1.2 Radioactivity 3.1.3 Water Chemistry 3.1.4 Mechanical Design

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3.2 Design Pressure, Design Temperature, and Design Mechanical Loads -

l 3.2.1 Design Pressure and Temperature '

3.2.2 Design Mechanical Loads 3.3 Operating Conditions 3.3.1 Nonnal Conditions 3.3.2 Upset Conditions l 3.3.3 Faulted Conditions i

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DESIGi[ SPECIFICATION SHEET WESTINGH*USE ELECTRIC CORPORATION

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EQUIPMENT SPECIFICATION DATED MEVISION NO. DATED ORIGIN AL ISSUE SUPERSEDES G-952744 9/8/78 0 @ u5 O'YSPO~5

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NOTE: Comments from EOulPMENT- Reactor Coolant System Equipment Supports Design the following groups Specification, ASME III Code Class 1 (for Steam he.ve been received and

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5.1.1 Welding 5.1.2 Heat Treatment

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EQUIPMENT SPECIFICA? ION COVER SHEET WESTINGHOUSE ELECTRIC CORPORATION WWESTINGHOUSE PORM S40e4C Nuclear Energy Systems P.O. Bos 365 Pittsburgh,Pennsvivania 15230 EOutPMENT SPECIFICATION DATED REVISION NO. D AT6 D ORIGIN AL ISSUE SUPE RSE DE S 953533 3/2/79 0 x ;Wpoj,u PROaCT. South Texas Project Units 1&2 G-952744 Rev. 0 EQUIPMENT: Reactor Coolant System Equipment Fupports Design NOTE: Consnents from the Specification, ASME III Code Cla.s 1 (for Steam "9 "

Generator, Reactor Coolant Plan 9, Reactor Pressure b c1 d re olved*

Vessel and Pressurizer) Quality Assurance Primary SHOE oRoER: TGX/THX-137 Equipment sv5TEu- RCS Reactor Vessels and Piping Metallurgical and NDE Anal sis sgngngneering This doctsrent is correct and complete and in compliance with the requirements Reactor Coolant and su ticle NA-3250 of ASME Rad at d tems Analysis

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EOulPMENT SPECIFICATION DETAILS WESTINGHOUSE ELECTRIC CORPORATIOf e4%*.*$44474 NUCLE AR ENEMG4 $4s?E*.t5 INDEX 1.0 - 7.0 Same index as }[ Equipment Specification G-952744

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. EQUIPMENT SPECIFICATION COVER SHEET WESTINGHOUSE ELECTRIC CORPORATION west NowousE pone seos4C Nucteer Energy Systems P.O. son 366 Pittsburgh Penneytvenia 15230 4

EOulPME NT SPEC 8 p tCATION DATED REVISION NO. DATED ORIGINAL IStut SUPERSEDES G-952628 6/19/74 1 1/8/75 ] '

."r' Ysfo"Ns 1 ATTACHMENTS W QCS-1 Rev. 6 W PS 597755 EOutPMENT:

PS 595137 PABRICATION REQUIREMENTS POR THE REACTOR COOLANT SYSTEM COMPONENT SUPPORTS W PS 292722 W PS 85310QA W Admin. Spec. W 54823

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U.S. Projects Planning & Scheduling Product Assurance Quality Engineering Purchases & Traffic

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WESTINGHOUSE ELECTRIC CORPORATION EQUIPME NT SPECIFICATION DET AILS NUCLE AH ENERGY SYS1 EMS p;IVt.4647a TABLE OF CONTENTS 1.0 SCOPE 1.1 Equipment and Services to be Furnished by the Seller 1.2 Services to be Supplied by Others 2.0 APPLICABLE DOCUMENTS 2.1 Attached Referenced Documents i 2.2 Referenced Documents Not Attached 3.0 DRAWINGS AND SUBffITTALS TO BE FURNISHED BY THE SELLER 3.1 Drawings 3.2 Procedures and Reports 4.0 MATERIALS 4.1 Acceptable Materials 4.2 Unacceptable Materials 4.3 Fracture Toughness Requirements for Materials 4.4 Welding Materials

. 4.5 Plate Discontinuities 5.0 MANUFACTURING REQUIREMENTS l

5.1 Buyer Release 5.2 Fabrication 5.3 Cleaning 5.4 Marking 5.5 Handling 5.6 Tolerances 6.0 QUALITY ASSURANCE ,

6.1 Seller Quality Control Requirements 6.2 Nondestructive Test Requirements

( 6.3 NDE Personnel Qualification 6.4 Documentation

• 6.5 Buyer's Examination 7.0 PREPARATION FOR SHIPMENT 7.1

• Painting

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SYSTE MS STANDARD APPENDIX A to SSDC 1.3. Revision 2 FLUID SYSTEMS DESIGN TRANSIENTS 3XL AND 4XL PLANTS TABLE OF CONTENTS Page(s)

Part A - Introduction 4 Part B - Description of Changes 6 Section 2.2 (Reactor Coolant System) - Text 7

- Figures 18 Section 2.3 (Pressurizer) - Text 22

- Figures 32 Section 2.4 (Steam Generators) - Text 34

- Figures 35 Branch Connections, Auxiliary Systems and Related 39 (RCS nozzles, CVCS, RHRS and SIS)

• Part C - Replacement Pages 46 Table 2.2-1 RCS Steady State Operating Conditions 47 2.5 Pressurizer Relief and Safety Valve Inlet Lines 48 2.6 RTD Manifold and Piping 50 Figures for Section 2.2 51-69 Figures for Section 2.3 70-81 Figures for section 2.4 82-107 a

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SYSTEMS STANoA Ao TABLE OF CONTENTS (CONT'D)

Page(s) 2.8 Reactor Coolant Piping Branch Connections 108 Table 2.8-1 12-Inch Accumulator Line and 110 Related Piping 2.8.1 Charging Nozzle 111 2.8.2 Accumulator Nozzle 119 2.8.3 Boron Injection Nozzle 122 2.8.4 RTD Manifold Return Nozzle 122 2.8.5 Letdown Line 123 2.8.6 Excess Letdown Line 123 2.8.7 RHR Pump Suction Lines 124 2.8.8 Seal Water Injection Lines 124 2.8.9 Auxiliary Spray Piping 125 Table 2.8-2 Reactor Coolant Piping Brance

128-129 Connections

. Figures for Section 2.8 130-140 Section 3 - Chemical and Volume Control System 141 2

3.1 Regenerative Heat Exchanger 141 3.2 Letdown Heat Exchanger 148 i 3.3 Letdown Reheat Heat Exchanger 154 3.4 Excess Letdown Heat Exchanger 158 3.5 Charging Pumps 160 Figures for Section 3 161-184 5.3 Safety Injection Pumps 185 Section 7 - Emergency Boration System 186 7.1 Baron Injection Tank 186 7.2 Boron Injection Pumps 190 7.3 Boron Injection Nozzle 191 Figures for Section 7 192-194

• tifINCH0Ulf ELECTRIC CORPO4 A floN NUCLE AM INERQy SYstgus 0 '

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PART A INTRODUCTION 4 ) I 1 This appendix provides fluid systems design transients information applicable to the 3XL and 4XL model plants. It is intended for use with the basic tran-sient document, SSDC 1.3,* and contains material which supplements, corrects.

g replaces or otherwise modifies information contained in SSDC 1.3. g 1

The need for this additional transients information is pointed up by several basic differences between the 3XL and 4XL plants and the 312 and 412 models addressed in SSDC 1.3, Rev. 2. These include

1) Higher pcmer levela

, 2) "E" model steam generators instead of "D"

I

3) Three train Safety Injection System

4) Separate Emergency Boration System

5) 250 spa letdown system (CVCS) ,

)

6) "S team Subble" heatup and cooldown.

l s

It should be noted that there are many portions of SSDC 1.3 Rev. 2 considered '

directly applicable to 3XL, 4XL design work without modification.

The transients described by these portions contain aufficient but not excessive conservatism; this conclusion is based on experience gained from the application of SSDC 13 .

) Rev. 2 to numerous component design and fatigue evaluation processes.

Unless indicated by information presented here in Appendix A (or in some other valid document), it should be assumed that the design tras.sients in SSDC 1.3 Rev. 2 cre applicable to 3XL and 4XL plants without change.

4 CSystems Standard Design Criteria, Nuclear Steam Supply System . Design Transients,

! Revision 2, dated April 15, 1974. t i

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Appendix A presents replacement 3XL, 4XL design transients information, by written descriptions of the appropriate changes (Part 5) and/or by new and replacement pages (Part C).

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I VSTEhe$ STA4oAeo PART B DESCRIPTION OF CHANCES I

In this part the modifications required to the SSDC 1.3 Rev. 2 transients information are described. The information which follows is identified with the same section and figure numbering system used in the basic document, and "

in most cases with page numbers. By means of this information and the new and replacement figures in Part C, a copy of SSDC 1.3 Rev. 2 can quickly be converted to a transients document applicable to 3XL and 4XL plants.

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NUCLEAR STEAM SUPPLY SYSTEM C' MSIGN TRANSIENTS q .

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TABLE OF CONTENTS

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Section Title

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1 Introduction 7 2 Reactor Coolant System Transiente >

2.1 Definitions and Organisation 9 2.1.1 Definitione of ASME and AN81 Classifications I 2.1.2 Definitions of Plant Operating Conditions 12 2.1.3 organisation 12 2.2 Reactor Coolant System (Primary System) 21 2.2.1 Normal Conditione 23 2.2.2 Upset conditions

( 2.2.3 Energency Conditions 31

• }

2.2.4 Faulted Conditiese '/

2.2.5 Test conditione 43 2.2.6 Figures for Section 2.2 (Reactor Coolant System) 47 2.3 Pressuriser Vessel -

91 2.3.1 Normel Conditione 94 2'.3.2 Upset Conditions 104 2.3.3 thersency conditions .

Ils I 2.3.4 Faulted Conditions ita V 2.3.5 Test conditions I 1

2.3.6 Susanary of Design Tranatente -

Pressuriser Vessel 131 g 2.3.7 Figures for Section 2.3 (Pressuriser Vessel) J' 2.4 Stone Generatore 1s4

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2.4.1 Primary'81de 172 2.4.2 Secondary Side 172

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2.4.3 Hydrostatic and Leakage Teste 1**

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SYSTEM 1r5 FANDARD k s TABLE OF CONTENTS (Cont.) .

v Section Title Page w

2 Reactor Coolant System Transiente (Cont.)

2.5 Pressuriser Relief and Safety Valve Inlet Lines 217 2.6 RTD Manifold and Piping 219 2.7 Loop Isolation Valves 221

,2.7.1 Valves Open 221 2.7.2 Valves closed 221 2.7.3 Mydrostatic and Leakage Testa 223

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2.7.4 Bypass Line 224 2.8 Raattor Coolant Piping Branch Connections " '

% 225 2.8.1 Charging Line Nossla 230 2.8.2 Accumulator Mossle 238 Z.8.3 Residual Heat Removal Systen Return Nossle 238 2.8.4 Low Head Safety injection Nossle 239 2.8.5 Migh Head Safety Injection Mossla 239 2.8.6 Boron Injection Nossla 240

(- 2.8.7 RfD Manifold Return Mossle 240

. 2.8.8 Fressuriser Surge Line Nossle 241 v 2.8.9 Susenary of Des 18n Transients -

Raaetor Coolant Piping Branch Connections 243 I( 3 Chemical and Volume control system 253 253 1.1 Regenerative Heat Eachanger Letdown Heat Enchanger 261 3.2 Letdown Reheat Heat Enshanger 267 l l 3.J l 3.4 T.xcese Letdown liest Rachanger 273 q * ,

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Page Section Title g 273 3 3.S Seal Water Nest Emahanger v 277 >

3.6 Charging Pu.pe Seeldual Neat memoval System 291 4

4.1 Reeldual Neat tachanger 291 4.2 Reefdual Nest nameval P ope 292 293 S Safety Injection System Beren Injection fenk 29)

Sei 297 S.2 Accumulatore 301 S.3 Safety Injection Pumpe 303 6 Seaflies System .,

303 6.1 Sample West Rachenser l

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SECTION 1 INTRODUCTION -

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This document presents a brief descri tetton and numery of the type and number of plant operational transients which should be sensidered in '

analysing and evaluating the designs of the major seaponents which comprise the NS$8. The document serves as a standard referenco on the subject of fluid systems design transients as they relate to system' design and equipment specifications.

f l To provide the necessary high degree of integrity for the equipment in the NSss, the tr. instant conditions selected for equipeant design evaluation are based on senservative estiastes of the magnitude and

. . ' frequency of the temperature and pressure transients resulting from various operating senditions in the plant. (This desument describes l l fluid system pressure, temperature and flew transiente only. It does  !

not cover the mechanical leadings on any component.) To a large entent, I the specific transient operating sendittene sensidered for design l

purposes are based upon engineering judgment and espersenes.  !

The transients selected are representative of operating conditions I which prudently are considered to occur during plant operation and that ure sufficiently severe er frequent to be of possible signifiaance to l component cyclic behavier. The transients selected may not always be

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completely accurate predictions of plant operations. They should

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i instead be regarded se a seneervative representation of transients {

ubich, when used se bases for aceponent fatigue evaluation, provide i L i

Q confidence that the'aempenent is appropriate for its appliestion

! over the design life of the plant.  ;

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'flie transients included in this document confoss with the ANSI document,

" Nuclear Safety Criteria for the Design of Stationary Pressurised Water Meactor Plants." ANSI N18.2. August 1973. Plant operating canditions which i

are listed in the ANS Criteria and which produce any significant. fluid

• systems transients are treated in this document. Most of these occur-  !

rences are described,directly while certain others of the same nature but which are less severe are covered under an "unbrella" by using the  !

,' most severe transient. ,

w For purposes of equipment evaluation, the number of transient occur-rences is based on a plant design life of 40 years. For plants having ,

' I

' a design life other than 40 years, the effects of the different number of transient cyclen'upon component fatigue analysis must be considered. j a .

i Again it should be noted that the transients described in this document t are based on conservative assumptions and are meant primarily for use in component stress analyses and de not necessarily represent actual l

- plant operation. Since this is a general document its applicability )

% must be reviewed for any specific plant.  ;

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SECTION 2 REACTOR COOL. ANT SYSTEM TRAN5IENTS

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2.1 DEFINITIONS AND OgCANIZATION d( 2.1.1 Definitions of ARME and ANSI cimanificatinam The conditione considered for selecting the operational tranatente are broken down into the following categories:

Operating Conditione Conditions for Design ASMA: !!! ANSI N13.2 Normal Conditione Condition 18 Normal Operation Upset Conditione

( Condition 118 Incidente of Moderate Frequency

, Emergency Conditions Candition !!! Infrequent Incidente Faulted Conditione Condition IV Limiting Faulte Testing Conditione ---

2.1.1-1 ASME Definittone The above Operating Condittene are defined in the A8ME So11er and Preneure Vessel Code for the design of Class 1 sosponente (AINE

( Section 111, July 1971 edition with Adlenda through Winter 1973,

.. paranraphe NS-3113 and MS-3114). These definitione are quoted belowl i Normal conditions Normal senditione are any sendition in the courov

( ul mystem startup, o,peration in the design power range, hot standby

% and system shutdown, other than Upset. Amargeney, Faulted er Testing

(.onditione.

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• Useet Conditione (Incidente of Moderate Freauency) Amy deviations fres Normal Conditions anticipated to occur eften enough that design should

( include a capability to withetend the esadittens without operational impettment. The Upeet Conditiene include these transients which result .,

" free any single operator error er centrol malfunetten, tranatente caused by a fault in a system component requiring its toelation free the syntes

( and transiente due te lose of lead or power. Upeet Ceedittene include any abnorme1 incidente not resulting in a forced outage and also forced

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outages for which the serrective estion does met include any repair of mechanical damage. The estimated duration of an Upeet Condition ohell be included in the Desten Specifications.

i peraency Conditione (Inf reeuent incidente) These deviatione free l l Normal Conditions which require shutdown for serrection of the son-  ;

dittene er repair of damage in the systen. The sendittees have a low probability of escurrence but are included to provide soeurente that ne grees less of structural integrity will result se a een- s w coattent effect of any danese developed in the eyeten. The total f

number of postulated occurrences for eveh evente shall not seuse me e than 2$ etrees eyelee having en 8,value greater than that for 10 cycles free the appliesble fatigue design surves of Figures !=9.0.

Duf te4 tonditione ILimitina faultet Theee sembinettene of eendittens desoststed willi entramely-low-pron. ability, postulated events wheoe ten-( sequences are such that the integrity and operability of the nuclear J

e nergy system may be tapetred to llis setent that eensideration of w publit heeltle and estety are involved. Sush sonalderetiene require tiepliants with eefety eriterte se any be specified by juriediettenel I authorities.

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Testina conditions ,* Testing conditions are those pressure overload tests including hydrostatic testa, pneumatic tests, and leak tests specified.

Other types of testf shall be classified under one of the categories .

( r,1ven in NS-3113. *

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2.1.1-2 ANSI Definitions in general there is almost direct correlation between the ASME

((_ definitions and the ANSI definitions. The " Conditions for Design" .4s s defined in ANSI N18.2, August 6,1973 are as follows:

Condition 11 Normal Operati_o_n, n ,

Condition 1 occurrences are operations that are expected frequently or regularly in the course of power operation, refueling, maintenance, or maneuvering of the plant.

Condition !!! Incidents of Moderate Freauency Condition !! occurr aces include incidents, any one of which may occ.r

y. during a calendar year for a particular plant.

Condition !!!l Infrequent Incidenen '

Condition !!! occurrences include incidents, any one of which may occur during the lifetins of a particular plant.

_ Condition IV 1.imiting Faulta  !

Condition IV occurrences .

are faults that are not espected to occur, but arv postulated because their consequences would include the potential for the release of alanificant amounts of radioactive material. Condition IV faults are the meet drastic which must be designed assinet, and thus represent tne limiting dealen case.

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J' 2.1.2 Definitione of Flant Operating Canditions a The operating conditione defined below are referred to throughout thie ~

, document. .t1

• -i Mot Shutdown The plant is in the het shutdown condition when the control d

rede are inserted into the core end the seaster is sub-aritical and not a

producing power. For design purposes the Raaster Coolant System is seneidered to be at normal operating pressure and at ne lead het 18) # -

and cold les temperature, i.e., both at S$7'F. The steam generator secondary side is stee assuesd to be at SS7'F and in thermal equilibrium with the primary eyetes.

L Ms Land At no lead sendittene the reseter le subaritical, but with less shutdown margin than at het shutdown, in anticipation j et returning to power. For decian purposes the pressure and ten-  !

] perature values are, assumed to be the same as at het shutdown.

cold shutdown With the plant in the sold shutdown eenditten, it ,

(in f J is assumed for design perpeees that the gepeter Coelant Systea ,,

1 le depressurised and at a uniform teoperature between 70*F 'and f f

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2.1.3 Ormanisation ) l The trenaiente considered under Section 2 are in reopense to the ASME I

and ANS Criteria for Normal Upset, hersoney, Faulted and Test Cen* t  !

I dit tene diosussed in Section 2.1.1. In general,.these transiente are ,- ,

ele l applicable to more than one scoponent er syetas, e.g., the Lees of Lead * =

transient of f acts the Reacter Coelant System (Primary Systen), the I >

pressuriser vessel and the steam generater setendary side. Therefore, ,

l Hection 2 is divided inte subsectione dealing with the following major l arveel .

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, 2.2 hometer Coelant 8/ stem (Primary System) ,

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