ML19343D586
| ML19343D586 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System, Satsop |
| Issue date: | 12/01/1980 |
| From: | Abbott R WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML19343D585 | List: |
| References | |
| WPPSS-0025, WPPSS-0025-R02, WPPSS-25, WPPSS-25-R2, NUDOCS 8105050391 | |
| Download: ML19343D586 (180) | |
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, g- ' Document No.: WPP55-0025 -
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> SUPPLY SYSTEM EQUIPMENT t E. QUALIFICATION PROGRAM FOR E , l
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- CLASS 1E INSTRUMENTATION AND' ,.
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WNP-1/4 AND 3/5 PROJECTS- , J s
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Washington Public Power Supply System l 3000 George Washington Way !
, Richland, Washington 99352 !
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') J 3 > ENGINEERING REPORT 3 QUALIFICATION PROGRAM FOR CLASS 1E INSTRUMENTATION
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AND ELECTRICAL EQUIPMENT FOR WNP-1/4 AND WNP-3/5 , J, 3 COPY NUMBER 6 & I J
- PREPARED BY: [ / [[ [ //-/-80 R. L. Abbott, Corporati Engineering D APPROVED BY: N /IA d Anennrate Engineering N . -. urter, WNP-1/4 3 %d .
E. Werle, WNP-3/5 v.
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DISTRIBUTION: COPY NUMBER: 001 N.S. Porter, WNP-1/4 002 A.G. Hosler, WNP-1/4 003 J.E. Werle, WNP-3/5
- , 004 K.W. Cook, WNP-3/5
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005 J.E. Rhoads, Corporate Engineering 006 A.N. Joshi, Corporate Engineering 007 R.L. Abbott, Corporate Engineering 008 Y. Mani, UE&C , 009 M. Sharma, UE&C 1 010 R.B. Rock, UE&C
-J 011 D.L. Quamme, Ebasco , 01 2 M. Yates, Ebasco 013 L.B. Tiscione, Ebasco 01 4 E.G. Ward, Babcock & Wilcox 01 5 A.A. Tuzes, Combustion Engineering 01 6 C.F. Miller, Consultant 4D 017 018 01 9 020 0
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ABSTRACT Qualification of Class IE equipment for WPPSS WNP-1/4 and 3/5 Nuclear Project is a complex process composed of relatively simple steps. These steps consist of: D o Determining which equipment must be qualified o Establishing criteria which qualification programs must meet o Establishing the most effective qualification methods D o Performance of the qualification progrm o Providing adequate documentation to establish qualification o Following up with procedures designed to insure that the ( qualification program is maintained during the operational phase. This report describes the WPPSS Qualification Program and the methods
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used to implement the ,tep mentioned above. It also provides sample program summaries which are used to document equipment qualification. O( O oe g<
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)c i WASHINGTON PUBLIC POWER SUPPLY SYSTEM . EQUIPMENT OUALIFICATION PROGRAM FOR ! CLASS 1E INSTRUMENTATION AND ELECTRICAL EnUIPMENT ) > < TABLE OF CONTENTS SECTION TITLE PAGE f
1.0 INTRODUCTION
1 1.1 Background 1 1.2 Scope 1 ' ] 1.3 Purpose 2 2.0 SUPPLY SYSTEM EQUIPMENT QUALIFICATION PROGRAM REQUIREMENTS 2 2.1 Confomance with Regulatory Guide 1.89 3 3 2.2 Confomance with Regulatory Guide 1.100 3 l 2.3 Confomance with Regulatory Guide 1.40 4 2.4 Confomance with Regulatory Guide 1.63 4 l 2.5 Confomance with Regulatory Guide 1.73 5 ) 2.6 Conformance with Regulatory Guide 1.131 2.7 Confomance with IEEE 101-1972 5 5 2.8 Conformance with IEEE 279-1971 ,5 , 2.9 Confomance with IEEE 387-1977 5 2.10 Confomance with IEEE 501-1978 5 2.11 Conformance with IEEE 535-1979 6
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2.12 Conformance with IEEE 650-1979 6 2.13 Conformance with Regulatory Guide 1.70 6 2.14 Confomance with SRP, Section 3.10 6 3 2.15 Conformance with SRP, Section 3.11 6 2.16 Conformance with General Design Criteria 6 2.17 Conformance with IE Circular 78-08 7 2.18 Conformance with IE Bulletin 79-01 7
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2.19 Conformance with NUREG-0588 7 2.19.1 Part I 8 2.19.2 Part II 8 l ! 2.19.3 Part III 9 j( ' Dv , _ _ . - . -- - . . - - -- -
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SECTION TITLE PAGE 3.0 CLASS 1E EQUIPMENT TYPES AND SERVICE CONDITIONS 11 , 11 3.1 Equipment Types 11 3.2 Service Conditions 3.2.1 Environmental Service Conditions 11 3.2.1.1 WNP-1/4 Environmental 11 e Service Conditions 3.2.1.2 nNP-3/5 Environmental 38 Service Conditions
?.2.2 Seismic Conditions 41 3.3 Class 1E Electrical /I&C Equipment Acceptance 41 9 Criteria 4I 3.3.1 Content 3.3.1.1 Equipment Description 42 1 3.3.1.2 Aging Simulation 42 3.3.1.3 Service Conditions 42 3.3.1.4 Test Sequence 42 3.3.2 Technical Adequacy 42 4.0 QUALIFICATION PROGRAM METHODOLOGY 44 g 4.1 General Oualification Methods 44 4.1.1 Qualificacion by Type Testing 45 4.1.1.1 Test Plan 4.1.2 Op. rating Experience 45
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4.1.2 Ongoing Oualification 47 4.1.4 Combined Oualification 47 4.2 Design Conditions 48 4.2.1 Aging 48 4.2.1.1 Aging Oualification by 48
- Testing 4.2.2 Radiation 50 4.2.3 Seismic Conditions 50 4.2.3.1 Seismic Oualification 50 g Using Combined Analysis &
Testing 4.2.3.2 Testing 51 4.2.4 Operational Simulation During A DBE 52 4.3 Qualification Methods Application 52 9 , 9
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g ' r SECTION TITL$ PAGE J 5.0 EOUIPMENT QUALIFICATION PROGRAM IMPLEMENTATION 52 ( AND DOCUMENTATION 5.1 Supply System Equipment Qualification Program 53 5.1.1 Design Phase 53 3 5.1.2 Specification Phase 54 5.1.3 Bid Evaluation Phase 55 5.1.4 Procurement Phase 55 5.1.5 Operations Phase 55 5.1.5.1 Maintenance of Qualified Life 55 3 5.1.5.2 Extension of Qualified Life 55 5.1.5.3 Design Modifications 56 5.2 Documentation 56 5.2.1 Vendor Documentation Submittals 56 5.2.2 Documentation Submitted to the U.S. NRC 57 5.2.2.1 Summary Report Infomation 57 5.'2.2.2 Required Licensing Information 57 5.2.2.3 Class IE I&C/ Electrical 57 3 Eouipment List 5.2.3 File System 57 "
6.0 CONCLUSION
58 Figures 1 STANDARD QUESTION REQUIREMENTS (Appendix E, NUREG-0588) 10 3.2.1-1 CONTAINMENT PRESSURE DURING LOCA, MSLB 3.2.1-2 CONTAINMENT TEMPERATURE DURING LOCA, MSLB D( Tables 3.11.1-1 WNP-1/4 WNP-3/5 3 3.11.1-2 WNP-1/4 Aopendices A Sample Summary Reports 9x B WNP-1/4 I&C/ Electrical Equipment List C Acceptance Criteria Qo I
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1.0 INTRODUCTION
This section presents the background, bases and objectives for gC the Supply System Equipment Qualification Program to satisfy the requirements of IEEE 323-1974, or its daughter standards that are supported by regulatory guides and/or U.S. NRC documenta-tion. This information repert is applicable to Supply System Nuclear Project Nos.1 and 4 (WNP-1/4) and Supply System Nuclear Project Nos. 2 and 5 (WNP-3/5), Docket Nos. 50-460, 513, 508, )' and 509. The sections in this report are identified as follows. Section 2.0 describes the fundamental requirements utilized by the Supply System in the equipment qualification program. Section 3.0 identifies the types of Class IE equipment to be qualified, and the ]< plant specific service conditions under which this equipment must perform. Section 4.0 describes the qualification methods used to de ,nstrate the required equioment safety function. Section 5.0 describes the program implementation and necessary documentation Section 6.0 presents the information report conclusions. D, 1.1 Background On January 16, 1979, Supply System representatives met with the NRC staff to present the Supply System equipment qualification progran and the schedule for qualification of Class IE electrical and I&C equipment on WNP-1/4 and 3/5 projects. In that meeting, the Supply System stated that they would submit an infortnation report describing 3 the methodology for qualification of I&C/ electrical equipment on WNP-1/4 and 3/5 projects. This report would also provide a sample Class IE equipment list and summaries of equipment qualification programs for various types of equipment. The staff agreed, in this meeting, to review the report and provide comments on the technical content and fonnat of information contained within. Any comments O generated as a result of a review of the reoort would then be resolved at that time. 1.2 Scoce The qualification requirements, methodolt y and documentation described O' in this report apply to balance-of-plant Class 1E equipment for the WNP-1/4 and WNF-3/5 projects. Although this report uses methods employed by the NSSS vendors, the report does not include the Class 1E equipment supplied by Babcock & Wilcox for WNP-1/4 or Combustion Engineering for WNP-3/5. D' The NSSS equipment qualification program for WNP-l/4 is described in Babcock & Wilcox' Topical report, BAW-10082. T'his topical report will contain equipment qualification reports as appendices, which the Supply System intends to reference for the qualification of the NSSS and B0P equipment for WNP-1/4. 9' The qualification of NSSS equipF.nt for WNP-3/5 will be based upon individual equipment qualification reports supplied by Combustion Engineering. The Supply System intends to reference these qualifica-tion reports for NSSS and BOP equipment on WNP-3/5. go O 1.3 Purcose The purpose of this information report is to describe the , requirements, identify the equipment to be qualified, and present , the methodology to be used in the Supply System equipment qualifica-tion program. The intent of the Supply System program is to satisfy the qualifica-tion requirements of IEEE 323-1974, or its daughter standards that are supported by regulatory guides and/or NRC documentation. 8 4 2.0 SUPPLY SYSTEM E0VIPMENT QUALIFICATION PROGRAM RE0VIREMENTS
. is section identifies the qualification requirements to which this information report was developed. The documents listed below, along with the plant specific service conditions of Section 3.0, fom the )
9 bases for the Supply System Equipment Qualification Program. The Supply System program confoms with the objectives of the regulatory guides, standards and other criteria listed below. Regulatory Guides: e R.G. 1.89, Revision 0, "0ualification of Class IE Equipment for Nuclear Power Plants"
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e R.G.1.100, Revision 1, " Seismic Qualification of Electrical Equipment for Nuclear Power Plants" e R.G. 1.40, Revision 0, " Qualification Tests of Continuous-Duty
- Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants" y e R.G. l.63, Revision 1, ' Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants: O e R.G. 1.73, Revision 0, " Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants" e R.G.1.131, Revision 0, " Qualification Tests of Electric Cable, 9 Field Splices and Connections for Light-Water-Cooled Nuclear Power Plants" IEEE Standards:
e IEEE 101-1972, " Guide for the Statistical Analysis of Thermal Life > e' Test Data" e IEEE 279-1971, " Criteria for Protection Systems for Nuclear Power Generating Stations" o IEEE 387-1977, " Standard Criteria for Diesel-Generator Units Applied g as Standby Power Supplies for Nuclear Power Generating Stations" O _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
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e IEEE 650-1979, "IEEE Standard for Qualification of Cliss IE Static Battery Chargers and Inverters for Nuclear e Power Stations", o IEEE 501-1978, "IEEE Standard for Seismic Testing of Relays" e IEEE 535-1979, "IEEE Standard for Qualification of Class 1E Lead Storage Battery Chargers and Inverters for Nuclear Power Generating Stations" 3 FSAR Requirements: e Regulatory Guide 1.70, Revision 3 e Standard Review Plan, Section 3.10 g e Standard Review Plan, Section 3.11 General Design Criteria: o 1, 2, 4 and 23 of Appendix A, 10CFR50 e III and XI of Appendix B,10CFR50 IE Circulars /Sulletins: e IE Circular 78-08, " Environmental Oualification of Safety-Related D Electrical Equipment at Nuclear Power Plants" e IE Bulletin 79-01, " Environmental Qualification of Class IE Equipment" e NUREG-0588, " Interim Staff Position on Environmental Qualification 3 of Safety-Related Electrical Equipment" 2.1 Confomance with Regulatory Guide 1.89 " Qualification of Class 1E Equipment for Nuclear Power Plants" This regulatory guides references IEEE 323-1974. (A basic purpose of g' the Supply System qualification program is to provide compliance with the objectives of NUREG-0588.) The equipment qualification program contained in this document exceeds this position oresented during the PSAR review. The source tem as defined by Regulatory Guide 1.89 and the Interim Staff Position NUREG-0588 is beino applied to detemine the radiation dose levels in specific equipment spaces. These levels, then, will be used in the equipment oualifica-O' tion program. 2.2 Confomance with Regulatory Guide 1.100, " Seismic qualification of Electric Equipment for Nuclear Power Plants" This regulatory guide references IEEE 344-1975. The qualification O' methods and procedures of IEEE 344-1975 are utilized by the Supply System according to equipment type and size. The summaries contained in Appendix A provide details of the Supply System's confomance to this IEEE standard and R.G. 1.100. 3e
O The Supply Systen preferred method of seismic qualification is random, multi-frequency inout testing, simultaneously to the principal vertical and one principal horizontal axis. This g configuration is rotated 90 degrees about the principal vertical axis with the excitation then repeated. Five OBE and one SSE tests are perfomed that envelope the required response spectra for each Supply System nuclear project. Single frequency tests are accepted if one of the following criteria g are satisfied: ' i
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e The characteristics of the seismic input motion indicate that the motion is dominated by one frequency (e.g. , by structural filtering effects). e The anticipated response of the equipment is adequately represented 8 by one mode. e The test input motion has sufficient intensity and duration to excite all modes to the required amplitudes such that the test response spectra will envelope the corresponding resoonse spectra of the individual modes. 3 M 2.3 Confomance with Regulatory Guide 1.40, "0ualification Test of Continuous Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants" This regulatory guide references IEEE 334-1971. The Supply System G also confoms with the 1974 revision of IEEE 334. The qualification procedure of IEEE 334-1974 is used with the parameters contained in the Supply System Technical Specifications to demonstrate adequacy of , aged motor and auxiliary equipment under nomal and postulated DBE conditions. A qualification summary contained in Appendix A illustrates the Supply System methodology in conforming with IEEE 334 and R.G. 1.40. 2.4 Conformance with Regulatory Guide 1.63, Revision 1, " Electric Penetration As:;emblies in Containment Structures for Light-Water C_ poled Nuclear Power Plants" g This regulatory guide references IEEE 317-1976. The Supply System combines the qualification test sequence of this standard with the plant environmental and seismic parameters of the Supoly System Technical Specifications to demonstrate aged penetration assemblies' adequacy to perfom their safety function during nomal and DBE conditions. ' O A qualification summary contained in Appendix A illustrates the l Supply System methodology in complying with Regulatory Guide 1.63 l and IEEE 317-1976. G O
I p 2.5 Conformance with Regulatory Guide 1.73, " Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear j Power Plants" This regulatory guide references IEEE 382-1972. The Supply System confoms with this qualification standard by combining the standard's qualification test sequence with the environmental and seismic para-meters of the Technical Specifications to demonstrate adequacy of 3 aged motor operator and auxiliary equipment under nomal and DBE
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A qualification summary contained in Appendix A illustrates the Supply System methodology in conforming to IEEE 382 and R.G. 1.73. 2.6 Confomance with Regulatory Guide 1.131, " Qualification Tests of
)r Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants" This regulatory guide references IEEE 383-1974. The Supply System confoms with the objectives of Revision 0 of the regulatory guide and the reference IEEE standard.
I( The IEEE 383 qualification test sequence is used with the Supply System Technical Soecification parameters to demonstrate adequacy for Supply System applications. Flame testing of aged cables is based upon the thermal aging procerties of the fire-retardant jacket materials to demonstrate fire resistance capability. Qualification ) sumaries contained in Appendix A illustrate the Supply System methodology in confoming to IEEE 383 and R.G.1.131. 2.7 Conformance with IEEE 101-1972, " Guide for the Statistical Analysis of Thermal Life Test Data" The Supply System employs the methods described in this standard when )! using Arrhenius methodology to address accelerated aging. 2.8 Conformance with IEEE 279-1971, " Criteria for Protection Systems for Nuclear Power Generating Stations" The Supply System Technical Specifications for safety-related equipment ) require confomance to the design basis and functional requirements of IEEE 279. 2.9 Confomance with IEEE 378-1977, " Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating . Stations" )L ,
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The Supply System employs the methods described in the qualification section, Section 5.4, of this standard. 2.10 Confomance with IEEE 501-1978, "IEEE Standard for Seismic Testing of Relays' )s The Supply System employs the fragility test guidelines of IEEE 501 whenever discrete relay qualification is perfomed.
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O 2.11 Conformance with IEEE 535-1979, "IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations" g The Supply System Qualification Program for Class IE batteries employs the type-test methods described in this standard. 2.12 Confomance with IEEE 650-1979, "IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power g Stations" The Suooly System employs the methods of IEEE 650 in the qua'lifica-tion of battery chargers, static inverters, and other safety-related electronic equipment. 2.13 Confomance with Regulatory Guide 1.70, Revision 3, " Standard Format 8 and Content of Safety Analysis Reoorts for Nuclear Power Plants"
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The Supply System conforms with the objectives of Regulatory Guide l.70. Sections 3.10 and 3.11 of this regulatory guide specifically require seismic and environmental qualification of safety-related / equipment. These sections are addressed in Section 2.14 and 2.15 S' of this document. , 2.14 Conformance with the Standard Revie.1 Plan, Section 3.10. " Seismic Qualification of Category I Instrumentation & Electrical Equipment" The Supply System conforms with the objectives of this Standard Review Plan. Appendix B illustrates in detail the methodology
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the Supply System intends to employ to satisfy the seismic criteria . I of the Standard Review Plan, Section 3.10. J 2.15 Confomance with the Standard Review Plan, Section 3.11, " Environmental Design of Mechanical and Electrical Equipment" g The Supply System confoms with the objectives of this Standard Review Plan. The Supply System combines the qualification test sequence of the IEEE qualification standards with the plant environ-mental and seismic parameters of the Technical Specification to demonstrate equipment adequacy to perfom required safety functions , under normal and DBE conditions. Appendix B identifies the methodology used in qualification of each piece of equipment. The qualification summaries in Appendix A provide additional details of the qualification program. The submittal of test results which demonstrate that the equipment meets the worst case environmental conditons (e.g., loss of air #l conditioning) required by Section 3.11.4 will be met by inclusion l of such data in the summaries of those tests / analysis. These will l be referenced in the FSAR to satisfy requirements of Standard FSAR Format Section 3.11.4. 2.16 Conformance with General Design Criteria G The Supply System is in confomance with the objectives of the General Design Criteria 1, 2, 4, and 23 of Appendix A, and III and XI of Appendix B to 10CFR Part 50. This is accomplished through confomance with
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NUREG-0588, IEEE 323-1974, its ancilliary standards, and IEEE 344-1975, as discussed in Section 2.0 of this document. D, 2.17 Conformance with IE Circular 78-08, " Environmental Qualification of Safety-Related Electrical Ecuipment at Nucle?r Power Plants" This circular requires documentation that demonstrates Class IE equipment will function under postulated worst case accident conditions. Specific items were identified in the circular as examples of inadequate e, documentation. These include connectors, penetrations, terminal blocks, limit switches and cable splices. The Supply System interprets the circular to emphasi:e certain soecific items mentioned above. The Supply System Equipment Qualifica-tion Program provides methods for meeting IEC 78-08 by conforming to 3 the objectives of NUREG-0588, described by Section 2.19 of this document. 2.18 Confomance with IE Bulletin 79-01, " Environmental Qualification of Class 1E Ecuipment" g IEB 79-01 re-emphasizes IEC 78-08 and identifies specific unqualified limit switches. The Supply System Equipment Qualification Program provides methods for meeting IEB 79-01 by conforming to the objectives of NUREG-0588, described by Section 2.19 of this document.
- 2.19 Conformance with NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment" The NRC Commissioner's Order, CLI-80-21, establishes NUREG-0588 as the bases for environmental qualification of safety-related equipment.
The Supply System is in the process of comolying with this order. O Review of this NUREG document has been completed at the Supply System. The Supply System and the respective Architectural Engineers have included the NUREG document in the equipment qualification review effort. This review effort provides for equipment vendor contact, which will establish confomance to the objectives of the NUREG doctunent. O E NURIG-0588 has incorporated Standard Question Number 4 as Appendix E. ThetSupply System intends confomance to Accendix E. The categorizing wili be perfomed as indicated below and in Figure 1.
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Appendix E of NUREG-0588, " Standard Question on Environmental Qualification of Class 1E Equipment", consists of several parts. O' Figure 1 represents the Supply System interpretation of the Standard Ouestion. The three major parts represent categories of Class 1E equipment. Within these categories lie subparts requiring detailed infomation dependent on equipment function and location. The major categories are: O' e All Class 1E Equipment (Part I) e Class 1E Equipment Subject to Design Basis Accident Environments (PartII)
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O e Class 1E Equioment Not Subject to Design Basis Accident Environments O 2.19.1 Part I For all Class 1E equipment, the Supply System will provide: e Identification of Equipment
- 1. Type (functional designation)
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- 2. Manufacturer
- 3. Manufacturer's type and model numbers e Qualification Envelope Simulated During Environmental Testing ,
- 1. The duration of the hostile environment and the margin in excess of design requirements. ,
e Methods Used for Environmental Qualification Other Than Type Testing. e Summary of Test Results
- 1. The summary which demonstrates the adequacy of the qualification program.
- 2. Justifications for all ana'yses and assumptions made, i
e Oualification Documents _
- 1. All qualification documents which contain detailed a supporting information including test data will be referenced in the sumary of test results.
2.19.2 Part II All Class IE equipment, which, when subjected to a Design Basis Accident environment must function or not fail, is provided with documentation. For this type of equipment, the Supply System provides the following infonnation: , o Equipment safety function requirements derived from the system safety function. The Supply System also substantiates that components will perfonn their safety function during postulated service conditions. e An environmental envelope as a function of time which 8 includes all extreme parameters, both maximum and minimum values, which are expected to occur during plant shutdown, normal ooeration, abnormal operation, design basis accidents ! (including LOCA and SLB), and post accident conditions. e Time required for the equipment to fulfill its safety function 9 (period of operability). O
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i s l Appendix E of NUREG-0588 requires identification of the system safety function. The Supply System interprets this to mean ) the equioment safety function. The Supply System Technical Specification identifies the equipment safety function required, along with the environmental and seismic service conditions. The equipment is then qualified to satisfy the safety function under postulated service conditions. If any method other than type testing was used for qualifica- ) tion, the method is described in sufficient detail to permit evaluation of its adequacy. The qualification test plan, test setup, test procedures and acceptance criteria for at least one of each type of equipment listed below is provided: Switchgear Motor Control Centers Logic Equ'.pment Cable Valve Operators Motors Diesel Generator Control Sensors Equipment Heaters ) Limit Switches Fans Control Boards Electrical Penetrations Instrument Racks & Panels Terminal Blocks Splices Connectors 2.19.3 Part III Jt For representative safety class equipment not subject to a design basis accident environment, the following infomation is provided: e Equipment safety function requirements derived from the system safety function. The Supply System also substantiates that 3 components will perform their safety function during postulated service conditions. e All environmental envelope as a function <f time which includes all extreme parameters, both maximum and minimum values, expected to occur during plant shutdown, normal operation, abnormal operation, design basis events (excluding LOCA and SLB), and 3( post DBE conditions. ;
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e Time required for the equipment to fulfill its safety function ' (periodofoperability). e The qualification test plan, test setup, test procedures, and 3 acceptance criteria for at least one of each group of representative equipment.
- 1. If any method other than type testing was used for qualification, that method is described in sufficient detail to permit evaluation of its adequacy.
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- 2. The representative equipment for which this data is provided cons ni.s of the list described in Section 2.19.2 Part II: of this document.
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l C)! FIGURE 1 O STANDARD OVESTION REOUIREMENTS (HUREG-0588, APPENDIX F) e PART I All Class 1E Equinment e Eauipment Identification e Oualification Envelone ID e Summary of Test Results e Qualification Documents O
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PART II PART III Class 1E Eouionent Sub.iect to DBE Class IE Equinment Not Sub.iect to Ep Environments DBE Environments e Safety Function e Safety Function
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e Environmental Envelone e Environmental Envelone e Period of Goerability e Period of Onerability e Test Data for One Group e Test Data for One Grouo of Eouioment of Equipment ab O
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1 l Class 1E Eouinment Class 1E Equipment Class IE Eauioment i Recuired to Function Not Required to Not Recuired to gp i ' During DBE Function: Cannot Fail Function: Can Fail Environments 9 O
D l i 3.0 CLASS 1E EQUIPMENT TYPES AND SERVICE CONDITIONS 3 This section addresses the eouipment types which are qualified by the Supply System Equipment Oualification Proqram. The service conditions applicable to WNP-l/4 and WNP-3/5, respectively, are also discussed. In addition, the acceptance criteria used by the Supply Sg tam in the review and evaluation of supplier qualification pr) grams are identified. ) 3.1 Equioment Types The Supply System Ecuionent Oualification Program involves all Class 1 electrical, instrumentation, and control eaufpment not l included in the NSSS scope of supply. The qualification programs g for NSSS equipment are contained in separate documents. 3.2 Service Conditions ! The equipment types are located in diverse areas within the plant. I Because of this, the service conditions affectino the operation of some equipment may be different from those conditions affecting the operation of other equipment. This section discusses service l conditions consisting of environmental (temperature, radiation, ! pressure, chemical and humidity) and vibrational (operational l and seismic) stresres. 3.2.1 Environmental Service Conditions O l Each oroject, due to different geographical locations and sepa' ate l NSSS vendors, has different service conditions. The methods tsed in the development of those conditions (i.e., temperature,t.m ure, radiation, humidity, etc.) will be contained in the respective projects FSARs, Section 3.11. O
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3.2.1.1 WNP-1/4 Environmental Service Conditions
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l e Control and Auxiliary Equipment Rooms This area, designated " Environmental Condition Code B8" in ~ a Table 3.11.1-2, is supplied by a redundant Class 1E, Seismic Category I heating, ventilating, and air conditioning system. This system (HCL) is designed to operate under nonnal and all emeroency modes. During an ESFAS condition, the system
is automatically connected to the acoropriate emergency bus. During loss-of-Offsite-Power, this system is manually loaded (' by the operator under administrative controls. No single 9 . failure of an active component will result in loss of service. l l During normal, abnormal (emergency mode powered by the i emergency bus), and accident conditions, the HCL system provides l heating, cooling, humidity control, static pressure control, , normal filtratioi , and atmosphere clean-up service while O maintaining the area ambient temoerature at nominally 75 F; therefore, no loss of air conditioning is costulated for this space. ht a ___
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The ability of this Class 1E equipment to perform its safety function under the environmental service conditions is demonstrated in the equipment qualification program. e Fuel Handlino Area This area, designated " Environmental Condition Code B3" in Table 3.11.1-2, is supplied by a redundant Class 1E, Seismic Category I heating, ventilating, and air conditioning system. This system (HSF) is designed to operate under normal and ' 9 all emergency modes. No single failure of an active comoonent will result in loss of service. During nomal, abnomal, and accident conditions, the HSF system provides heating, cooling, humidity control, normal filtration, and atmospherfc clean up while maintaining the area ambient at a nominal 80 F. The system is automatically loaded on receipt of an ESFAS e signal and is administrative 1y loaded upon a Loss-Of-Offsite-Power condition by administrative procedures. No loss of air conditioning is postulated for this space. The ability of the Class 1E equipment to perform its safety function under the environmental service conditions is demonstrated in the equipment qualification program. g e Safeguards Area This area, designated " Environmental Condition Code B4" in Table 3.11.1-2, is supplied by a redundant Class IE, Seismic Category I heating, ventilating, and air conditioning system. , This system (HSG) is desianed to operate under normal and all emergency modes. A single failure of an active comoonent will not offset the environmental conditions of the area. 7' Evaporative coolers are provided for cooling, however, the normal supply of chilled water is r.ot postulated to be i available during Loss-Of-Offsite Bower. Du5"98"**er98"cV' if the temperature of the space e.xceeds 130 F, a temperature 8 controller opens the chilled-water valves allowing chilled water supplied from the HSF system to circulate through emergency chilled-water coils located in the HSG air-handling units. This maintains air conditioning to this area and therefore, loss of air conditioning is not postulated for this area. The partial loss of air conditioning will not 9, resgit in extreme temperatures as the maximum condition of 130 F is within the design limits of the equipment and will be of short duration. Accelerated thermal aging of eouipment or components subject to thermal degradation during the quglification program g includes temperatures well above 130 F and establishes the abilityoftheeguipmentorcomponenttosurvivetheabnormal condition of 130 F. The equipment qualification program demonstrates the equipment's ability to perform its safety function under the environmental service conditions. t e
i G e containment This area, designated " Environmental Condition Code A1 , and A2" in Table 3.11.1-2, is supplied by a recirculation system (CFC), a purge system (CPP), and a heating system (HSS). The only parts of these systems designated Class 1E are the hydrogen-pock?.t removal fans and associated instrumentation and con rols. The CFC system, howe.. nas four 100% capacity air-handling 8 units--any one of whiu, can maintain the containment tempera-ture below 135 F. These air-handling units are powered by the emergency buses and are manually loaded by administrative controls upon Loss-Of-Offsite-Power. Durina LOCA conditions, temperature conditions are maintained by containment spray. Loss of air conditioning to the containment is highly unlikely G and therefore, the maximum abnormal condition wfil not result in extreme temperatures and will not exceed 135 F. Class 1E equipment located in containment which mitigate the effects of a LOCA or MSLB events are qualified to these conditions. Other Class 1E equipment required to mitigate D the effects of other events are qualified to the service conditions produced by those events, e Diesel Generator Area Each diesel generator area, designated " Environmental Condition 3 Code B5" in Table 3.11.1-2, is supplied by an independent Class 1E, Seismic Category I heating, ventilat'ng and air conditioning system (HDG). Each of the HDG sys; ems is separate, independent and powered from the emergency power bus of its respective diesel generator. Upon LOOP or ESFAS conditions each HDG system is automatically loaded on to its respective diesel source by the emergency power load sequencer. Each 3 of the HDG ventilation systems has 100% capacity in both nomal and emergency modes, thus the postulated single failure in the HDG does not prevent performance of the redundant diesel systems safety function. The ability of the Class 1E equipment to perfom its safety D function under the environmental service conditions is demon-strated in the equipment oualification program. Accelerated thermal aging of components and equipment susceptible to thermal degradation is performed during the aging portion of the qualification program at substantially higher temperatures and establishes the adequacy of the equipment to survive the D abnomal condition. e Switchgear, Battery and Cable-Soreadino Area This area, designated " Environmental Condition Code B12" in Table 3.11.1-2, is supplied by a redundant Class 1E heating, 9' ventilating, and air conditioning system (HSC) and is designed to operate under normal and all emergency modes. A single failure of an active component will not affect the environmental condition of the area. During an ESFAS condition, the system 1 3 J
CL is automatically loaded on to the emergency buses. i During Loss-Of-Offsite-Power (LOOP), operator action j under administrative control re-establishes the HSC 1 system. Therefore, no loss of air conditioning is #d
!
postulated for this area. The maxi um extreme tempera-ture for the switchgear area is 104 F--with the battery andcable-spreadingareasmaintainedatgmaximumof85F during normal and LOOP conditions and 90 F during ESFAS. The ability of the Class 1E equipment to perform its safety function under the environmental service conditions G is demonstrated in the equipment qualification program. e Electrical Pioing Tunnels This area, designated " Environmental Condition Code B10" in Table 3.11.1-2, is supplied by a redundant Class 1E, e Seismic Category I heating, ventilating, and air conditioning system. This system (HPT) is designed to operate under nomal and all emergency modes. A single failure of an active component will not affect the environmental conditions of the area.
- Evaporative coolers are provided for cooling during normal power conditions; however, during LOOP, the normal supply (
of chilled water is not postulated to be available. Calcula-tionshavebeenperfgrmedthatestablishthemaximumambient conditions to be 130 F with the outside environmental conditions at maximum. This is accomplished through ventilating O the area with outside air. This maintains ventilation to this area and therefore, loss of air conditioning is not postulated. The partial degradation of the system will not d resgit in extreme temperatures as the maximum condition of 130 F is within the design limits of the equipment and will be of short duration. The Class 1E equipment qualifica-tion program demonstrates the ability of this equipment to 8 perform its safety function under the environmental service conditions. o Component Coolina and Makeup Pumo Areas This area, designated " Environmental Condition Code Bil" in e Table 3.11.1-2, is supplied by a redundant Class IE, Seismic Category I heating, ventilating and air conditioning system. This system (HCA) is designed to operate under normal and all emergency modes. Single failure of an active component ( will not affect the environmental conditions of this area. System startup, or the transfer of operation from one train to the other, is accomplished by manual control during normal plant operation or following a LOOP. The system is automatically , loaded on the emergency bus in the event of an ESFAS signal. l The evaporative coolers are not available during Loss-Of-Offsite-Power conditions. Calculations have wen performed , l g l
) thagestablishthemaximumambientconditionstobe 130 F with outside environmental conditions at maximum. j- This is accomplished through . ventilating of the area - with outside air. This maintains air conditioning to this area; therefore, loss of air conditioning is not i postulated. The partial degradation of the system will ' not result in exgreme temperature as the maximum condition of 130 F is within the design limits of the equipment and will be of short duration. Accelerated , ' thermal aging of the equipment and components susceptible to thennal degradation during the qualificatign program includes temperature exposures well above 130 F and establishes the ability of the equipment or comoonent to survive the abnormal condition. ) e Main Steam and Feedwater Isolation Areas l This area, designated " Environmental Condition Code Ol" in Table 3.11.1-2, is supplied by a non-Class IE heating, ventilating, and air conditioning system. The system (HIA) is not vital to the safe operation or shutdown of the } plant. The system has been designed such that failure l of any component will not affect the operation of any
- safety-related system.
l The design basis for qualification of safety-related equipment in this area is a HELS in the main steam lines. 3 In order to mitigate the consequences of this accident, i the main steam-valve actuator and other required control l equipment located in the area of influence are qualified ! to the more limiting environment of the HELB. e Spary-Pond Pumo House Area ) The spray-pond pump house is divided into two separate and identical areas. Each is served by an independent Class IE, Seismic Category I heating, ventilating and air conditioning system (VAB). Each system is separate, independent, and powered from the emergency bus of the pump house it serves. They are automatically loaded on ESFAS conditions. Loss ) of one of the air-handling units will require operation of the redundant spray pumo system. As each HVAC system and pump house constitutes an integral, separate unit, the single failure of any HVAC system component cannot prevent l the safe shutdown of the plant. During a LOOP condition, ! manual restarting of the VAB I, stems ensure continued J environmental control. Dur,ng emergency conditions with
thegpumps running, the peak inside gmbient will not exceed 121 F with a 24-hour average of 108 F maximum. ' FSAR Tables 3.11.1 and 3.11.5 and Figures 3.2.1-1 and 3.2.1-2 are included as reference to provide details of the environ-3 mental conditions 9f WNP-1/4 equipment spaces discussion above.
)
. . . . . -
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In*lNrl hitli '58SMiliefNflii A 1616M BA$'I'S'MClfiiil Requ?Yed Ouration 160rmaI/Abnoma1 of Operation for DBA (3) + feA [lIVla0stiftelAt ' f5 Aft ! SY51[M UtilPHf fli 10CAil0N (1)l ora III M5t B CONDITI0ft SCCTInel REACIOR Cla4ANI Reactor Vessel Containment Continuous Continuous Al 5.3, 5.4 SVs11M insidtirs.ne Wall ,
" " "
5tema Generators Continuous The unaffected 5.G. Is required
* "
Pressurizer Contininnas Not Required " Reactor Coolant Pisups
- Continuous Conditionally " "
Required
"
RC5 Piping Continuuusly Continuously "
- Required (5) Required gq .
5 Instrumentation & Controls Inside Containment Short Term 51. ort Tem ? Outside Containment Long Ters p) Long Termpg g i stC Puit ttator outside Containment Short Duration Conditionally B, D-2 8.3 3 , flonttoiing Cabinets Required = ' I LONIAltittNi HfAI ilDtHVAL SVslLMS: Spray Additive Tank
- Short Term bI loot Required B4 6.2.2, 2 fductors 6.5.2 i Ne SPRAY * "
5 pray Pieq>s & Drivers Continuous Continuous "
"
- 5 pray lleat Exchangers Re-Cir Male Re-Cir Mode *
- Valves & Pipir>J Continuous Continuous " "
, Spray Nozzles M.inifolds & Inside Contalemient Continuous Continuous A2 " Pipinq Outside Crane Wall
* "
, Imergency Supps Continuous Continuous *
; Inserisuentation & Controls Inside Containment Continuous Continuous A2, B4
- Outside Contatsument (Fission Product removal portion is nut required
, forit5tB)
i ! n 9 It ,!
e 1A8t! 3.11.1-1
.
{5 Feet 2oTB] Required Duration Nosmal/ Abnormal of Operation for DBA (3) DBA LNVIROIM PIAL ISAR CON 0lil0N SCCi topt 10CA110N III SVS11M EQUIPMENT (1)t0CA M5t B Valves & Piping Inside Ccntairment & Continuous Not Required A2. 84 6.2.4 CONTAINMENI 150tA110N SW1Ett Outside Containment
* * " * "
- Piping Penetrations
* * * * *
- instrumentations & Controls CateUSIIBtE 6A5 6.2.5 CONTR0t $154tHS
- See Contaltunent Heat Removal System (a) Contalru ent Spray 5> stem Hydrugen pocket inside Contelnment Continuous Not Required Al
- k (b) Contaise.cnt Recircuiation Ventilation fans & drives inside Crane Wall a
, " * * *
- S (c) Containment Hydrogen monitors m Q Ainsosph.re e
Honitorin9 System h
" * * * *
(d) Hydrogen Control Hydrogen recombiner System Units *
* *
(e) Contalem.ent Purge Purge fans & drivers
" Not Regaired LMEN4 NCY Ct,HE COOLING 6.3 SYSilH
- Cose flood lanks Inside Containment Continuous Continuous Al (a) t~ ore f l..oding System Piping & Valves InstJe Crane Wall Instrumentations &
Conteols
"
Outside Containment Continuous Continuous Cl (b) Saf ety injection BW51 Systems (LPI # HPI) *
* *
- B4, gli Pumps & drivers
"
Heat exchange'rs
- Re-ctr mode Re-cir mode 54 ,
- Valves & piping Inside & Outside Continuous Continuous AI, A2. 84 Contalement
.
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^ _ _ _ _
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I Adl E 3.11.1-1 i lSheet3'oM Required Duration NormaI/Abnormai of Operation for l*A (3) 08A ENVENONPENTAL f5AR SYS11H EQUIPMENT LOCAlI0tl (1)t0CA (2)gg CON 0lif0N SECTION Inside & Outside Continuous Continuous A2. 84 6.3 Instrumentations & Controls Containment
=
Sumps 8 screens Inside Contalrunent Continuous Continuous A2 Outside Crane Wall 6.5 FISSION PR0adC1 REMOVAt & CONIROL SY51E MS: see Contalemm nt Heat Removal System 6.5.2 (a) Containw.ent Spray Sistem Contaireent Continuous Continuous Al A2 6.5.3.1 (b) Contalrusent Containment Structures System g ON511E POWLs 5f511M5 8.3 k= , Outside Containment Continuous Continuous 81 8.3.1 3 (a) A-C Pom r 4160 vol't Distribution U System buses & switchgears *
" *
- 120 V a-c vital I&C Outside Contalement power system "
" "
Outside Contalement 85 Diesel Generators
& associated equipments
" "
Electrical Cables All areas
"
A. 8. . C. D. E
" " =
inside & Outside A2 Electrical Penetrations Contaliument Battery chargers, distribution Outside Contairement
*
- BI 8.3.2 (b) D-C Pom.r System switchgear & panels "
= " "
"
Batteries *
- Electrical cables All areas
- A.B.C.D.E
* *
- Inside & Outside A2 Llectrical penetratlons Contalraent
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188tE 3.11.1-1 (5heet5or1T Required Duration INmnal/ Abnormal of Operation for lea (3) ENVip0NMENTAL FSAR DBA CONDill0N 5(C110N 10CA110N (llg (?),g3gg SYS11M [QUIPHfNI AIR C00eolltf4.lHG HEAllhG. C06aING & VENillA110N SYSittts 9.4.1 Continuous 88 Air Conditioning Outside Containment Continuous (a) Control s Aux. Equip. L a System & associated of GS8 equipments 83 9.4.2 Continuous Continuous Air Conditioning & Outside Containment (b) Fuel Hautling As ea Sy:, tem atmosphere cleanup os G58 systems & associated equipments 9.4.5 E Continuous Continuous 84 Air Conditioning Outside Containment f (c) Safeguaits Area q of GS8 system & associated g
,
,
equipments Inside Contalssent Contint.ous Continuous AI. A2 9.4.6 ( g t (d) Contalru. nt fans & drivers " " " m
" "
Purge $; stem Inst A crane tsall Air duct work & dampers " " " " " Instrumentation & Inside Containment Controls Continuous 85 9.4.8 outside Containment Continuous Ventilation System (e) Diesel (enerator & associated equipments Area of G5B Continuous 512 9.4.9 Outside Containment Continuous Air Conditioning (f) Suitchg.ar. Batter) & Cable- System & associated , spreadt..g Area of equipments 658 Continuous 810 9.4.12 Outside Containment Continuous (g) Electri.al & Air Conditioning System Piping lunnels cf & associated equipments * * *
*
(.58
- Atmosphere Cleanup System
' & associated equipments Continuous 811 9.4.13 Outside Contalsment Continuous (h) temponuet Coeling Air Conditio'ning &
& Aux. Pug Room atmosphere cleanup systems Area of G5B & associated equipments .
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l O O O O l ,. _ _ 1 Ast r 3.11.1-1 s (Sheet 7of81 Required Duration Normal / Abnormal of Operation for DBA 3 DBA ENVI NIAL FSAR L0raunsa (1)gg (2),5gg CON 01110N 5(Cil0N SV51EM [QUIPfENT Lube OfI sump tanks outside Containnent Continuous Continuous SS 9.5.7 ! DifSEI GENEM10R tuSRICAllan 5YSILM * * * *
*
- Lube Oil pumps & drivers
* = = =
- Lube Oil coolers & heaters = =
" * =
Lube Oli keepuare pumps & drivers * *
" "
- tube all filters * *
" " " a-Piping & valves
" " " a
"
Instrumentation & Controls y Outside Containment Continuous Continuous D 10.3 5 e MAIN SIEAM Sf51EM isolation Valves *
- E N
- Not Required Continuous N Safety valves
" "
Modulating atmospheric " Not Required Continuous dump valves
- "
Piping from steam
- Continuous Continuous generators to the isolation valves Outside Containment Continuous Continuous 0 10.4.1 MAIN FEELMA6tR feeduater isolation SYSTEM valves AuxlLIARY flitMAIER Drain. unter storage Outside Containment Short tera NI Continuous C2 10.4.9 SYSTEM tank
" * "
Pumps & drivers
- 84
* * * *
"
Piping & valves
* * * =
"
Instrumentation & Controls i 1
-
l , i
'
I
- ---
1ABt! 3.11.1-1 Uheet 8 T 8l Required Duration Normal /Abnosmal of Operation for 08A (3) [$A (NVIRONMENTAL F5AR 5V51EM EQUIPMNT LOCAll0N (2)g$gg CONDITION SECil0N (1)LOCA RtACIOR PRulECil0h kP5 Cabinet Outside Qtatement Short terin Short tesm(6) b8 7.2 SV51EM " "
"
Process sensing channels inside Contalement Al Inside crane wall
" " "
Reactor trip switchgears Outside Contatsment
* * " "
RPS & f.FC remote control abdules
* *
- Aux. protective Outside Containment cabinets k ENGINEEltED 1Afflf ESFAS auallisry relay Outside Contalement Short term (6) Shortterm(6) 88 7.3 k*
FEAIURES AllUAllDN cabinets SV51EM ? Process sensing channels inside crane wall & " " AI. A2, 81
- E
, Outside Containment
" * * "
Actuation logic CONI AINME NI lipdrogen monitors Inside Containment Continuous Available A2 4.2.5 AlMOSPHIRIC IONil0R SY5sEH 2 NOIES: 1. The design basis LOCA 11 based on the po:tulated 11.17 f t double ended reactor coolant pump suction pipe break.
- 2. The design basis MSL8 is based on the postulated 28" main stese line break.
- 3. See Table 3.11.1-2 for Nocmal/ Abnormal & DBA Knvironmental Conditions
- 4. Spent fuel pool cooling recuirement is indepencent of tb? alant conditions and the system would be in operation as long as there is spent fuel in the pool.
- 5. Piping is required to maintain its integrity during and after the accident.
- 6. Shorc term is defined as no longer than 24 hours efter the accident initiation. See Class IC IIst for specific equipment period of operability re9etrements foe all equipment re.nired to operate during a LOCA or itst8.
- 7. Certain su>st accident s,onitorin3 instricientation 'as reoutred for lonn tem oneration.
t . . , ,
-_ - --_ - ___ _A_
.- - - . . - o IA8tt 3.11.1-2 UFeTlPT SteetARV 0F SEISMIC CAIELORY I SIEUCTURES/ BUILDINGS liitTITDIFTii91NdlRErtDiiM1T111it . PLANT AREA ENVIRONMENIAL 5t#91t R WINita RADIATI0st DOSAGE DOA ABNORMAL PRES $URE VISRATI0el CONDITION (NORMAL) (NORMAL) *(8) CODE *(10) *(11) *(11) (Extremes) (futremes) Design RH1 W8 I Desten RH% Normal Accident F Summer I Summer (HVAC Systein) g,$3gg,,,) 08 I (ba.) (Ns.) DB I *(ll' F Winter F Winter (Max.) (Mi n.') (Min.) (Min.) Rads /fr. Pads 5 RH 1 RH
. Containment A
*(6) *(2)
Contalsment inside Crane Wall ke circ Al Rec-135F 80% 89.01 Rec-95F Vary tater See Table See Figure 135F hormal Balanced Mode (Non-Redundant (9.4.6) Purge-95F 20% 66.0F Prg-55F 3.11.5-2 3.11.1-l.2 95F with Atmosphere flote c
-CIC) Purge Ibde 3.11.1-3.4 20%-801 [0CA-3.II.1-2 *(13) %
(Redumfant-t PD) M5tB-3.II.1-4 g a ,=. N Contserment outside *(2) f C
"
Crane Nde Wall Re-circ (Non-ReJundant. *(4)(A29.4.6)Rec-135F 801 89.0F Rec-95F Vary 42B See Table See Figure 135F Balanced with CFC) Purge Nde Purge-95F 201 66.0f Prg-55F 3.11.5-2 3.11.1-1.2 95F Atmosphere liote (Redundant-CPD) 3.11.1-3.4 20E-801 *(13) General Service Building B Primary Aux. Area Bl .ggg (Non-Redundant iHPA) (9,4,y) 98f 601 85.5F 55F 301I51 3.91 later Later Later.ggg Negative Note 401 77.5F *(13) Waste lreataient Area 82 98f 601 85.5F SSF 30t!51 1.16 e.23sl0 0 Later'III Later *III Negative Note (Non-Redundant-HRW) (9.4.3) 40% 77.5F *(13)
*(6)
*[8),,"jgf'{l2) kg
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80F 1 69 F $5I 401 ( 10.00 44.5 Negative
. 601 40%-605
.
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ I A8t f 3.11. 5-2 ISheet 2 of 4I INVIRONH[NIAL Sit 9E R WIN 1ER RADIATION 005AE D8A A8 NORMAL PRESSURE Vl8RA110N PLANI AREA CONDill0N (NORMAL) (NORMAL) *(8) CODE *(10) *(111 *(11) (tstremes) (Futremes) D* sten RH1 W8 F Deslen RH1 Normal Accident F Susener F Sussner (HVAC SV51til) 08 F Max.) (Nn.) 08 I (1) F Winter F Winter (FSAR Ref") (Me.g. ) Min.) (Min.) (Min.) Rads /fr. Rads 1 RH I RH General Ser @ es uldg. (cont) Safeguards A.ea 84 98F 601 85.5F 55F ! < 10.00 30151 < 10.00 13(T *(5) 130F *(5) (Redundant-11SG) (9.4.5) 401 77.5F 5/ 501-451 5/ 501-451 Ne9ative Note *(13) Diesel Genesator 85F 601 85.5F 10F 1511 51 < 10.00 < 10.00 130F *(5) 130F *(5) Slightly Ate *(13) Area Redundant- 95 401 77.5F i 17 Positive 1108) Diesels on) (9.4.8) 301 201 301 201
'fg
- f 85 90F 601 7 3F ' 55F 301I 51 < 10.00 4 10.00 N/A N/A Slightly Note *(13)
'
'
e HOG) (Diesel:. of f) I9*4 0I I *i
=
ro Y Mec hanical .1 -eulp. *(3) 301!51 Later leightly Area for Class I 86 99F 601 85.5F 55F later 130F *(3) 130F *(3)
& ll Equiene.it (9.4.16) 401 77. 5F Igf*(5) Igf *(5) Positive note *(13) 501-451 501-451 (Redundant-Ht R) (9.4.17) *(9)
*(9)
Electrical I palp. 87 98F 601 85. 5F 55F 301! 51 (10.00 <10.00 130F *(14) 130F *(14) Slightly ll/A b I'I*'O Ad** (9.4.7) 401 17.5F Igf Igf Positive Are4 - 501 US 501 451
,
)
Control & Ana. 88 75F '501 62.5F 75F 451 410.00 < 10.00 75F 75F Equipment R " 61.0F 77 75t Positive N/A (9.4.1) 451 (Redundant-liCL ) 401-101 m!!M w -- - .. , 0 _ - - _ .
- _ - _ - _ _ _ - _ _ _ - - _ _ _ _ _
*
- 2* ~
* * & * *
- _
*
'
'
O U U V U O O V V U V I A8t f 3.11.1-2 [5E et l of 4T PLANI AREA ENVIRONMfM1AL SlHER WINilR RADIAIION DOSAGE DBA A8. . PRf 550RE VIBRAlloft r'NtDilION (NONMAL) (NORMAL) *(8) u *(10) *(11) *(11) (Futremes)(Estremes) (HVAC 5V5I1:1) Design Rit! W8 F Design RH1 Normal Accident F Swsner F Summer 08 F (M.ss.)(Max.) Da F *(l) F Winter F Winter (Man.) (Min.) (Min.) (Min.) Rads /fr. Reds 1 Ril . RH Electrical. Pipire I"""*I5 A I"""*I"' 810 95F 601 85.5F $5F 301151 10.00 Later 130F *(5) 130F *(5) ment Penet:4 tion 77.5F 5F Sgf Negative Note *(13) (9.4.12) 401 Aream (Red... dant- 501)-451 501 451 IIPI) Cosponent Cooling & Fukeup B11 95F 601 85.5F 55F 301I51 10.00 tater 130F *(5) 130F *(5) 401 77.56 55F 55F Negative Note *(13) Pump Area (9.4.13) (RedundantilCA) Switthgear. Battery *(6) S
. & Cablespre. ding B12 85F 501 10.5F RI.F 351 10.00 10.00 90F 85F ?
N Area (Redus.Jant- (9.4.9) (104F) 351 65.5F 97 8F Slightly N/A C 401-101 401)-101 Positive *-
? 185C) SWGR m
lank Enclosare h - Area C Demineralized & Borated Water Storage Cl 98F 601 85.5F 55F 301151 10.00 N/A 130F *(5) 130F *(5) lank (Reh.lant-MLR) 9.4.19 401 77.5F IQF IQF Slightly N/A 9.4.20 501-451 501-451 Positive
.
_ _ _ _ _ _ _ _ _ _
__
.
TA8tf 3.11.1-2 [ Sheet 4 of 4T ENVIRONE NIAL StMA R WINIER RADIAll0N DOSAGE DBA ABNORMAL PRESSURE vitRAll0N PtANI AREA CON 0lil0N (NORMAL) (40RMAL) *(8) CODE *(10) *(11) *(ll) , (Fatremes) (Futremes) (HVAC SYSitH) Deslog RH1 W8 F Desjon RH1 Normal Accident F Suminer F Sussmer D8 F (Max. D8 F lal) F Winter F Winter II N'#*I (Max.) (Mle.))(Min.) (Ham.)(Min.) Rads /fr. Rads 1 RH 1 RH Steam & Fece.ater Isolation Valve D House Steam & Feed..ater 3 6 Isolation Valve D1 90F 70E 85.5F SAF 301I 51 12.5:10 2x10 HEL8*(7) later Area (Non-ReJondant- (9.4.14) 401 77.5F 420F *(9) Slightly Note *(13) $ HlA) 1001 Positivw ?
*
e Electrical Ei,ultment a
'd Roam in Steau & D2
#
e Feddwater Isolation , Valve House Spray Pond P..mp E 98F 701 88.5F 55F 301-51 N/A N/A 121F 121F Slightly Note *(13) House (Redundant-VAB) (9.4.15) 401 77.5F 55F 55F Positive
.
V j j - - _ _ _. O * *
- e 9 - O n 9 m O O O O
l I e hge 23 ) WNP-1/4 NOTES: 3.11.1-2
'
O. B. = Ory Bulb Temperature W. B. = Wet Bulb Temperature R. H. = Percentage Relative Humidity
- Max. = Maximum Min. = Minimum N/A = Not applicable. The environmental parpfaeter is not present or
.
significant enough to warrant consideration. J
* (1) Dose rates in Rads under accident conditions has been integrated over ,
the duration of accident, DBA or LOCA which results in maximum dose rate.
* (2) Maximum hypothetical accident release in the Containment, gama J radiation. Integrated dose levels, applicable to equipment located inside containment building with respect to the time after the LOCA, a:e provided in Table 3.11.5-2.
* (3) Mechanical equipment room containing Class I and II equipment will have ventilation available under LOCA and LOOP.
* (4) Under normal operating conditions, while in recirculation mode, de containment interior temperature may fluctuate between 950F and 1350F, depending on the number of air-conditioning fan coil units in operation; 1300F for one fan, 1120F for two fans, 1000F for three fans, and if all fans are running.
3 * (5) The indicated temperature of 1306F is the maximum daily temperature which may last for five (5) hours in any 24-hour period. The twenty-four hour average for such extreme environmental conditions will be 1170F. The duration of this environmental condition can be as long as twenty-nine (29) consecutive days, but may occur only once during the 40-year design life of the plant. It is possible that these _J temperature conditions may occur concurrent with other design basis events, including LOCA or LOOP.
* (6) During plant shutdown, the minimum temperature of 550F DB will be maintained.
- D * (7) Values listed for temperature, humidity, pressure, and radiation are for a main steam line break outside containment in the area of the main steam valves. All other areas are governed by the values listed for LOOP.
D r , I
_ 1 i O) Page 29 WNP-1/4 1 l
* (8) Pressure requirements within individual areas depend on the contami- i nation level within that area. Air flow pattern will be from a zone with lower contamination level towards a zone with higher contamina- , Ol tion level within the same area. This is also true in the case when air flow from one area to an adjoining area. * (9) No air circulation is provided during and following a LOCA or LOOP. * (10) Provides cross reference between Table 3.11.1-1 and Table 3.11.1-2 9 for environmental conditions. * (11) Exterior Environmental Design Conditions (Normal)
Summer Winter s G Design Dry Bulb Temperature 1100F -100F d Design Wet Bulb Temperature 700F -10.20F Design Relative Humidity 12% 90% I Design Dew Point Temperature 460F -130F
* (12) Based on normal spent fuel pool water temperature of 1400F. * (13) All the rotating machines identified, such as pumps, compressors, ) ,
fans, etc., are subject to non-seismic vibration during their ' operation. All safety-related pumps are designed such that the perk-to-peak vibratica is within the following limits at rated speed and at a cap'acity of + 10% from rated capacity: c Double Amplitude Vibration (Mils) At Rotational Frequencies
.
Or Speed At the Sleeve Bearings 1200 and below 4.0 mils
- 1201 to 1800 3.0 mils
- i e
- Vibrations are measured on the rotating shaft.
* (14) During LOOP or DBA conditions, this area is fed by natural circula-tion from the safeguards area HV&AC system. Temperature alarms are provided which facilitate operator action to open dampers.
) O l
l l l .
.
1 0
9 f' WNP- 1/4 FSAR D . TABLE 3.11.5-2 TIME-LdPENDENT INTEGRATED BETA AND CAMMA DOSE
- IN THE CONTAI!Rd.ENT A?.0 SPHERE O
BETA . GAMMA TOTAL TIME AFTER LOCA (Rad) (Rad) (Rad) 1 He 2.6(+6) 5.0(+5) 3.1(+6) D 12 Hrs 1.2(+7) 2.2(+6) 1.4(+7)
.
1 Day 1 8(+7) 2.9(+6) 2.1(+7) 10 Days 6.4(+7) S.5(+6) 7.3(+7)
,
GD 1 Mo 8.4(+7) 1.1(+7) 9.5(+7) 6 Mos 9.8(+7) 1.1(+7) 1.1(+8) 1 Yr 1.1(+8) 1.1(+7) 1.2(+8) O
.
r
.
.
.
O
.
O O
. O
- -
O O U U U U U U U U U
,.
54 _ .- WNP-1/4 s-- .~ _-._ WNP-3/5 46 - LOCA s - - - -- .- - 3 / I
/s / Combined LOCA,
/ \ / l HSLB 38
,' .
/ I
/ l- - - --- -- __ _ _ _ _ _
,
/
m E
~
/
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E I M 22, g / HsLB
' /
/
FIGURE 3.2.1-1
/ CONTAINHENT PRESSURE IIISTORY 14 . DURING LOCA, HSLB
/ .
/
6. , 2 3-
- %
2f 10 lo'l 10 2 '3 l0 '4
}9 3 5
Time (Seconds)
_ - _ _ _ _ _ _ _ _ _ _ _ - _ _
O _ _ 5 _
.
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_ 0 _
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0 0 0 0 0 0 0 0 6 2 8 4 0 6 4 3 3 2 2 2 1 y* $ X [" ggc$SO" -
.
3 1 3.2.1.2 WNP-3/5 Environmental Service Conditions 3 e Control Room
!
'
- The control room areas will be heated and air conditioned--
with protection provided against radiation to allow safe and continued occuoancy. The HVAC system consists of two Class 1E, capacity air-handling trains which prevent system loss in D the event of a single component failure. ( During loss of off-site oower, the redundant HVAC system is automatically placed on the emergency power source sunplied from on-site diesel generators. Transfer from normal operation to emergency filtration is accomplished auto-matically upon a high radiation or high chlorine level 3 signal. Therefore, no special environmental design requirements for' loss of ventilation or air conditionina need be incorporated in the design of safety-related electrical and instrumentation equipment located in the control room. The ability of the Class IE equipment to perform its safety function under the environmental service O conditions is demonstrated in the equipment qualification program. e Auxiliary Building Equipment required for Class 1E operation is assigned to O separate rooms according to redundant actuation trains. These rooms are heated and cooled by Class IE HVAC units which may be placed on the emergency power source upon los:, of off-site power. The auxiliary building ventilation systems consist of the O main ventilation system (which provides normal auxiliary building ventilation), the ECCS area filtered-exhaust system (which provides post-accident air filtration of the ECCS area), and the ECCS area fan coolers (which supply cooling to the safety-ralated pump areas required to function during the DBE). The portion of the auxiliary building main HVAC system which provides ventilation to the ECCS area will be isolated automatically upon initiation of a costulated DBE. Simultaneously, the ECCS filtered-exhaust system and fan cooling system will be actuated tc orovide coolina and ventilation to the pump areas throughout their required O' operation. Since the safety-related equipment and HVAC systems are I separated by rooms according to redundant actuation trains, l a single component failure in the HVAC will produce loss of cooling only within its actuation train. The remaining O train is designed to provide the necessary safety function durina the postulated DBE. The ability of the Class 1E equipment to perfonn its safety function under the environ-mental service conditions is demonstrated in the equipment qualification program. 9 I
, _r-. y ..p, -
9 - -- .-
Ol l e Fuel-Handling and Storace Areas The fuel-handling area heating and ventilating system , consists of a s'pply subsystem, an exhaust subsysten, ' j and a return-air subsystem. -
- The normal operation of this ventilation system is to l
orovide outside air to both the fuel-handling area and I fuel-storage pools from the supply subsystem. The exhaust - subsystem will draw air from the fuel-pool area and 8 discharge to .the atmosphere via the return-air subsystem ( discharge duct. Similariy, the return-air subsystem draws air from the entire fuel-handling buildina for return to the supply air subsystem or the atmosohere, deoending on the temperature of the outside air. Each of the above subsystems is equioned with redundant fans in parallel, 9 one fan on standby, to ensure continuous operation of the ventilation system. In the event of a postulated fuel-handling accident, the supply and return-air subsystems each contain dampers, arranged in series, to isolate the fuel-handling building g from the atmosohere. The fuel-handling building ventilation, then, is interconnected and maintained by the ECCS filtered-exhaust system. The ability of the Class 1E equipment to perfom its safety function under the environ-mental service conditions is demonstrated in the equipment qualification program. g
<
e Containment In the reactor building, the combustable gas control system and the shield building ventilation system are the only safety-related ventilation systems. , Since neither system contributes to the heating or coolina of the containment environment, during accident conditions safety-related components must be designed and qualified to function under DBE conditions. Examoles of such components are instrumentation transducers, motor and solenoid-operated valves. These items are cualified to withstand the extreme 9 temperature, humidity and radiation effects of the postulated DBE. l Figures 3.2.1-1 and 3.2.1-2 illustrate the pressure and temperature orofiles produced by a postulated DBE in the WNP-3/5 containment region. The equioment is 'aualified g to withstand these profiles and a 40-year integrated radiation dose including the DBE event. , e Diesel Generator Are__a_ l l Each diesel generator room is orovided with three(3) Class g l 1E, 33-1/3-percent-capacity exhaust fans plus a seoarate I heating and ventilating unit. The exhaust fans provide 1 O
1 D.c additional cooling to the room when the diesel is operating. The separate unit supplies filtered, } conditioned air to maintain room conditions when the diesel is in standby. e The exhaust fans and the seoarate HVAC unit are supplied power from a nomal source. Upon a loss of off-site power, power to each HVAC unit is supplied by the respective diesel generator. Thus, a single ( component failure affects only one of the two standby generators, leaving the remaining generator to supoly emergency power to mitigate the consequences of a DBE and provide safe shutdown of the plant. All safety-related components associated with the diesel ) generators are qualified to withstand the operating, environmental, and seismic stresses exhibited in Table 3.11.1-1. e Switchaear, Battery, and Cable =Soreadina Area )( This area is provided with redundant Class 1E, Seismic Category I HVAC systems. Upon loss of off-site power, the systems are automatically connected to separate emergency buses and powered by separate diesel generator units. D The redundant systems are required to operate durino F. both normal and accident conditions to maintain an acceptable operational environment for the safety-related equipment in each electrical-equipment and battery room. No single component failure will result in the loss of heating, ventilatino, and air conditioning 3g to any room in this area. The operating environment that this HVAC equipment is designed to maintain is defined by Table 3.11.1-1. The ability of the Class 1E equipment to perfom its safety function under the environmental service conditions is demonstrated in the equipment qualification orogram. 3 e CCWS Dry Coolino Towers Eouipment Area Redundant electrical equioment is located in two separate CCWS cooling tower rooms. Each room is served by a Class IE 100%-capacity air-handling unit located within the room it serves. The unit must provide acc 7 table operating 3L conditions for the Class 1E eouipment within the roem during normal and accident conditions. In the event of loss of off-site power, the separate air-handling units will be switched to their resoective diesel source of emergency power. No single component failure will J result in the loss of ventilating canability to both equioment rooms. Table 3.11.1-1 reflects the environmental conditions provided by the air-handlina units. The ability D
- - _
O of the Class 1E equipment to perfonn its safety function under the environmental service conditions is demonstrated in the eauipment qualification orogram. g 3.2.2 Seismic Conditions Plant seismic response spectra are develooed in accordance with the criteria stated in the " Standard Review Plan", Section 3.7. Section 3.7 of the Supply System SAR responds to the Standard , Review Plan by providing the criteria used for the develooment g of the individual plant seismic response spectra. Floor response spectra have been developed for each elevation of the various plant building areas using an analysis of the time history method. These floor response spectra are inserted in the technical specifications for vendor use in seismic # qualification of safety-related eouipment.
<
The Required Response Spectra (RRS), Test Response Spectra (TRS) and test results are contained in the individual test reports for each equipment tyoe and in some cases for components. O Sumaries of the WNP-1/4 qualification plans contained in Apoendix A also reference the individual test reports. WNP-3/5 oroject sumaries will be provided in conjunction with the WNP-3/5 FSAR. i ! The details with respect to the methods used for seismic qualifica-l tion are discussed in Section 4.2.3. O 3.3 Class 1E Electrical /I&C Equioment Acceptance Criteria , The Supply System Equipment Qualification Program evaluates the i report submitted to provide qualification of electrical and I&C equipment based on the' criteria established in Section 2.0. The , acceptance criteria used to evaluate this report covers three major areas: l e Content of the Qualif ication Plan / Test Procedure l e Technical Adequacy of the Oualification plan / Test Procedure O e Demonstration of the Equipment to Perform Its Safety Function per the Test Procedure. 3.3.1 Content The Supply System acceptance criteria requires that the vendor G qualification plan / test procedures address specific items. Among the more imoortant of these items are the eauipment description, aging simulation methods, service conditions simulated, and the test sequence. Appendix C provides the detail af the cualifica-tion acceptan.: r criteria. O S
- _.
G n l 1 3.3.1.1 Equioment Description It is imoortant that the vendor describe the equipment. and its model number so that the Supoly System may ensure that the equipment to be installed in the plant is the same as that tested. The mounting of the equioment and connections must also be described. These are reviewed by the Suoply System to ensure g that the expected plant installation is simulated accurately by the qualification method. 3.3.1.2 Aging Simulation The vendor aging orocedures are revievred for detail and justification of methods. Arrhenius and/or stress analysis ,< methods are required to ensure conformance with IEEE 323 and NUREG-0588. 3.3.1.3 Service Conditions The vendor qualification procedures are reviewed to ensure
- that the Supply System service conditions, as defined by the Technical Specifications, are addressed and enveloped.
3.3.1.4 Test Sequence Section 6.3.2 of IEEE 323-1974 requires that the specific O sequence of testing be conducted which accurately simulates and envelopes olant-specific service conditions. The vendor qualification program is reviewed to ensure comoliance with this requirement. 3.3.2 Technical Adequacy O The items discussed under 3.3.1 above, are reviewed for technical detail and accuracy to conform to the Supoly System Technical Specifications, IEEE 323-1974, or its daughter standards that are supported by regulatory guides and/or NRC documents. Appendix C illustrates the depth of technical detail required from the g vendor in preparing an acceptable qualification program. The summary reports contained in Appendix A also present the para-meters required to meet or envelope the Supply System plant requirements. O O
,
O
( U U U U U U U U U v .v n n ,
.
l l l WNP-3/5
.
I ABL E 3.11.1-1 (Sheet I of 5)
#
IQUIPMENT REQUlpfD 10 PEHf0HM 5AFEIY FUNCil0NS tullNG AND Sil85t4Uf MT 10 A Of 51GN BASIS ACCIDfMI ENVIROISKNTAL [5AR LOCA MSL B CONDITION SECil0N SY STEM IQillPMtNT LOCATION (se5fEI) Air Conditioning, Heating, Cooling, & Ventilation Systems outside Containment Continuous Continuous B-C 9.4.1 (a) Control Room Air Conditioning System, ILC, Associated Equipment 4
* " " "
l-C.D.E 9.4.2.2 (b) ECCS Area f an Coolers
" " *
- l-C,0 9.4.2.3 (c) Electrical Equipment
& Sattery Room
" " Not Required Not Required I-C,D,E 9.4.2.4 (d) fuel llandling Sidg.
"
- Continuous Continuous B-C.D H 9.4.2.5 (e) Diesel Generatur I " *
- l-G 9.5.4 Diesel Generator fuel Storage Tanks
$e Oil Storage & Iransfer
.
* * * *
- System fuel Oil Iransfer Pumps *
* * " "
"
Day Tank
* * * *
- Interconnecting Piping
' & Valves
*
" " "
l-C,0 Instrumentation & Controls
* *
- I-C.D,H 9.5.5 Diesel Generatur Jacket Water Cooler Cooling Lter System * * * *
- Ja. set Water Pump
* * *
*
- Intercooler
* * * *
- Intercooler Water Pump
* * *-
l "
- Valves & Piping
" * "
Instrumentation & Controls
" l-C.D
* "
- tutte all Cooler
- l-C.D H
-
WNP-3/5 IABit 3.11.1-1 (Sheet 2 of 5) EQUIPMENT R10UlRLD 10 PERf 0RM SAFETY IUNCil0NS [11 RING AND SUBSEQUENT 10 A DESIGN 8ASl5 ACCIDINI [NVIR0fMENIAL ISAR LOCA MSL 8 CONDlil0N SECil0N SYSifM [00lPMfMT LOCAll0N (NOTFl] Continuous I-C D 9.5.6 Diesel Generator AC Motor Driven Outside Contaltunent Continuous 5 tarting Air System Cynpressor Starting Air Dryer
" * *
" "
Air Receivers
* * *
"
- Solenoid Operated Starting Valve
" " "
"
- Piping & Valves
* * *
"
- Instrunentation & Controls Inside Containment Not Required Not Required I-A,8 5.0-5.2 Reactor Coolant System Reactor Vessel
" "
" Continuous Continuous ,
Stesa Generators ILC O e * * " " " ' Pressurlier I&C
* * * *
- Reac tor Coolant Pump, Mon. Sys.
" " " "
"
RCS Piping I&C Contairement Heat Removal System Outside Containment
" " l-C,D,E 6.2.2.2.2.1 Contairveent Spray System Spray Pugs & Drivers
" * *
- 9.2.10.2.2 Stutduwn Cooling Heat Exchangers l&C 9.3.4.8.3f Refueling Water Tank laside & Outsl
- 6.2.2.2.2.5 Valves & Piping I&C Containment insulation & Heat Iracing
- 6.2.2.2.2.7
" 6.2.2.5.2 Instrissentation & Controls s
* * * * *
- G ___
e __ e
U U' U U U U U U U V b J (~ r n ] ! ime-3/5 i i IABLE 3.11.1-1 I (Sheet 3 of 5) EfpilPMf hi Nff)JIRID TO PERIORM SAFETY flmCil0NS DINilNG AND SUB5f t)KNT TO A DESIGN 8A$15 ACCIDINI i
. 1
' [NVIR000l[NTAL ISAR
, $Y511M EQUIPMENT LOCAllON LOCA M5t 8 CONDI TION
~
Sfcil0N
~
(1Inffl)
i 1 Radiation Nnitoring Instrassentation & Controls Inside & Outside Continuous Continuous I-A,B,C,0,E.F G,H 11.1.4 System Containment 12.1.4 Main Steam System isolation valves outside Containment *
- I-A,8 10.3
* *
- Safety Valves
- Not Required
"
Modulating Atmospheric
- Continuous
- l-A,C
" "
l&C On Piping from Steam * " l-A E Generators to the Isolation
! e Valves
! *" * *
? Main feedwater System feedader Isolation Valves, I&C
" "
10.4.7
i Auxillary f eedwater Pumps & Drivers "
$hort-Ters
- l-C,0,E 10.4.7.2 Sys tem
- Condensate Storage Tank * *
- I-C,0
"
- I ILC On Piping & Valves inside & Outside " l-A,B,C,D,E Containment
* * "
Instrassentation & Controls " l-C D j Onsite Power Systems (a) A-C Power System 4.16kV Distribution outside Containment Continuous *
- 8.3.1.l.3 I 480V Distribution " * *
- 8.3.1.1.4 120V Vital * * * "
8.3.1.1.6
,
* * * " "
Cables
* * * *
- Electrical Panel
. A
- i
? 1 ________________o
.
WNP-3/5 IABtE 3.11.1-1 * (Sheet 4 of 5) EQUIPMfMI REQUIRED 10 PERFORM SAFETY FUNCil0NS DURING AND SUBSEQUINI TO A Of 5IGN BASIS ACCIDf MI ENVIRONMENTAL FSAR LOCA M5t B CONDITION 5ECil0N LOCA TION SV5ftM EQUIPMENT (N6TFI) Outst& Containment Continuous Continuous I-C D 8.3.2.1.1 (b) D-C Puwer System 125V IE
* " *
*
- Electrical Cables
*
" " " l-A,B,C,D,E Electrical Penetrations Imergency Core Cmling System inside Containment
* " l-A,8 6.3 (a) Core Ilouding System ILC On Saf ety Operation Tanks
- inside & Outside
" " l-A,B,C,0,E ILC on Piping L Valves Contairwient
"
ILC Ref ueling On Water Tank Outside Contairment
" I-C i (b) Safety injection y System
" "
e Safety injection Pumps
*
- I-C D E.
& Drivers
- Inside & Outside
*
- l-A,B,C.D,E ILC On valves & Piping Containment
* *
- l-A,B.C.D.E 6.2.4 Con ta lisai n t iso lat ion I&C on Valves & Piping Sy stem 6.2.5 Coubustible Gas Control Systems outside C .eatament
* " l-C,D,E 6.2.5.2.3 Sampling & Monitoring filters Sy stem * * * *
- H2 Analyz er
* * * *
-
Saaple Cylinder
* * * *
- Sanple Pumps
" * * *
-
Piping & Valves
"
- Not Required
- 6.2.5.2.2 Ctetalraent H2 Purge f ans & Drivers Inside Containment
- Continuous I-A,8 6.2.: . S. ]
H2 Raoub hution System H2 Rwunbination Units
*
-
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O U U U U U V U U V U s r n m +
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WitP-3/5 IA881 3.II.1-1 (Sheet 5 of 6) (tjulMNI NitpilN1010 PtRit*M SAf fly fintCII(m5 l IslHjemi AaNa SH85f tllifMI 10 A of 51GN SASIS MClefMI l i INVINONHfMIAL (SAR i I OCA M58 8 CON 06Iloll sic [losi (OCAi10N SV SIiM (iQPMfIII (iiBit'l)
.
flot Sequired (later) 9.l.3 outside Containment isolate.1 Spent tuel Poul Cuoling Piastis & lirivers Suring LOCA
& Cican.g System * * * "
*
- Heat tachangers "
* *
"
- Valves & Flping * *
* *
- lastruwntation & Control Continuous I-f 9.2.2
- Cont lemsous Comenaient Couling Water Dry Coollag Tower
- System " *
- l-C,0,f
$leutduwa Coollag tot *
* *
*
- Pugs & Drlwers * *
* *
"
tssential Valves & Piping . .
. .
.
Sungo 144 "
,
" * " l-C,0 5
Instrumentation & Control 7 outside Contatsment Sliort-lein Short-Iern I-C 1.2 Reas.tus Ps utistiusi System NP5 Cabinet * *
* *
- Core Psotection Calculator "
*
- l-A,5 Protess lastrissent Channels
-
laside Contalsment
*
*
- I-C,0 Neactor Irty Sultchgear outside Contalsement
*
* *
- l-C NP5 Hemote Control Modales "
* *
- l-C,0 Ausillary Protection Cabinets Continuous I-C 1.3 L$t AS Ausillary Relay outside Contalemment Cuntinuous ingssacering Safety f eatuses Actuatiost System Cabinets "
"
- l-A,N,C,0 Instrassentattost & Control laistde & Gutside Cont alsucut (Outside Seiteld Wall)
. "
" " l-C,0 Ac tuat ion logic Dutside Contaisument
_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
Ol NOTE 1: Table of WNP-3/5 Environment Conditions ENVIRONMENT DESIGNATION I-A - Containment Environment: Loss-of-Coolant or Steam Line Break I-B - Containment Environment: Nomal Environment
- I-C - Auxiliary Building Environment: Nomal Environment I-D - Auxiliary Building Environment: Loss-of-Coolant Accident I-E - Auxiliary Building Environment: Steam Line Break (Outside Containment)
I-F -- CCWS Dry Cooling Tower Electrical Equipment Rooms: All Plant Conditions I-G - DGFOST Rooms: All Plant Conditions ,' Diesels Running T I-H - Diesel Generator Areas: l The specified conditions for each category are listed below and equipment will be rated for operation for these and more severe conditions. I-A g 4 PARAMETER NORMAL ACCIDENT Temperature 40-122 F 383 F Instantaneous Peak 370 F for 20 seconds 350 F for 10 minutes g 250 F for 90 hours 200 F for 7 days 175*F for 31weeks 150 F for year Pressure / Steam 0-5 p.ig/ t 40-44 psig for 10 minutes e Partial Pressure or 10-90% RH 30-35'osio for 90 hours Relative Humidity B-10 psig for 7 days
,
5 psig/100% RH to 1 year 1x10 7Rads 3.3x10[ Rads
- g Radiation Dose 30-100 min After 100 min 400M00 pm v onme t tepsity pH(NAbHduffer) @00-6800 pom 9.0-10-0 10.0-11.0 is 0.7 Gal / Min /Ft directed vertically downward)**
O I-B Temperature 400F-122 F Pressure 0 psig - 5 psig Humidity 20% - 90% RH O Radiation 1 x 10 Rads Chemical Not Aoplicable
- Dose consists of 40 year integrated dose plus 1 year LOCA dose.
**The manufacturer shall detemine the most severe conditions within #
these ranges, and conduct any qualification to these minimum conditions. 1
-42A- G
_ _ _ _ _ _ _ - .
e' I-C PARAMETER NORMAL ACCIDENT 3
Temperature / Humidity 40U F-1040 F at 20% RH to (**) - Pressure Atmosphegic Radiation 3.5 x 10 (Max.) Chemical Not Applicable <J I.0
,
0 Temperature 120Ffor4gours Decreage120F to 104 F Humidity 20% - 90% RH 3, Pressure Atmosphegic
<
Radiation 3.5 x 10 (Max.)(*) Chemical Not Applicable I-E Temperature / Humidity 1100F/50% RH Long Tenn ( 330 F/100% RH Short.Tenn Pressure Atmosphegic Radiation 3.5 x 10 Rads (*) (Max.) Chemical Not Apolicable I-F Temperature U 40 F-104 F 400F-104 F Pressure Atmospheric Atmosoberic Humidi ty 0-100% 0-100% Radiation Negligible 3.4 x 102 Rads (*) g( Chemical Not Aoplicable Not Applicable I-G 00F-120 F 0 U Temperature 0 F-120 F Atmospheric Atmospheric 3 Pressure Humidity 0-100% 0-100% 2 Radiation Negligible 4.7 x 10 Rads (*) Chemical Not Applicable
- Dose consists of 40 year integrated dose clus 1 year LOCA dose.
Jt
**The manufacturer shall determine the most severe conditions within these ranges, and conduct any qualification to these minimum conditions.
3 J
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} 4.0 OUALIFICATION PROGRAM METHODOLOGY The methods below are used by the Supply System to qualify Class 1E instrumentation and electrical equipment to the requirements )F of IEEE 323-1974, or its daughter standards that are supported by regulatory guides and/or NRC documentation. These methods are used to qualify equipment to meet postulated service conditions discussed in Section 3.2 of this document. 3 The first portion of this section discusses methods used in qualification. These methods consist of: er Qualification by type testing e Qualification through operating experience, supported by 3( partial type testing e Oncoing qualification, after establishing an equipment qualified life e Combined qualification by analysis, supported by partial type C( testing e Qualification by utilizing military qualification methods. The second oortion of this section addresses' the types of service conditions to which the above methods are used to qualify equioment. D Where the conditions below cannot be simulated within the limits of the state-of-the-art, engineering judgement will be used. These service conditions are: o Humidity e Temoerature 3 (. e Radiation e Op: rational e Vibration e Chemical e Seismic e LOCA and HELB 3 4.1 General Oualification Methods IEEE 323-1974 provides for the following general methods to qualify Class 1E equipment.
- Qualification by type testing e Qualification through ocerating experience, supported by cartial type testing e Ongoing oualification, after establishing an equicment qualified 3 life e Combined qualification by analysis, supoorted by partial type testing 3 e Qualification by utilizing military cualification methods.
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D f Analysis alone is not listed in this document, although it is part of IEEE 323-1974. In most qualification programs, the combined qualificatiert approach by test and analysis has been used. g 4.1.1 Oualification by Tyoe Testing The type test program is used to demonstrate that the Class 1E , l equipment can perfom its safety function within the accuracy ' and response time' requirements apolicable for nornal, abnormal 3 . and DBE sertica conditions. The type test will consist of a demonstratiort of safety functions under a planned sequence of simulated service conditions both before and after age conditioning. Adequacy of the type test orogram is deternined from the Supply System " Acceptance CMteHa for Class 1E Equipment Qualification". D' This method is the preferred means used by the Supply System to qualify Class IE equipment. 4.1.2 Coerating Experience D< IEEE 323-1974 defines operating experience as an " accumulation of , veMfiable service data for conditiens equivalent to those for the equipment to be verified". In this context, experience can serve as a basis for detennining the qualified life of equipment
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(e.g. , systems, subsystems, components). O In order to deternine that Class 1E equipment is qualified by operating expeMence, the following acceptance criteria must be met: o CcmoaMson and identification of differences between the equipment in service (operating) and the proposed equipment, g' such as differences in equipment design, service conditions, and environmental conditions. An analysis must be provided to justify any extrapolation involved due to differences found. e Identification and history of failures of the in-service equipment must be provided. o e The mandatory maintenance requirements should be stated to provide adequate confidence that the qualified. life of the proposed equipment will equal or exceed the in-service equip-ment. o( The seismic conditions experienced by the in-service equip-s' ment must be documented to demonstrate that these conditions envelop the site seismic requirements. Also, the aging failure mechanisms must be identified for the in-ser/ ice ! equicment. lO i s The equipment selected for coerating experience must have perfomed under conditions equal to or surpassing the If not, { seveMty of the site-specific coerating conditions. ! l supplemental type testing is required of the in-ser/ ice l equipment (e.g. , radiation and OBE exoosure) .
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l 1 e Margin will be suitably considered when deteisining 1 the levels for which qualification is being sought. l When auditable data is provided which demonstrates the above 9 criteria are met, the eQuinment will be considered cualified by reason of operating experience. This qualiT1 cation will be valid for a length of time no longer than the natural aging period. If the above criteria are met, operational experience can be e the most effective method of qualifying equipment. Operating I experience also is useful in supplementing the methods described in Sections 4.1.1, 4.1.3, and 4.1.4.
.
4.1.3 Ongoing Oualification
' e This method is discussed in IEEE 323-1974. The method allows Class IE equipment to be placed in service with an established ,
qualified life of less than the required design life. The qualified life is estimated by means of a mathematical model, then verified using the test and/or analysis methods described by Sections 6.3, 6.4 and 6.5 of IEEE 323-1974. Identical 3 e equipment can be installed for service limited to the verified
.
life. f 4 The qualified life may be extended by removing the in-service equipment prior to the end of its qualified life, and reperfoming e the original aging and type testing. This will extend this type of equipment's qualified life by an amount equal to the original verified life clus the in-service natural aging. 4.1.4 Combined Oualification Class 1E equipment may be qualified by a combination of test, , e analysis, or previous operating experience. There may be various rationales for qualifying equioment by the combined approach. Sample reasons are:
- 1. The equipment is too complex for analysis or too large for l testing alone. eJ
- 2. Tests of selected samples of a particular design group may vary in size but have similar materials and design principals.
Qualification of the entire design group may be achieved through proper analysis techniques using data from the selected test samples. e
- 3. Verification of an analytical model by partial type testing.
- 4. Use of operating experience to develop a basis for simulated aging techniques. ,
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- 5. Analyses correlating the interfaces and degrading effects '
between two subassemblies that have been qualified separately to demonstrate the design requirements when the subassemblies are combined. 8-
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- 6. Military qualification methods may be used to establish a basis for the Class 1E equipment's qualified life.
D The combined qualification demonstrates the equipment can perfom its safety function under normal, abnormal, and DBE service conditions throughout its qualified life. Combined qualification provides auditable data by which the various primary qualification methods may be brought together to satisfy the equipment qualification program. 3 4.2 Design Conditions This section is provided to show how the various qualification methods in Section 4.1 are used to qualify Class IE equipment to the effects of: e Aging e Radiation e Seismic e Design Basis Events D These service conditions are the most complex and difficult to provide qualification methods for and were, therefore, selected for description. 4.2.1 Aging D Simulation of aging is not well bounded. Engineering judgement plays an important role in the present state-of-the-art. Each of the qualification methods mentioned in Section 4.1 may be employed to establish an interval for Class 1E equipment qualified life. Methods for aging of equipment are discussed in the following sections. 4.2.1.1 Aging Oualification By Testing Age conditioning is a process of controlled physical deteriora-tion that will provide an evaluation of the equipment's vulner-ability to aging mechanisms that could affect the ability of that equipment to perform its safety function. Age conditioning O stresses are intended to produce equipment degradation levels that exceed or equal expected in-service degradation. Age conditioning addresses the effects of temperature, vibration and coerational cycling as follows: D 1 D
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D
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_ _ _ _ _ _ _ _ _ _ _ 0:
- 1. Temperature effects on aging are addressed using the form of the Arrhenius model: ,
G,
- s t
g
=t exp -
A Where: , to = Equipment lifetime in service tA = Equipment lifetime at the aging temperature To = Service temperature, OKelvin TA = Aging temperature, OKelvin EA = Activation energy, electron-volts kB = Boltzmann's Constant, 8.617 X 10-Sey/og ) e This model is extremely useful in estimating the useful life of insulating materi>', and other "sof t-goods" materials for which the activation energies are known. The temperature effects on electronic components are often , g-handled using the methods described in Section 2.0 of MIL-HNDBK-217C. WPPSS will use both the Arrhenius and the MIL-HNDBK methods as a basis to derive a qualified life for materials and components that make up the Class 1E equipment, t
- 2. In-service vibration which is determined to have an aging ) g mechanism on Class 1E equipment will be addressed in the test sequence prior to seismic testing. The methods will employ specific standards such as IEEE 382, for which vibration aging methods are described.
- 3. Operational cycling effects are simulated by subjecting the ' O test specimen to the number of cycles anticipated in plant service.
The determination of qualified life is based on conservative engineering analysis which takes into account, as applicable:
- 4. Results of age conditioning
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- 5. Equipment service conditions .
- 6. Existing type test results
- 7. Equipment design data e g
- 8. The equipment maintenance and replacement schedules.
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O 4.2.1.2 Age Qualification by Analysis Using NRC, Military, EPRI Literature O Where there are no aging mechanisms that could affect the ability of the Class 1E eouioment to perform its safety function, the simulated aging test is omitted. This is justified through use of Arrhenius, MIL-HNDBK-217C, EPRI or NRC documentation. q ~ 4.2.2 Radiation An important factor in determining the qualification of Class IE equipment is the potential radiation exposure which the equipment could receive. The radiation dosage described in , Section 3.0 is used to qualify the equipment. Where the " radiation dosage is above the threshold damage level of the equipment, qualification is performed by actually exposing the equipment to a gamma source to achieve the combined Beta / gamma integrated dose. , Where it can be demonstrated that the effects of Beta and/or J < gamma radiation does not degrade the capability of the equip-ment or material to perform its safety function, such as metallic elements, or the threshold damage level is not exceeded, the radiation exposure is omitted from the testing. 4.2.3 Seismic Conditions D The basic principles of seismic qualification are described in IEEE 344-1975, as supplemented by Regulatory Guide 1.100. These principles are applied by the vendors to qualify Class 1E equipment to meet postulated seismic forces. Where required, the equipment is aged and irradiated to IEEE 323-1974 requirements prior to '9 the seismic qualification. Two methods are used for seismic qualification of WNP-1/4 and WNP-3/5 projects: o Combined Analysis and Testing - e Testing 4.2.3.1 Seismic Qualification Using Combined Analysis And Testina 3 This test method involves analysis using a verified (by partial testing) computer model to meet the intent in Section 7.0 of IEEE 344-1975. It is used in cases where: ,, e The equipment mass or size exceeds the capability of the J testing facilities. An example of this would be a section of a motor control center line-uo. The section is seismically tested with the results analyzed and extended to the entire MCC line-up. e Components of a Class 1E system are tested individually D' with the results analyzed and combined for system use. O
!3 v
,
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The main steam isolation valve is an example of this case. The actuator is seismically tested under simulated valve loading conditions; a stress analysis , is perfomed on the valve body. The results of both the , test and stress analysis are then analyzed to show operation capability under the postulated seismic stresses. 4.2.3.2 Testing
-) #
The Supply System employs proof testing in the majority of the seismic qualification programs. The guidance provided in Section 6.0 of IEEE 344-1975 is used by equipment suppliers in qualifying Class 1E equipment. The test sequence includes vibration aging (if applicable, 3 9 see Section 4.2.1.1.2) resonance search (if applicable), OBE and SSE tests.
- 1. Vibration Aging - If required due to equipment location, vibration aging is performed prior to 0BE and SSE testing.
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- 2. Exploratory Test - Exploratory tests are conducted if 1) vibrating aging is required 2) the complete required response spectrum may not be enveloped by the test resaonse spectrum, 3) calculated resonant frequencies are in the frequency range of seismic concern, and 4) the other applicable supoort interfaces cannot be simulated 3 g on the test table. When conducted, the exploratory tests will be at an acceleration level that is intended to excite all modes between 1 and 33 Hz.
- 3. OBE Test - The Operating Base Earthquake (0BE) or a more conservative test is perfomed with the test specimens.
These tests are perfomed at levels expected to simulate ' 8 the earthquake which could occur during the operating life of the plant. Five OBE tests are conducted (minimum) in each of the equipment's three principal axes. Each test input is applied biaxially for a 30-second duration and is designed to envelop the OBE required response spectrum. The equipment is operated during and after the OBE testing ) 9 to demonstrate satisfactory performance of the required safety function.
- 4. SSE Test - The Safe Shutdown Earthquake (SSE) tests are conducted on all test specimens. This test is conducted at maximum levels for which the building structure, safety >
e systems and comoonents are designed to remain functional. A minimum of one SSE test is performed in each of the equipment's three principal axes. Each test is applied biaxially to envelop the SSE required response spectrum for a 30-second duration. O
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_ ] 4.2.4 Operational Simulation During A DBE J Operational simulation consists of applying one or more of the C qualification methods described in Section 4.1 to the Class IE equipment to ensure that it will perform the safety function under the plant-specific envircnmental and seismic conditions. In most cases, the only acceptable fom of operational simulation 3' is by actual test. There are cases, however, where analysis with justification is used. For example, a Class IE valve-body may be analyzed to show that it will perform its safety function during any postulated event. Some equipment is designed to operate before, during, and after 3' a postulated event. Other equipment, such as an isolation valve,
<
is intended to function immediately following the event. Therefore, the Class 1E equipment is tested in an operational condition deter-mined by its intended safety function. If a malfunction is experienced during the testing, the effects of the malfunction are detemined and documented in the final test report. 3( 4.3 Qualification Methods Acolication The methods discussed in Section 4.1 are used in Class IE equipeent qualification. The purpose of this section is to describe how these methods are applied to specific Class 1E equipment. For ease of review and to meet Appendix E or NUREG-0588 requirements, sumary reports of 3 these equipment qualification programs have been prepared. The equipment types selected are: e Switchgear e Valve Operators 3 e Motors e Cable e Connectors e Electrical Penetration Assemblies e Terminal Blocks "3 Appendix A of this document contains the sumary reports for the above identified equipment. Additional si.mmary reports, similar to those provided in Appendix A which will encompass the remainder of the Class 1E equipment will be contained in the FSAR's for WNP-1/4 and WNP-3/5 projects. g 5.0 EQUIPMENT OVALIFICATION PROGRAM IMPLEMENTATION AND DOCUMENTATION This section describes the Supply System Class IE equipment qualifica-tion program implementation and the types of documentation required.
)
The prime objective of the Supply System qualification program is to provide documented evidence that the Class 1E equipment is qualified. 3 The documentation is of such a form that oroof of qualification is maintained and that the plant operations group may use this documenta-tion in perfoming equipment maintenance as necessary. 3o _ - _ .
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l 0 l 5.1 The Supply System Equipment Qualification Prooram i The Supply System Class 1E equipment qualification program consists of following quality assurance procedures already in place. In , #' addition, engineers at the Supply System, the Architect Engineer, , and the equipment suppliers participate in programs that specifically ' address the requirements of the documents mentioned in Section 2.0. The Supply System qualification program includes the specific activities which occur during the construction and operation of the 9; nuclear power plants. These consist of design-related activities, I specification-related activities, bid evaluation, procurement, and operations. During the operational phase, extension of qualified life and design modification become important activities related to equipment qualification. Design Phase } 5.1.1 The Architect Engineer has the primary design responsibility to develop specific infomation related to the Class 1E equipment to be used in the plant. The Supply System fcilows quality assurance procedures in the review of that infomation. The design infoma- g tion developed by the Architect Engineer related to equipment i qualification consists of the following: e Safety function and description e Electrical and mechanical requirements , e Seismic loads e Performance requirer ants under operational phases such as plant startup, nomal plant operation, plant shutdown, Design Basis Event (DBE) and post-DBE.
>S e Environmental conditions anticipated during storage, construction, and operation (including DBE and post-DBE).
e Interface requirements, including definition of the functional and physical interfaces involving structures and systems.
> g' Equipment specifications are reviewed for compliance with the plant design requirements by both the Architect Engineer and the Supply System during the design phase.
5.1.2 Specification Phase
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The bid specifications are prepared incorporating information developed
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during the design phase. In the bid specifications, the following equipment qualification information is included: e Required confomance to IEEE 323-1974. e Required confomance with the qualification standards for the
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O specific equipment being procurred. e Desired qualified life. g
g e Designation of the safety function. 3 e Environmental conditions to which equipment will be cualified. e Range, type, and duration of design basis event environment. I e Operating Basis Earthquake and Safe Shutdown Earthquake N conditions imposed at the equipment location. e Equipment performance requirements. e The reauirement f'or identification of subcontractors, including testing laboratories. , The most important items in equipment qualification are the J requirements contained in the bid specifications. Without proper requirements, great difficulty can be expected in obtaining informa-tion related to equipment qualification. The range, type, and duration of environmental conditions are specifically defined in the bid specifications so that the vendor 3- can supply equipment that satisfies the safety function require-ments. Curves and/or tables depicting in-containment and ex-contain-ment temperature, pressure, and radiation profiles are provided. The bid specification provides floor response spectra on the Operational Basis Earthquakes and Safe Shutdown Earthquakes for O specific equipment-mounting locations. The equipment supplier then is required to develop these criteria in the seismic qualification process. The documentation provided by the vendor for qualification testing includes the following: e Qualification test plan e Test procedure e Test report with applicable analyses, test data, results, and conclusions. 3 Supply System engineers and the Architect Engineer have a review cycle reserved for each of the above items prior to final approval of each vendor qualification program. 5.1.3 Bid Evaluation Phase g After receipt and review of the Supply System bid specifications, l the bidder is required to submit an outline of the equipment qualification program for evaluation. The extent to which the program conforms to the requirements of IEEE 323-1974 and to th? qualification requirements in the specification, partially deter-O mines the selection of the successful bidder. 9" l l
1 O l e 1 5.1.4 Procurement Phase The procurement phase of the design activities at the Supply g System consist of awarding the contract to the selected vendor, ' reviewing each part of the vendor's equipment qualification program, and ensuring that the equipment is qualified in accord-ance with that program. The detailed activities consist of: e Reviewing the complete vendor qualification program for that piece of equipment. ') O e Monitoring the progress of the vendor qualification program. e Reviewing the results of the vendor qualification program. e Establishing a program to maintain and verify qualification 3 8 for in-service equipment. This includes an equipment storage period, as necessary. Each qualification program is reviewed using the Supply System acceptance criteria described in Section 3.3 of this document. Based on the review of the qualification program results, additional ) G requirements may be established for maintenance and replacement to ensure an equipment 40-year qualified life. 5.1.5 Operations Phase Requirements exist to r'inta 9 equipment qualification during g storage, installation, starto, and operation, based on vendor recommendations. These recommendations, along with the qualifica-tion program results, are incorporated into standard Supply System procedures to ensure continued qualification status. Spare parts are procured according to recommendations established by the vendor. 3 g In addition, continued evaluation of the equipment performance is made to extend the equipment's qualified life whenever possible. 5.1.5.1 flaintenance of Qualified Life Initial equipment qualification does not necessarily ensure that # each component of a system will continue to be qualified during its service life. Qualification status throughout equipment service life requires component maintenance and/or replacement. The Supply System procedures identify the minimum maintenance schedules to retain equipment qualifications throughout service
) G life.
5.1.5.2 Extension of Oualified Life The qualified life of certain equipment may be less than the plant design life. In such cases, a replacement program, additional qualification testing, additional analyses supported by testing, ' e or operating history may be used to demonstrate that the equipment can perform its safety function beyond its established qualified life. 9
J Qualification retesting may be performed using sample aged components or by advanced qualification techniques, as they 3 become identified, to extend equipment qualified life. Analyses may be presented to extend equipment qualified life when the Supply System can identify physically measurable parameters that accurately reflect the state of component deterioration. 3 Other methods will be used to extend equipment qualified life if these methods adequately demonstrate that the equipment will perform its safety function for the additional period of time.
, 5.1.5.3 Desion Modifications J <
The wide variety of equipment used in Supply System nuclear projects require that guidelines be established in perfomance of any design modifications. Each equipment type and situation must be evaluated to determine the impact that the design modification would have on the equipment qualification. This evaluation will D determine the extent of any additional qualification required. Where changes affect neither the aging mechanism nor the possible failure modes, requalification is not required. Where there is such an effect, requalification is performed to demon-strate that the modified equipment can perform its safety 3 function for the specific period of time. The techniques described in Section 4.0 (i.e., analysis, type testing, or combined analysis and testing) will also be used in the requalification of design modifications.
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3 5.2 Documentation The Class 1E equipment qualification program contains documentation which demonstrates the equipment capability to perfom its intended safety function under the service conditions in which it must operate. The fundamental criteria for this documentation is contained in the Supply System acceptance criteria, discussed in Section 3.3 of this O document. This section indicates that the document requirements of IEEE 323-1974 must be satisfied in each vendor oualification orogram prior to Supply System acceptance. The infomation develooed by the Supply System Class 1E Qualification Program must be accessible and available to personnel for audits and O available to operational personnel during the plant operation phase. To accompsh this, the Supply System maintains a ' dtem of rc:ords in accordance with 10CFR50, Appendix B. 5.2.1 Vendor Documentation Submitta's_ O The vendor documentation submittals consist of qualification test plans, test procedures, test reports and a final documentation package. Supply System review of this documentation results in approval or negotiation to ensure confomance to the qualification acceptance criteria. g
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O 5.2.2 Documentation Submitted to the U.S. NRC The information that is submitted to the NRC will meet the objectives 'g of the documents identified in Section 2.0 of this recort. These requirements establish the need for these categories of infomation: e Equipment qualification sumary reports and information satisfying Appendix E of NUREG-0588. e Information required by present Regulatory Guides and s
- Standard Review Plans.
e A list of Class IE I&C/ electrical equipment. 5.2.2.1 Sumary Report Infomation_ Example summary reports are provided in Appendix A of this document in res?onse to Appendix E requirements of NUREG-0588. 5.2.2.2 Required Licensing Infomation The standard review plans require that specific information be ) 9 available for inspection by the NRC Staff. This infomation, as described in Sections 2.13 and 2.14 of this doc <1ent, will be ! provided. 5.2.2.3 Class 1E I&C/ Electrical Equioment List
> 0 The Supply System is in the process of developing the Class 1E equipment list. This list contains detailed infomation regarding the equipment and its qualification status. Appendix B, Part I of this docunent contains the definition of the codes and entries used in the equioment list.
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The infomation provided in this equipment list may be sorted in many ways to obtain reports which allow correlation in such areas
. as equipment location and qualification methods. This list will .
be submitted as part of the FSAR for NRC Staff review. 5.2.3 File System ) , The Supply System maintains files in accordance with established Quality Assurance procedures which conform to Appendix B, 10CFR50 requirements. These files include: O e Equipment specifications e Test plans and acceptance criteria , e Test results ! e Analyses and other documentation required to support any assumptions contained in the recorts o Summary reports of the qualification proorams 'e e Correspondence related to each qualification program. , l l
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6.0 CONCLUSION
)c This report has been provided by the Washington Public Power Suoply System to illustrate the Supply System's methodology in complying
,
l with IEEE 323-1974, or its daughter standards that are supported by regulatory guides and/or NRC documentation. ' The Supply System Equipment Qualification Program ensures that b all safety-related I&C/ electrical equipment has been identified, that posNiated accident environments have been defined, and that an equirment qualification program has been developed to demonstrate the required equipment performance within the specified service conditions. ) D l D D D b l b , N l
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3 J APPENDIX A ) SAMPLE
SUMMARY
REPORTS OF EQUIPMENT QUALIFICATION ) PROGRAMS OF CLASS 1E EQUIPMENT
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D D 3 J J'
e 1/4-47-QS-1 CLASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM
SUMMARY
e r-I. Equipment Identification Type: SKV, 250MVA, 1200 AMP Switchgear Manufacturer: Gould, Inc. Model No.: 5HK-250 0 II. Equipment Classification Safety Function: Operate on demand and where required to maintain continuity of a circuit during the DBA conditions (LOCA) and earthquakes if no electrical fault or GD overload condition exists. Should a short circuit or other circuit overload condition occur during the DBA er earthquake, open and reclose. DBA Exposures This equipment is subjected to Operating Basis Earthquake (OBE) and Safe Shutdown Earthquake gp (SSE) conditions. Other adverse environmental conditions do not exist in the location of this equip.nent. Time to Fulfill Safety Function: The equipment is required to carry rated current and open any circuit with an overload or fault gg condition during and after a postulated LOCA, OBE or SSE. III. Equipment Description The switchgear equipment is composed of the enclosure, primary circuit ID components, circuit breaker and other components such as meters, relays, switches, transformers, and interface components. IV. Qualification Environment Normal:
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Temperature: 55 F to 85 F [) Pressure: Slightly Positive Relative Humidity: 35% to 50% Radiation 10 rads / year Abnormal: Temperature: 85 F Pressure: Slightly Positive Relative Hamidity: 40% - 10% () Radiation: 10 rads / year DBE: Operating Basis Earthquake (OBE) and Safe Shutdown Earthquake (SSE). V. Summary of Qualification Plan !
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A. Aging: 1 i The objective of the qualification plan is to satisfy the ' criteria contained in IEEE 323-1974 for the WNP-1/4 plant specification.
(
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1/4-47-QS-1 V. Summary of Qualification Plan (cont) Thermal: A thermal aging analysis is performed to show that thermal aging is not a factor which prevents d> I the equipment f:om perfonning its safety function during seismic events. Where analysis indicates unacceptable effects, thermal aging is performed prior to seismic testing. Radiation: An analysis was performed which shows that the gg WNP-l/4 radiation parameter (410 rads) for this I equipment is not a factor which would prevent the equipment from performing its safety function during seismic events. Vibration: Self-induced vibration and vibration from nearby gg equipment is not a factor which would contribute ) to the aging of this equipment. Therefore, vibration aging is not performed on this equip-ment. Operational: Components susceptible to operationally induced failure mechanisms are cycled a conservative ) II number of times to represent the design life cycles. Components of static design and those whose design life cycles are a small fraction of it apability are exempted. B. Seismic: The basic equipment in the as-produced condition is ) GD subjected to five OBE and one SSE (minimum) random, multifren.uency, biaxial excitations in each of two directions. The equipment is monitored for proper electrical functioning during excitation. Locstions of components (protective relays, current transformers, etc.) are monitored for excitation levels and compared ) dp to the qualification data for the cemponent. C. DBA: LOCA not applicable. MSLB not applicable. D. Other: Design Tests: Basic equipment in the as produced condition is subjected to flanmability, dielectric, continuous ; gg current, load current switching, short time current carrying, short circuit interruption and momentary current tests. VI. Summary of Test Results II The analyses and test results show the switchgear will perform its function under the conditions specified in Part II of this report provided the periodic maintenance of Section 9 and parts replacement schedule of Section 7 of Reference 1 are adhered to. This switchgear equipment is an assembly of two types of components. ' The first type comprises the " basic equipment" which includes ID standardized primary and secondary ccmponents which perform the basic function of switchgear equipment. The second type of GD'
S 1/4-47-QS-1 VI. Summary of Test Results (cont) gp components furnished with switchgear is the "vags ible assortment" l of control, instrumentation and protection equipment. l A. Aging - Thermal & Radiation (N/A): The analysis was divided into i two phases. The first phase addressed the " basic equipment" and identified the possible failure modes and their effects gg on systen operation. Further studies and analyses showed (through Arrhenius projections of existing laboratory and operational data, and application of conductive coatings to prevent ionizing of air gaps in encapsulation) that most of the failure modes could be prevented from occurring in a gervice environment of 40C and a cumulative radiation q, of 10 rads. Data used for the Arrhenius projections show satisfactory operation for greatly extended periods above the possible 38C environment. The second analytical phase (" variable assortment") included a review of manufacturer's data and reports, and research of data on basic materials and techaiques applicable to the II " variable assortment". These analyses showed projected operating life of 40 years under the normal and DBE conditions for most of the items. They also identified those with a less than 40 year life and quantified the required replace-ment time to ensure a margin for safe operation. Details of these analyses, on going tests, a list of the " variable (D assortment" and reference documents used in assessing them are in Reference 1. Operational: Circuit breakers met all performance criteria after the 10,000 cycles of operation which greatly exceed the 1200 operations requirements. 4 B. Seismic: A sample set of the " basic equipment" in the as produced condition was subjected to five OBE and two SSE biaxial RRS in two axes. All circuits were electrically loaded, operated and monitored for proper functioning. All equipment cperated satisfactorily before, during and after the seismic exposure. Margin of 4% to cver
) 31% on the SSE RRS was provided.
Accelerometers were placed at strategic locations and outputs recorded during the vibration runs. The data was then used to evaluate the seismic withstand capability of the " variable assortment" equipment. b) Where manufacturers' data showed the equipment would satisfactorily meet the vibration environment of its location in the switchgear structure it was considered qualified. Where data was insufficient, vibration testing was performeC to the spectrum of the equipment location. All of this equipment is qualified by one of these methods. The list of these " variable assortment" D
1/4-47-OS-1
.
B. Seismic (cont) equipment and how qualified seismically for this program , GD are in Reference 2. A typical test response spectrum with the required responses is given in Figure 1. The supplier qualification report presents experimental and I gp analytical findings which indicate the.t anticipated environ-mental effects during a qualified life period required for WNP-1/4 do not put the equipment into a condition during a seismic event other than when new. These findings, and an approp-riate component replacement program, permit seismic verifica-tion testing of new components. gg Other - Design Tests: Requirements of all tests were satisfactorily met. The recommended maintenance or adjustments were made at the required intervals. See Reference 1.
) 8 VII. Modifications to Equipment None VIII. Attrchments Figure 1, Typical Se smic Test Response EDectrum ) GD IX. References
- 1. Gould Report 33-51659-QS Revised 3-28-79. Qualification Sunnary Report SrV Switchgear Contract 47, Transmittal 60A.
) GD
- 2. Gould Report 33-51659-SS, dated 9-78. Seismic Certification for Class 1 Electrical Equipment Contract 47, Transmittal 75.
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} 1/4-55-QS ) CIASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM
SUMMARY
I. Equipment Identification Types Modular Type Penetration, 600 Volt Power, Control
& Instrinnentation.
Manufacturer: Westinghouse Model No.: Prototype Modules Include Serial No. 328; small size low voltage cables, Serial No. 261; larger size low voltage cables and } Serial No. 246; two tri-axial cables II. Equipment Classification Safety Function: The penetrations function electrically to carry signals to and frota safety devices ) and current to power these devices within the containment. They also provide a pressure barrier to prevent any gases from leaking from the containment during normal plant operating conditions, during Loss of Coolant Accident (LOCA), Main Steam Line Break (MSLB) Operating Basis Earthquake (OBE) and Safe Shutdown Earthquake (SSE). DBA Exposure The penetrations are located and mounted on the containment liner-wall and are exposed to LOCA and MSLB conditions. J Time to Fulfill Safety Function: The penetrations must function both electrically and as a pressure barrier for the period of time that the DBA or earthquake is postulated to exist, the ] longest being the LOCA which is postulated to exist 100 days. III. Equipment Description The electric penetration is a device which, when sealed into its aperture in a bulkhead, allows for the passage of electrical circuits }< and information through the wall of a nuclear containment vessel without compromising the integrity of the containment vessel's pressure boundary. Its double module seal allotes for the continuous monitoring of the module's gas leakage rate. Connectors, terminals, terminal blocks and wire are also part of the complete plant instal-lation. Summaries of their qualification follow as separate documents. )y ]L
.
'
s, 1/4-55-QS-1 IV. Qualification Environment . Normals Temperature: 55F(13C) to 95F(35C) Humidity: 20%to80g gg Radiation: 1.71 x 10 ' Abnormal: See Accident and DBE Accident: LOCA: Temperature: See Figure 2 Pressure: See Figure 1 Radiation: 1 x 10 rads integrated over i II accident and one year following. Spray: Continuous for 48 haurs and intermittant for additional 98 days, to consist of 2100 ppm boric acid with Sodium Hydroxide to pH of 9-11. < GD MSLB: Temperature: See Figure 2 Pressure: See Figure 1 DBE Seismic: See Figure 3 O V. Summary of Qualification Plan The objective of the qualification plan is to satisfy the criteria contained in IEEE 317-1972 for the WNP-1/4 plant specifications. A. Aging: ) gg: Thermal: Develop Arrhenius plot by linear regres-sion analysis of test data and determine a time and temperature for accelerated aging of the penetration modules to a 40 year life at 70C through extrapolation of
; g, that plot.
Radiation: Samplestogeexposedtoacummulativedose of 1.1 x 10 rads from a Cchalt-60 source. Vibration: Self-induced vibration and vibration from nearby equipment is not a factor which would ID contribute to the aging of this equipment. Therefore, vibration aging is not performed on this equipment. Operational: Normal operation produces heating effects which are well below the 70C value considered (p in the thermal aging portion of this program. Thus, operational aging is included in the thermal aging, above. B. Seismic: The sample is to be subjected to biaxial random vibration with a frequency spectrum of 0.7 to 100 gg Hertz. The input shall be applied to the sample six times (five CBE and one SSE) in each of four biaxial directions. O
,
I 3)n' 1/4-55-QS-1
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C. MSLB:LOCA: See Figures 1 and 2.
$) D. Other: Temperature extremes' cycling. Samples shall be placed in an environment of -34C for one l and one half hours, 23C for four hours and then one and one half hours at 93C with 95%
' humidity. This le to be done for five complete cycles.
- $)
Mechanical shock. The samples shall be sub-jected to a sand drop test twice from a height to induce a force in excess of one l and one quarter g. ! [) Thermal cycling. Samples shall be subjected to 120 cycles between 21C and 77C at a rate of change of 28C per hour. Gas Leak Rate. Samples shall be pressurized with helium to 75 psig and the pressure to be
-
monitored throughout testing to determine leak rate. l l Electrical Tests. Continuity, dielectric strength, and insulation resistance are to be performed at the start, during cycling I and aging, DBA, and following short-circuit
) tests.
Rated Short-Time Over Load Current Test The modules shall be connected so that same i size wires are connected in such a manner [) as to allow the required current to flow through the maximum number of cables. The test on module, S/N 328 (cable sizes
#12, #10, and #4), to be performed as follows:
using hesting tape, heat the cables to an [] ambient of 122F(50C). Apply rated current plus margin (5%) through the three cable sizes, the temperature being recorded after stability is reached. At this point a current seven times rated current plus margin to be applied to the cable size under test for a ten second duration. The maximum cable {) temperature is to be rscorded. The test on module, S/N 261 (cable size #2,
#1/0, 250 KC MIL, and 350 KC MIL), shall be
- performed by heating one cable of each size i
! to approximately 194F(90C) and then applying )
) seven times rated current plus margin to the i
cable size under test for ten seconds and ! recording the maximum temperature. h) l l
1/4-55-QS-1 Short-Circuit Current Duration Test (per-formed next after the Rated Short-Time Overload Current Test). gg The modules, are to be installed and secured in a test mounting collar in the same manner as they would be sealed into a bulkhead. Three cables of the same size are to be fastened together at the inboard side of the module and their extensions on the outboard side secured s II to the three phase power source. Heat the wires to be tested to a minimum of 194F(90C) prior to applying the short circuit current. Af ter programming the power source to produce the required current for the proper number of ) GD cycles, the unit shall be turned on, thereby delivering the faulted current to the cables. The maximum temperature attained by the tested cable size due to the short circuit current shall be recorded. At the conclusion of the test performed on the first triad of wires, the , gp second group shall be connected and the test repeated. This procedure is to continue until all the required cable sizes of both modules have been tested. Installation welding. The module shall be welded ) gg to a linear nozzle and the developed tempera-tures measured at the conductor insulation and the epoxy seal. VI. Summary of Test Results The analysis and test results sh the penetrations will perform I their function under the condita as specified in Part II of this report. The combination of terminals, terminal block and wire in an electrical enclosure is being evaluated for performance in MSLB environment. Aging: II Thermal: Cast epoxy penetration seals were tested at four temperatures from 150 to 200C and using linear regression analysis an Arrhenius curve was developed that showed 99.7% of the seals will have a life greater than 342 years at 70C. gp Based on this curve the samples were aged at 150C for 100 hours to simulate 40 year life at 70C. This gave a margin of 35C over the maximum normal service temperature. Radiation: The samples were exposed to gamma radiation from gg a Cobaltg60 source for 220 hours at a rate of 0.5 x 10 rads per hour. The samples were 8 rotated periodically to obtain a dose cf 1.1 x 10 rads. This gave a margin of 10%. O
D
- 1/4-55-QS-1 Seismic: The penetration modi 21es were pressurized into g 64 psig, energized with 21,000 volts de and then subjected to biaxial random vibration with a frequency spectrum of 0.7 to 100 Hertz. The input was applied six times (five CBE and one SSE) in each of four biaxial directions. Margin of 50% or more was provided between required levels and the test levels. See Figure 3 for SSE vertical response (worst case requirement). There was no visual or apparent evidence of mechanical
, damage er deterioration of the penetration as ' a result of the reismic vibration. See reference 3. b DBA: LOCA: The three modules were installed in th'e steam chamber, and each conductor was attached to its power supply. The power supplies were adjusted to deliver the following voltages and currents to the respective cable during the test: h !
#12AWG and #10AWG
#4AWG and #2AWG 20 90 Amps Amps at at 600 600 Volts volts i #1/0 125 Amps at 600 volts l 250 KCMIL and 320 Amps at 600 volts l
350 KCMIL The penetrations were then exposed to the Design t Basis Accident Pressure and Temperature profiles ! shown in Figures 1 and 2. A chetaical solution I was sprayed intermittently on the modules, at a rate of 0.15 gallon per minute for a total of 81 gallons during the 30 day period. The first 63 gallons of solution (7 hours of spray, 0.15 gal / min) consisted of 4000 ppm of boric acid buffered with sodium hydroxide to a pH of 8.5. This exceeds the WNP-1/4 requirements and pro-duces a more severe test. The remaining 18 gallons of spary consisted of 2100 ppm boric acid buffered to a pH of 9-11 with sodium hydro-O xide. This solution was consistent with WNP-1/4 requirements. l ! Insulation resistance readings were taken daily
- throughout the test. At the conclusion of the
! LOCA testing, the modules weg leak tested. The -2 p leakage measured at 1.1 x 10 std. cc/sec (1 x 10 std cc/sec, maximum, was specified).
The insulation resistance readings were within acceptable limits. The dielectric strength test was performed and all cables passed the test after cycling and aging. All cables passed the test after the design basis accident with the exception of cables 10 and 13 in Module Serial No. 328. These cables, along with #15, were used to conduct the short circuit current duration test and were 2 stressed beyond the IPCEA maximum recommended I t 0
-_. - --
1/4-55-QS-1 value of 5.6 x 10 by 46%. This over-stressing could have contributed to this failure; however, one of the overstressed cables and four other #10 cables satisfactorily met the test. Sometime after 41 hours into the 45 the DBA and prior to 71 tours, borated water and condensate accumulated in the chamber putting the penetrations under wa ter. Several of the cables failed the insulation resistance at 71 hours. The drain valve was adjusted and all but the triax cables had recovered by the 97 gp
)
hour test. This is not detrimental a the penetrations are located above any flood line and the triax cables need to operate only at the beginning of DBA to signal its occurrence. A margin of 60F was provided throughout most of the profile. gg MSLB The LOCA test exposure is used to demonstrate capability to met MSLB environment. A margin of 50 psi is provided over the maximum pressure. A margin of 55F is provided over the maximum temperature calculated to be transferred to the II penetration. The calculation was based on the methodology of Appendix B of NUREG-0588 (Aug.
- 79) see Reference 4. The result of all post LOCA exposure tests were satisfactory.
Other: The results of the Temperature Extreme, Mechanical Shock, Thermal Cycling, Gas Leak i GD Rate, Continuity, Dielectric Strength, Insula-tion Resistance, Rates Short-Time Overload Current, and Short Circuit Current Duration Tests were satisfactory except for Dielectric Strength as discussed under LOCA results. See Reference 1. (p Welding of the modules into place was
-
satisfactorily demonstrated. See Reference 1. VII. Modifications to Equipment O None VIII. Attachments Figures 1, 2 and 3. II IX. References
- 1. Qualification of Modular Type Electrical Penetrations, Westinghouse Electric Corporation, Report No. PEN-TR-77-59, July,1977, WNP-1/4, Contract 55, T-33. This transmittal also contrins the following repcrts:
O o 75-7BS-BISAL-R2; Research Report o PEN-ABE-1-74-4; Module Ca'acity Test Report o PEN-TR-76-47; Test Repcet on simulated field installation welding of an electrical penetration module type fitting to a 12 inch nozzle.
'
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, _ --. . 1/4-55-QS-1
.
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- 2. Letter - UEWP-78-007.1 B. D. Redd, Project Engineering Manager to WNP-1/4 Project Manager, J. P. Thomas, Containment Electrical Penetrations, January 13. 1978.
- 3. PEN-TR-77-107; Report of Seismic Vibration Testing of One Medium Voltage Penetration, Revised 4-5-78.
- 4. Temperature transient response in safety-related equipmwnt following MSLB, UEWP-80-179.
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1/4-55-QS-1A l
. CLASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM
)
SUMMARY
l- I. Equipment Identification . ! Type High Temperature Terminal Lug ) Manufacturer: Model No.: AMP Inc. 53000 Series l II. Equipment Classification i ! Safety Function: The terminations carry signals to and from safety devices and current to power these i devices within the containment, i ! DBA Exposure: The terminations are located in teminal boxes outside the containment and are exposed to HELB. Time to Fulfill Safety Function: The teminations must function continuously for the period of time that the HELB or earth- , quake is postulated. Also, the terminals must l function throughout a postulated 100-day LOCA
- period, but are not exposed to the associated environment.
III. Equipment Description The terminal lugs are of polyvinylidene flouride (KYNAR), pre-l insulated type, which provide the interface connection for wires I and terminal blocks. ) l IV. Qualification Environment > Normal Temperature: 55F(13C) to 100F(38C) Pressure: Atmospheric Relative Humidity: 12 to 70% Radiation: 10 rads / year ] Abnormal: Temperature: 10F(-12C) to 130F(54C) Relative Humidity: 5 to 95% DBA: HELB V. Summary of Qualification Plan The objective of the qualification plan is to satisfy the criteria contained in IEEE 323-1974 for the WNP-1/4 plant specifications. D D l
.- . . . .- . - . -
, _-
,!
1/4-55-QS-1A A. Aging: Thermal: Conduct an analysis to determine expected life and define a time and temperature for II accelerated aging to 40 year life at 70C. Radiation: Samples tg be exposed to a cummulative dose of 2 x 10 rads from a Cobalt-60 source. Vibration: Self-induced vibration and vibration from GD nearby equipment is not a factor which would contribute to the aging of thi. equip-ment. Therefore, vibration aging is vat performed on this eculpment. Operational: The effects of normal operation produce gp heating effects which are included in the thermal aging portion of this program. B. Seismic: Seismic vibration is not a factor which would produce common mode failures due to the mass of the terminals and the mechanical restraints placed , gg on the wiring. C. LOCA, MSLB: See Figure 4 of this summary report. This profile the temperatures and pressures anticipated for a HELB outside of containment. II D. Other: Out-gassirg, flammability, tensil strength, axial load and voltage drop are among the tests performed. VI. Summary of Results The analysis and test results from the LOCA testing (Figure 4) indicate that these terminals will perform their safety function in much more ID severe environments thatn required by ex-containment applications. The WNP-1/4 HELB requirements are currently being defined, however, it is not anticipated that the environment produced by an HELB will approach the severity of the LOCA/ Chemical Spray testing performed on the terminals. O Aging: Thermal: Tests were conducted to determine the activa-tion energy of the insulation by a thermo-gravimetric analysis. From this it was determined the terminals would have an gg equivalent life of 3.35 million years at 70C when aged at 163C for 120 hours. Samples aged at 163C for 120 hours showed no deterioration of the insulation. 8 Radiation: Samples were subjected to a dose of 2 x 10 rads by exposing to a Cobalt-60 source. U. , These samples were then exposed to the LOCA 8 profile. This gave a margin of over 1 x 10 . j l O l l
O r 1/4-55-QS-1A DBA: LOCA: The radiation aged samples were subjected ID to the temperature, pressure, spray profile of Figure 4. All performance requirements were met after exposure. The sanples were
. not thermally aged prior to this test due to the long life shown by the analysis.
(D The satisfactory performance assures proper operation in ex-containment environments. Other: The results of all of the other tests were satisfactory. VII. Modifications to Equipment None VIII. Attachment Figure 4 gg IX. References
- 1. Engineering Test Report GPR 575-98, AMP, Inc., September 9, 1976.
- 2. Engineering Test Report of AMP, Radiation Resistance PIDG II Terminals. GPR 575-99, April 16, 1974.
- 3. Product Specification for PIDG Terminals, AMP, Inc., Peport No.
108-11023, May 3, 1974.
- 4. Radiation Exposure Test Data Summary, AMP, Inc., Report No.
GD 3425-200 (1-14), June 13, 1975.
- 5. Product Bulletin, Nuclear Terminals and Splices, AMP, Inc.,
Report No. 309-1, 1975.
- 6. Analysis of PIDG Thermal Aging conducted by AMP, Inc., Wyle
]) Laboratories Report, Report No. 44275-1, December 19, 1978.
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1/4-55-QS-1B CLASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM n
SUMMARY
.V 4 I. Equipment Identification Type: Electrical Cables Manufacturer: Rockbestos Company () Model No.: Firewall III II. Equipment Classification Safety Function: The cables carry signals to and from safety devices and current to power these devices
'
within the containment during normal plant
' C) ( operating conditions, during Loss of Coolant Accident (LOCA), Main Steam Line Break (MSLB).
DBA Exposures The cables are located in the containment penetrations with the penetration " pigtails" exposed to LOCA and MSLB conditions. f () Time to Fulfill Safety Function: The cable must function for the period of
,
time that the DBA or earthquake is postulated to exist, the longest being the LOCA which is postulated to exist 100 days. 1 () III. Equipment Description (1) A single conductor with 30 mils of flame retardant, irradiation cross-linked polyolefine insulation. () (2) Inner insulation of polymer LD covered by a layer of either radiation cross-linked mcdified polyolefin or radiation cross-linked cellular polyolefin (both types were tested) and an outer jacket over the shield of radiation cross-linked, flame retardant, non-corrosive, modified polyolefin.
" () IV. Qualification Environment Normals Temperature: 55 F to 95 F Relative Humidity: 20% to 80%
Radiation: 428 rads / year
. C) ' Abnormal: Terperature: 135 r (nax.)
Relative Humidity: 20% to 80% Radiation: 428 rads / year
- O c) ' .
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1/4-55-QS-1B Accident: Temperature: See Report 1/4-55-QS-1, Figure 2 l LOCA: Pressure: See Repogt 1/4-55-QS-1, Figure 1 Radiation: 1.2 x 10 rads integrated over accident and one year following. Spray: Continuous for 48 hours and intermittant for an additional gg 98 days, to consist of 2100 ppm ) boric acid with sufficient sodium hydroxide buffer to achieve a pH of 9-11. MSLB: Temperature See Report 1/4-55-QS-1, Figure 2 II Pressure: See Report 1/4-55-QS-1, Figure 1 i V. Summary of the Qualification Plan The objective of this plan is to satisfy the criteria of IEEE 383-1974.
) GD A. Aging:
Thermal: Develop an Arrhenius projection to deter-mine a time and temperature to accelerate age the cables to a 40 year life. Age cables to those conditions. > (p Radiation: Samples are t be exposed to cummulative 8 doce of 2 x 10 rado from a Cobalt-60 source. Vibration: Self-induced and vibration from nearby 3 gp equipment has no aging effect on the cables. Operational: Cable operation produces thermal aging ef fects, which are determined from the Arrhenius methods used above. , g, B. Seismic: Seismic events produce effects only at the interface connections. The interface is qualified separately and not included in this program. C. LOCA, MSLB: See Figure 5 of this summary report. O D. Other: The flame test requirement of IEEE 383-1974 was satisfied for the cross-linked polyolefin insulations through testing the coaxial unit to paragraph 2.5 of the IEEE standard.
~'
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() n 1/4-55-OS-1B VI. Sununary of Results
-) '
The analysis and test results show that.the cables will perform their function under the conditions specified in Part II. Aging: Thermal Regression line test data was assembled according to IEEE 101-1972, and an Arrhenius () plot was developed for this insulation. The plot showed that 650 hours at 150 C simulated a 40 year life in an ambient temperature of 90 C. Or, that 135 hours at an aging temperature of 150 C would simulate a 40 year life in an ambient
- C) temperature of 75 C.
The single conductor cable was aged in an oven temperature of 150 C for 1300 hours. The coaxial sample was aged 168 hours in an oven temperature of 150 C. Thus, the
' () thermal aging performed on these samples enveloped the Arrhenius curves with margin-to demonstrate the life of the insulation is well beyond the 40 year environmental conditions of the WNP-1/4 plant.
Radiation: The thermgily aged samples were subjected
- ()
to 2 x 10 rads by exposing them to a Cobalt-60 source. This envelopes the WNP-1/4 requirement with adequate margin. DBA: i () LOCA: The radiation and thermally aged samples MSLB were then subjected to the temperature,
, pressure and spary conditions described by Figure 5 of this summary report. Following exposure, all samples passed the voltage withstand test while wrapped around a 40X-C) cable diameter mandrel and immersed in tap water. 2000 volts was applied to the coaxial cable and 2400 volts to the single conductor unit. Comparison of Figure 5 with Figures 1 and 2 of the summary report 1/4-55-QS-1B indicates that margins of 50 psig and 60 F
) () were achieved. The chemical spray, combined with the high pressure margin, indicates a nore severe postulated accident conditions. 4
- () ' Other: The flame testing performed on the cross-linked polyolefin dinsulation demonstrates this material's ability to with-stand the IEEE 383-1974 test.
u i
O 1/4-55-QS-1B VII. Modifications to Equipment None a VIII. Attachments Figure 5 IX. References
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- 1. Report Qualf.fication of Firewall II Coaxial Constructions for class 1E Service, dated 1-18-78.
- 2. Report: Qualification of Firewall II Class 1E Electric Cablets, dated 6-7-78.
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1/4-87-QS-1 CLASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM-C,
SUMMARY
I. Equipment Identification
- Type: Self-contained Hydraulic Actuator
- () . Manufacturer: Anchor / Darling valve Company Model No.: Prototype Unit II. Equipment Classification Safety Function: Actuate main steam and feedwater isolation
- () valves under normal, abnormal design basis event and post design basis event conditions.
DBA Exposure: The valve actuators are subject to MSLB outside of containment environment. The actuators
- are required to isolate the containment ar' main feedwater system.
() Time to Fulfill Safety Function: The safety function requires the valves to close within 1.8 to 3 seconds upon receipt of activation signal. ' () III. Equipment Description The prototype hydrualic actuator equipment is composed of hydraulic components (cylinder, accumulator, valves) and pneumatic conponents (pneumatic reservoir, solenoid valves, in-line check valve, pressure transducer), and interface components. The electrical components
- () are described in Paragraph VII under Modifications.
IV. Qualification Environment Normal: Temperature: 55F (12C) to 85F(30C) Pressure: Atmospheric l () Relative Humidity: 40%to70g Radiation: 12.5 x 10 rads / year Abnormal: Temperature: 10F (-12C) to 130F(54C)
- Relative Humidity: 5% to 95%
. () Accident: LOCA: Not applicable (see Section ' III, above). MSLB: Temperature: 420 F (Max.) Relative Humidity: 100% 6 Radiation: 2 x 10 rads (TID) Pressure: Slightly Positive
)
DBE: Operating Basis and Safe Shutdown Earthquake.
.
--._ . - -
g a 1/4-87-QS-1 V. Summary of Qualification Plan The qualification plan is to satisfy the objectives of IEEE ,3 GD 323-1974, IEEE 344-1975 and IEIE 382-1972.
.
A. Aging: s Thermal & The deterioration due to environmental Radiation: exposure is judged to be insigificant gg for metallic components. Therefore, no environmental aging will be performed on components, sub-assemblies, or parts consisting of metallies only. Environ-mental aging effects must be taken into account for all non-metallic components. gg An aging tempertaure of 250 F (120 C) will be used for all non-metallic components. The actuator supplier establishes 122 F (50 c) as the " normal" ambient temperature, which is well above WNP-l/4 requirements. Based on these values, the actuator non- I II metallies were aged at 250 F for 13.2 days to simulate five years life in a 122 P ambient. The m7nimum radiation dose the valve actuator will experience (based on 40 years ) GD service with 50s margin on a 2 Mrad accident dose) ic 5 Mrads. A major portion of the
-
non-metali!c components in the actuator system consists of elastomeric "O" ring type seals. Only three (3) varieties are present: Buna N (Nitrile), Viton (fluoro- ) (p carbon), and Ethylene Propylene; and they will be irradiated as components, separate from the actuator system. The maintenance / replacement period for the actuator's non-metallies is ten years so > gg the qualification deae will be 3 Mrads using a 25% margin un the accident dose. Shielding effects will be taken into consideration during the irradiation of the elastomers to account for the shielding that exists in actual usage. II separate sets of non-metallic components or sub-assemblies and parts containing these components will be irradiated as defined above and following irradiation , will be temperature aged as also defined GD above. O
l' g .- 1/4-87-QS-1 These components will be introduced into the actuator active control system after the initial functional test (described below). Vibration: Considered during the operational test below and seismic test described in Paragraph V-B.
, operational: It is anticipated that no more than 700 l full-stroke cycles and 1000 exercise cycles will be required of the actuator ! ' while instal 1ed for 40 years in any nuclear power plant. A total number of 800 full-stroke cycles will be applied on one control side--the active one. This I accounts for an additional 100 total cyc.es providing the necessary margin-- in this case 14%--to meet the objective of IEEE 323-1974. A total of 1200
- exercisa cycles will also be applied to
! the active control side, thus providing an additional 200 cycles, or 20% margin, to meet the objective of IEEE 323-1974. All cycles will be performed using the active control system and the active accumulator, where applicable. AC and DC solenoids will be included in the cycle aging process. They will be changed such that half the aging cycles wif.1 be with AC and half with DC solenoid valves. All cycles will be run at a minimum temperature of 122F. Saturated steam mixed with ambient air vented to atmosphere will produce a relativo humidity in excess of 90% during these cycles. Humidity: See the operational test. i Other: The actuator will be functionally tested l prior to and after the radiation exposure / thermal aging test. The actuator will again be functionally tested after the operational test. During each of these functional tests, the hydraulic actuator will be fully stroked (a) using the pump and the active AC controls. Then it will be exercised using the active DC controls. Stroking, exercising and accumulator charging times will be checked and recorded. Bucking cylinder closing pressure will be checked and recorded for all closing strokes at the fully closed position. L
- - - - _ . _ . . , _ . _ - . __ . - . . , _ - . _ _ . _ - , , - . _ . - . . _ _ . _ _ .
,
1/4-87-QS-1
- 1 1
B. Seismic: The test program will consist of a dynamic evaluation test to determine natural frequencies, biaxial random multifrequency testing, and q ID sine beat tests. C. DBA: MSLB: The qualification actuator will be subjected to an accident condition as described in Figure
- 1. The actuator will be actuated at each point as noted on the graph using the active controls 3 (p
only. Each actuation will be performed by using one accumulator to extend the actuator . rod and the actuator pump to retract it. VI. Summary of Test Results
') GD The results of the tests show tha: the valves will perform their safety functions under the conditions described below. These valves, with periodic maintenance and component part replacement, are qualified for a 40-year service life.
A. Aging: ) gg Thermal & Non-metallic components and sub-assemblies Radiation: of the prototype actuator were subjected to temperature and radiation aging. The temperature was held at 250F(121C) for 13.2 days. This is equivalent to 17 years at 90F and gives a seven year margin over ' II the 10 year qualified life. Other identical components were uniformly exposed to a Cobalt-60 source for a period of time that yielded an air equivalent dose of gamma radiation at 2.5 Mrads. VI.
'
(D After the radiation exposure and temperature aging, the components were functior_ ally tested under a simulated load including full-stroke cycling. The functional tests included exercise cycles which were 10% of the full-stroke cycle using the actuator system pump i (p as a power source. The tests showed no indications of degradation. Vibration: Vibration was considered but the extent to which the seismic tests were conducted (32 tests compared to the IEEE 344-1975 gg requirement of 12) more than meets the minimum requirements. See Paragraph VI-B below.
'
GD 9
_ _ . _ O 1/4-87-QS-1 Operational: System cyclic aging tests consisting of 800 full-stroke cycles and 1200 exercise C) cycles which provide a 40-year qualified life including margin, were conducted. The tests were run at a minimum tcmperature of 122F(50C) , which was 32F margin above maximum normal postulated service condition for WNP-1/4, and a relative humidity in () excess of 90%. The test time complied with the cycle aging requirements without compromise to mechanical or electrical integrity.
! "'
r3 Humidity: The humidity tests were successfully run during the operational tests above. Other: None B. Seismic: The seismic test program consisted of a dynamic evaluation to determine natural frequencies, biaxial
. ). '
random multifrequency testing, and sine beat tests. The program demonstrated that the specimen possessed sufficient structural integrity to withstand the pre-scribed seismic environment to perform its intended safety function.
' () The test program included of a dynamic evaluation using the frequency range of 1-40 Hertz to determine natural or resonant frequencies.
There were five (5) random multifrequency tests at the CBE level and two (2) below. Next, two (2)
- C) more' random biaxial tests were conducted at the same orientation but one was at the SSE level and one beJ ow. Seven (7) sine beat test runs were made
(=till in the same orientation) . The oriontation was then changed 90 and the nine (9) random oiaxial tests were repeated, three (3) at below OBE level, five (5) () at OBE level and one (1) at SSE level. Finally, under this second orientation, the seven (7) sine 1 beat test runs were repeated. Margins of 83% or more was provided on the SSE RRS except below 1.5 Hz due to test equipment limitation.
; () See Figure 2 (Attachment 5) for typical response spectra.
, During the OBE tests the specimen was in the open ' position. During the SSE tests; the specimen was operated in the emergency closing operation. During the sine beat tests the specimen operated successfully l () - in the emergency closing operation one (1) time at each test frequency. The TRS data was analyzed at 1/2, 1, 2, 3, and 5 percent damping. () '
. . . - . - -_ ,.
C 1/4-87-QS-1 These tests amply qualify these actuators to the required service (the associated piping systems have been shown through analysis to transmit less ' gp than 3g) as the OBE and SSE tests envelop the 3g limit. Seismic analysis of the terminal box was successfully conducted verifying that the terminal box mounts would survive the design basis earthquake to which g the actuator would be subjected. C. DBA: HELB The prototype actuator, with aged components, instal-led, was subjected to accident qualification testing. Saturated steam was used to attain a peak surroundings temperature of 450 F according to the time / temperature
'
profile shown in Figure 1. The actuator closing times remained within acceptable limits throughout the simulated DBA testing. The testing was performed with the actuator sur-rounded by an " ambient box". Thus, no pressure restrictions existed and saturated steam was pro- ) II duced. This approaches the WNP-1/4 pressure requirements for HELB accidents involving main steam line breaks in the main steam isolation valves. D. Other: None
>S VII. Attachments
- 1. Figure 7. - Main Steam /Feedwater Isolation Valve Accident Temperature Test.
- 2. Table 1 - A/DV Hydraulic Actuator Bill of Material (Safety Related Item) y gg
- 3. Table 2 - Qualified Parameters.
- 4. Figure 2 - Accident Temperature Profile (when available)
- 5. Figure 3 - Vibration Response Spectra .
IX. References
- 1. Qualification Report for the Anchor / Darling Valve Self-Contained Hydraulic Actuator and Accessories, Report No. QR-1, Revision A, WNP-1/4, Contract 87, T-064A.
- 2. Qualification Report for the Anchor / Darling Valve Self-Contained Hydraulic Actuator and Accessories, Report No. OR-1, Revision B '
WNP-1/4, Contract 87, T-064B. II
- 3. Terminal Box Support Seismic Calculations, Anchor / Darling Valve Company, WNP-1/4, Contract 87, T-65.
- 4. Test Report on Electrical Terminations Subjected to Design Basis Accident Environment, Conex Corporation, Report No. IPS-107. GD 9
i
O n 1/4 87-QS-1 gg 5. Testing for Thermal Endurance: A case History Based on Polysulfone Thermal Plastic, paper presented by T.E. Bugel, Union Carbide Corporation.
- 6. Connectron, Inc. , letter, Schmidt, Connectron, Inc. , to Kresco, Anchor / Darling Valve Company, Justification for Equivalency of gg NSS3 to NU-2 Terminal Blocks.
- 7. Engineering Test Report GPR 575-98, AMP, Inc., September 9, 1976.
- 8. Engineering Test Report of AMP, Radiation Resistance PIDG Terminals, GPR 575-99, April 16,1974.
i 9. Product Specification for PIDG Terminals, AMP, Inc., Report No. 108-11-23, May 3, 1974.
- 10. Radiation Exposure Test Data S'm: mary, AMP, Inc., Report No.
3245-200 (1-14) , June 13, 1975.
'
- 11. Product Bulletin, Nuclear Terminals and Splices, AMP, Inc.,
Report No. 309-1, 1975.
- 12. Analysis of PIDG Thermal Aging conducted by AMP, Inc., Wyle Laboratories Report, Report No. 44275-1, December 19, 1978.
e) 13. Final Report, Qualification Tests of Class 1E Electric Cables in a Simulated Steam-Line-Break and Loss of Coolant Accident Envi.conment, Final Report, F-C4113.
- 14. Qualification Tests of Class 1E Electric Cables in a simulated Steam-Line-Break and Loss of Coolant Accident Environment, m, Brand-Rex Company, E ranklin Institute Research Laboratories
Report No. F-C4771.
- 15. Long Term Thermal Aging Arrheniut Plot, 40-year Life, Brand-Rex Company.
-
- 16. Specification for Ultrol @ Flame-Retardant Utility Station
~' Control Cable, Brand-Rex Comnany, Report No. BR-8084A, January 1976.
- 17. Qualification Tests of Electric Cable Under Conditions Simulating Normal Reactor Containment Service and a Loss of Coolant Accident, Samuel Moore and Company, November 1973. Franklin Institute E) Research Laboratories, Report F-C3683.
- 18. Qualification of NAMCO Controls Limit Switch to IEEE Standards 344-1975, 323-1974, and 382-1972, Rev. 1, NAMCO Controls Company, Acme Cleveland Development Company.
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" A/DV llVDRAULIC' ACILIATOR Ritt. Of MATERIALJSAFEfY RELATED ITE_:l1SJ ,
~ Component ilodel fin. 's~ Qualification
- Component ' - - ~
Source Prototype Act'uator WPSS 1,/_411S Reference WPPSS 1/4 FW
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A. Hydraulic Components, P-ill Dwg #763007 R/F Same as Prototype 1
- 1. Cylinder (7" hore x 5" rod x 25" stroke)
P-il Dwg #763011 R/B P-il Dwg #773046-1 R/A 3 P-il Dwg 1773046-02 R/A3 1
- 2. Ilydraulic/ Pneumatic (16 gal 9" I.D.)
Accumulator (15 gal - 9" bore) (18 1/2 gal - 9" 1.D. ) 7-R2 Mod #23304-7001- T-R3 Mod #23104-7001- T-R Mod #23304-7001- 1
- 3. 4-Way llydraulic . 2852 (75 gpm)
Valves (M,N,M1 &N) 2852 (75 9pm) ~ 2852 (25 gpm) 1 P-il Mod # CPS-1200-5 P-il Mod # CPS-2400-S- 1
- 4. Pilot Operated (P.O.) P-ll Mod iCPS-2400-S- VX-1775
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Check Valves VX17/S VX-1775 Accumulator Discharge TR-R Mod #C-224-3/45-28 Same as Prototype 1
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S. Flow Control Valve (G & G) ! P-il Mod #MVI-1200 Same as Prototype 1
- 6. Cylinder Rod Erd flow Control Valve
. (f & f) 1 Same as Prototype
- 7. Manif old tiounted P-il (tod CS-12005
. Check Valves Pneumatic Com[wgents
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, D. P-Il Dwg f/63018 R/B Same as Prototype 1
- 1. Pneumatic Reservoir
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Same as Prototype
- 2. 3-Way Solenoid Valves Sk immer Mod VSil61090/ -
( A, A } , 11, 111 , C , 1100 , C 1 , D, D 1) Same as Prototype 1
- 3. In-Line Check Valves P-il Mod #C-fl00ll 1
Same as Prototype
- 4. Nitrogen Pressure Sensolec Mod A-10
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C. Electrical Components .
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' Connectron iloil, till 2 Connectron flod flu 2 4,5,6
- l. lerminal Strips Drarpl-Rex 2/C-14AWG 13,14,15,16
- 2. Soln. Valve Wiring Ilrand-Rex 2/C-14AWG nip-PIDG Type AttP-PIDG lype 7,8,9,10,11,12
- 3. Wire Terminal Lngs Wire / Soln. Connector Amphenol Same as Prototype 1 4.
All 3106E1056-45 flamco tiod. EA-100 10 Limit Switches llamco tiod. EA-180 flamco Itod. EA-180 S. Brand-Rex 7/C & 2/C- Brand-Rex 7/C & 2/C- 13,14,15,16
- 6. Limit Switch llire 14AWG 14AWG Samuel Moore 3/C-16AWG 17 Pressure Transducer Samuel tioore 3/C-16AWG 7.
Wire __- _ fintes:
- 1. P-il, Parker ilannif in.
- 2. T-R, Teledyne Republic.
- 3. Component of the same generic design as that of the prototype.
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WPP'SS I & 4 A/0V PROT 0lYPC ILRilillAL lLllMillAL IflSIRUltf fil AI I0fd 1.lilli HSIV L FWlV llYDR AULIC POWER SillTCllES LUGS CAlll E CABLE BLOCKS
- Iloill4AL COIIDIT10ti APPLICAfl0liS ACll!ATOR
' 92.50F, 900F 770C (1710F) lemperature 550- 900f 93.60F 900C (1940F)
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Pressure Atm. Atm. -
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Ilumidity 40% - 60% 90% 200 Mrad 200 HRad 204 HRad 70 Rads 2.5 liRad *200 Mrad 25J) liRad R adiation Auff0RflAL CutlDIT10ft 3500 f(2) 34por(2) 3400F(4) 4500F 3850f(l) 4200F(5) 1emperature 4200F 57.5 psig 122 psig 105 psig 70 psig 1.6 psig Atm. 60 psig Pressure 100% 100% 100% 100% 100% llumidity 100% 100% fint req'd per riot req'd per Acme-flot r eg'd per flot req'd per Wyle Report lEEE383-74 IEEC383-74 Cleveland DBE (Seismic) 43847-2 IEEE3fl3-74 ILEC383-74 Developraent
' Sec. 10 Report Ref. flRL Rpt. Acme-Ref . F IRI. Rpt. Ref. Conax Rpt. Ref. AliP Rpt. Cleveland OBE (14SLB) flo. FC4771 flo. LPS-107 tio. GPR-575-98 tio. F-C36113 ,
Hyle Report Page 3 Page 3-4 Development 1 Attach. 4-1 Pages 10-12 4 3114 7 - 2 figure #4 Figure #5 Report
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Sec. 12 Figure #2 figure #3
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_ _ _ - _ _ _ . _ _ _ . _ _ (1) Extrapolation of the Arr.henius Data indicates that failure would occur after 4200,000 hours athours 470"F. at 4200f. (?) Extrapolation of the Arrhenius Data indicates that failure would occur af ter (3) Extrapolation of the Arrhenius Data indicates that f ailure Musld occur af ter 3 hours at 4200f. (4) An unaged flamco Limit Switch was used during the prototype actuator DBE Test.
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(5) Supplemental analysis on material provi ci (polysulfone thermoplastic). 4 i _ _ - _ - _ _ _ _ -
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O ,. I/4-87-0S-1A CLASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM C SUMARY
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I. Equipment Identification Type: Type 23, Series Nuclear Limit Switch g Manufacturer: NAMCO Controls Model No.: EA 180-31302 and EA 180-32302 II. Equipment Classification Safety Function: Provide control and position indication for
- g' the main steam and main feedwater isolation systems.
DBA Expc,sure: The valve actuators are subject to MSLB outside of containment environment. Time to Fulfill O- Safety Function: See Main Steam and Feedwater Isolation Valve Actuator Sumary, 1/4-87-05-1. III. Equipment Description The equipment is a snap-lock cosition, limit switch. ^:O IV. Qt.alification Environment Normal & Abnormal: Same as Main Steam and Feedwater Isolation Valve Actuator Sumary.
- O Accident (MSLB): Same as Main Steam and Feedwater Isolation Valve Actuator Summary.
DBA: Exposure Operating Basis Earthquake (0BE) and Safe Shutdown Earthquake (SSE).
.O V. Sumary of Qualification Plan The plan objective is to satisfy the criteria presented in IEEE 323-1974 for the WNP-1/4 MSIV specifications.
A. Aging: i O Thermal & The switch will be heat aged and irradiated Radiation: to a level of 204 Mrads gama radiation from a Cobalt-60 source at 1.25 Mev and carried l out at a rate of one Mrad per hour. O O
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O 1/4-87-QS-1A Vibration: Enveloped by the operational tests below and the seismic tests inidorthcoming Paragraph V-B. 3 e Operational: The switch will be subjected to 100,000 actuation cycles in order to simulate the normal switching. Humidity: The thermal aging test will be conducted , in a humid environment. Other: None B. Seismic: A single axis seismic test will be performed on t'se sample in each of three axes and the switch to be monitored electrically during the test. Biaxial O testing will not be conducted since analysis indicates negligible cross-coupling. C. DBA: LOCA: The temperatures and pressures used to do a LOCA test are presented in Figure 6. During the test, a caustic spray will be continuously recycled over the test sample. ) O DBA: MSLB: A separate test will not be conducted to simulate MSLB for the LOCA test mentioned above demonstrates the adequacy of this switch to meet MSLB require-ments. Calculations supporting this arugement are forthcoming. 3e D. Other: None. ' VI. Summary of Test Results The switch performed satisfactorily as it maintained all required , g performance characteristics during all parts of the tests. The switch performed it's safety function during postulated nomal/ abnormal and accident conditions. A. Aging: Thermal & Arrhenius methods were used to provide a ' ' Radiation: basis for the thermal aging of this comoonent. A life of 7 years ing the maximum normal temperature of 85 F was established by artfficiallyagingtheswitchassemblyat 200 F for 200 hours.
' O The switch was irradiated to an integrated total dose of 204 Mrads gamma radiation from a Cobalt-60 source.
Vibration: Enveloped by the Operational tests below and the seismic test results in Paragraph ' e VI-B. O
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n 1/4-87-QS-1A Operational: The switch was subjected to 100,000 actuation cycles in order to simulate switching functions of the unit. The 4 actuation was accomplished by a cam mechanism operating at 70 actuations per minute. The electrical loading during this part of the test was 500 milliamps at 100 volts DC. This simulated mechanical and electrical aging of C the unit. Humidity: See Themal Aging for Humidity considerations. Other: None. O Shaker table testing was conducted on the limit switch B. Seismic: and single axis tests performed in each of three axes. i The test spectrum consisted of a range of input motion from 1 to 35 Hz in 1/2 octive intervals maintained at an acceleration of 9.529 A cross-coupling analysis n was conducted on the components which detemined that
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the cross-coupling is not limiting in the unit, and therefore, single axis vibration testing was considered acceptable. Vibrational aging to simulate in servicg condition was performed at 100Hz,1.3g's, and for 10 cycles. Electrical load was applied during these vibrations. The perfomance of all the switches except g' #61 was monitored for contact chatter greater than 2 milliseconds. None was observed. 4 The 9.52g test acceleration seismically qualifies the limit switch to its 40 yeer ervice life because of the substation margin over the 3g limitation on its O associated valve actuator (see Paragraph VI-G of report 1/4-87-QS-1). C. DBA: LOCA: The temperature and pressure profile for the design basis accident exposure used in the tests is provided in Figure 4. Switch #61 was mounted in a test chamber O and held at the specified temperature and pressure i (Attachment 1). The switch was subjected to a caustic spray composed of boric acid, water, sodium thotosulfate and sodium hydroxide, and was recycled during the entire time. g Spraying was initiated following the second transient temocrature rise. The flow rate of the spray was 0.015 4 gallons oer minute per square 'oot. The pH of the spray was maintained between 10 and 11. i ^ The switch was transferred from the high to a low pressure -g chamber following the first of four days of the LOCA test. It remained in the low pressure chamber for the rest of the 30-day test period. 4 'O s
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O 1/4-87-0S-1A
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MSLB: The test profile used during this generic program is that of a LOCA condition with caustic spray and is conservative with respect to the SLB requirements ,G in all parameters except temperature. During the actuation test (see Reference 1) a non-thermally aged EA-180 limit switch was used which experienced a 450F temperature peak. This switch was mechanically and seismically tested during the mechanical aging and seismic test portion of the actuator prr' gram. e These additional tests coupled with the generic test 3 program above demonstrate the adequacy of the NAMCO limit switch EA-180 series for this application. D. Other: Contact resistance was measured on the switch. In all phases of the test, the open circuit contact
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g resistance of the switch remained above 50 kohms.
'The closed circuit current remained within two milliamps of the baseline closed circuit current.
During seismic testing, the trip point (with 2-inch arm) varied by 0.060 inches or less for all units seismically tested. ) 8 VII. Attachments
- 1. Figure 4 - Test Chamber Temperature Profile for Accident Environment Simulation - NAMCO Limit Switches (E-180).
- 2. Accident Temperature Profile, MSLB Requirements (to be provided ) G-later).
VIII. References
- 1. Qualification of NAMC0 Controls Limit Switch to IEEE Standards 344-1975, 323-1974, and 382-1972, Rev.1, NAMC0 Controls Company, ) S Acme Cleveland Development Company.
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Q. ,, 1/4-87-QS-1B CLASS 1E VENDOR EQUIPMENT QUALIFICATION PROGRAM
;O
SUMMARY
I. Equipment Identification Typer 2 Conductor, 14 AWG, 19 Strand, 600 V Rated
'O_ Control Cable Manufacturer: Brand Rex Company Model No.: Model - ULTROL II. Equipment Classification Safety runction: Transmit power to solenoid valves and IO ' limit switches on the main steam and ,
main feedwater valves.
! DBA Exposure: The valve actuators are subject to MSLB '
outside of containment environment. .O Time to rulfill Safety Function: See Main Steam and Feedwater Isolation valve actuator sunnary,1/4-87-QS-1. III. Equipment Description lO The equipment consists of two (2) cross-linked, polyethylene I control cables; one to supply power to the solenoid valves and another to wire limit switches to terminal box. Internal electrical conduit is provided for cable protection. i IV. Qualification Environment
!O Normal '
Abnormal: Same as Main Steam and Feedwater Isolation Valve actuator summary report. DBE: Seismic: Same as Main Steam and Feedwater Isolation ! O V*1"* **t"** " """"*"Y "*P 't-
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V. Summary of Qualification Plan
- The objective of this plan is to qualify this equipment cabling i to satisfy the criteria of IEEE 383-1974 in the WNP-1/4 specifica
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environments. A. Aging: , . Thermal & Arrhenius methods were used to demonstrate l Radiations a qualified life of greater than 40-years
in an ambient temperature of 85.5 F. fO
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O 1/4-87-QS-1B O B. Seismic: Seismic testing of the wire and interface configuration was demonstrated by the Main Steam and Feedwater Isolation Valve Summary Report, and is not repeated in this test.
- c. DBA: LOCA: The test will be in accordance with the pro- gg cedures recommended in IEEE std. 383-1974.
The cables shall be exposed to a steam / chemical spray environment throughout the 30 days of the test. D. Other: Mandrel bend and high-potential withstand tests will be conducted. II VI. Summary of Test Results The results of the tests show the cable will perform satisfactorily under the conditions of Part IV of this report.
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GD - A. Aging: Thermal
& Radiation: Representative cables of the one used in pro-duction were selected for testing in accordance with Table 1 of IEEE-383-1974. s dp The cables were thermally aged to an equivalent 40-year life by exposure to 277F (136C) tem-perature for 468 hours. The cables were ex-posed to 200 megarads of gamma radiation using a cobalt-60 source. The cables were rotated gg to give a uniform radiation exposure. There were no visible changes that would affect per-
, formance in meeting all' requirements.
Vibration: Not applicable, see Section V-A, B. Operational: The cables performed their required electrical II function both during and following the aging and LOCA tests. Humidity: The LOCA test (described below) successfully subjected the cables to an intense steam /
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chemical spray. ID B. Seismic: Not applicable, see Section V-A, B.
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C. DBA: LOCA: The~LOCA test temperature / pressure profile to which the cables were exposed is illustrated ,
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in Attachment 1. The cables were exposed to a steam / chemical spray environment thoughout the 30 days of the test. The cables were
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sprayed continuously with a chemical solution consisting of H 3 B03 (3000 parts per million boron) bufferred with sodium hydroxide to a PH of betwer. 10.C and 10.5 at room temperature (75-80F) . 3 Extrapolation of Arrhenius data for the insulation material shows that the cable could survive for several hours prior to failure at 420F. The enclosure on the cable coupled wita Arrenius extrapolation demonstrate the adequacy of the cable of the thermal [) conditions in this application. The peak test temperature was 346F and it was held for two hours while the required peak exists only for a short period. This approach is further justified due to the fact that the
- ) humidity and pressure levels greatly exceed the requirement and the electrical cable is contained in metalic conduit and will not experience the full level temperature excursion.
MSLB: Aged and irradiated cables were also exposed to a superheated steam blast (autocalve
'7) temperature rose to 370F within 10 seconds) and 370F was held for two minutes then lowered to 350F and held for another 8 minutes. At this time the cable was cooled to 301F by a chemical spray of 6200 ppm boron mixed with ~3 50 ppm Hydrazine and solution pH between 8.6 s and 10.0 maintained with trisodium phosphate.
The 302 F temperature was held for 10 hours until conclusion of the test. All cables demonstrated satisfactory performance during MSLB test with substantial margins of life remaining.
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D. Other: After the 16-day exposure to the steam / chemical spray, the cables were removed from the test vessel and subjected to final mandrel-bend and high-potential withstand tests. Al cables withstood the mandrel and high-
) potential test both before and after the steam / chemical spray tests. There was not evidence to show the cables will not meet or exceed their requirements.
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0 1/4-87-QS-1B i l l l l 1 9 VIII. Attachments
- 1. Accident Temperature Profile, MSLB requirement (to be furnished later). O
- 2. Figure 7--Actual Temperature / Pressure Profile for Simulation of LOCA for Brand Rex Qualification Report IX. References 9
- 1. Qualification Tests of Class IE Electric Cables in a simulated Steam-Line-break and Loss of Coolant Accide,'; Environment, Brand-Rex Company, Franklin Institute Research Laboratories Report No. F-C4771.
- 2. Iong-Tem Thermal Aging Arrhenius Plot, 40- vear Life, Brand-Rex Company. g
- 3. Specification for Ultrol @ Flame-Retardant 11tility Station Control Cable, Brand-Rex Company, Report No. BR-8084A, January 1976.
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C3 7 1/4-87-QS-lC CLASS 1E O VENDOR EQUIPMENT QUALIFICATION PROGRAM
SUMMARY
I. Equipment Identification . C) Type Modular Terminal Block Manufacturer: Connectron Inc. Model No.: Model No.-2 II. Equipment Classification 2 () Safety Function: The terminal blocks provide the electrical interface and mechanical termination to and from the Main Steam and Main Feedwater Isola-tion valves. The terminal blocks must remain intact during a DBE to provide physical separa-tion of electrical connections. O DBA Exposure: The terminal blocks are protected by an enclosure from the MSLB conditions. Time to Fulfill Safety Function: This device must fulfill its safety function within the time and requirements of the
'l system (see Paragraph II of A/DV Actuator Qualification Summary Report 1/4-87-QS-1).
III. Equipment Description The equipment consists of the NU-2 terminal bloc:. It is rated at 600 C) volts, 50 amps, will accommodate terminal of wire sizes 16 thru 10 AWG and the insulating material is polysulfone.
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IV. QualiEication Environment See Main Steam and Feedwater Isolation Valve Summary Report 1/4-87-QS-1.
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V. Summary of Qualification Plan The NU-2 terminal blocks are qualified by a type-test performed on similar terminal blocks: Connectron, Inc. , Model No. NSS3 with the same material (thermal plastic molded polysulfone) . ' () Aging: A. Thermal & The activation energy (2.53 ev) of poly-Radiation: sulfone material is of such magnitude to preclude the need for thermal aging. . However, the terminal block will be - () both thermally and radiation aged prior to DBE testing.
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l l Ol 1/4-87-QS-lC Vibration: The Main Steam and Feedwater Isolation Valve Summary Report, 1/4-87-QS-1, demon-strated the ability to withstand self- G induced vibration effects on the wiring and interface components. The testing is not repeated here.
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Operational: Same as Vibration, above. G Other: Functional testing will be done by energizing the teminal blocks to verify their electrical integrity following the above aging tests. B. Seismic: Same as Vibration, above. g C. DBE: LOCA: The LOCA test will be conducted using the thermally and irradiation aged terminal blocks mounted in terminal boxes. The terminal blocks will be energized during the LOCA test. See Figure 8. MSLB: A report by Union Carbide (Reference 2) indicates that the half-life of polysulfone material at 410 ,- 36 F is a matter of days. Main steam line break environments exist only a matter of minutes. Therefore, there is no doubt of this material's ability to survive the MSLB environment in a 420 F environment for 1-2 minutes. No testing is necessary. > 0 D. Other: High-potential withstand testa will be conducted. Flashover tests will be conducted on adjacent terminals of the terminal blocks during the test. Insulation resistance, dielectric strength and continuity tests will also be performed during the 9 type-test. VI. Summary of Test Results The objective of this testing was to satisfy the criteria of IEEE 323-1974 for WNP-1/4 plant specifications. g A. Aging: Thermal & The terminal blocks were aged to an Radiation: accelerated life by exposure to a temperature of 300F(146C) for a period g of 74 hours. Arrhenius data igdicates this is equivalent to 6.1 x 10 years in an ambient temperature of 85.5 F. ! l An integrated dosage of 25 Mrads gamma radiation was imposed on the blocks. No noticeable effect was detected after the O irradiation.
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?O-gs 1/4-87-QS-lC Vibn tion: See Section V-A, above. 'O Other: Functional testing by energizing the terminal blocks verified their electrical integrity following the above aging tests. B. Seismic: See Section V-B, above. 'O C. DBA: IOCA/ The aged and irradiated terminal blocks were MSLB: mounted in terminal boxes and exposed to LOCA tests consisting of the temperature and pressure profile described in Figure 8. Based on the test results presented in Reference 2, O the LoCA temperatures usea are justified. The half life of the material at 420F(216C) is a matter of days. However, the specified abnormal condition is anticipated to last only a matter of minutes. Insulation resistance measurements before and during the LOCA tests indicate the terminal blocks
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D. Otter: The prototype test terminal blocks successfully completed the high-pot testing. The high-pot testing was conducted after sequential testing of the blocks by exposing them to aging, radiation, and to LOCA conditions. The terminal blocks are iO considered qualified to perform their safety function under the conditions they will experience in the WNP plants. Also, there were no indications of any flashover. VII. Attachments .O
- 1. Figure 8 - Conax Terminal Blocks NU-2 Accident Temperature Test (Terminals Inside Terminal Box Protected from Direct Spary).
VIII. References .O 1. Terminal Box Support Seismic Calculations, Anchor / Darling Valve Company, WNP-1/4, Contract 87, T-65.
- 2. Testing for Thermal Endurance: A case History Based on Polysulfone Thermal Plastic, paper presented by T.E. Bugel, Union Carbide Corporation.
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D 3 1/4-87-92-10 CIASS 1E
' VENDOR EQUIPMENT QUALIFICATION PROGRAM
SUMMARY
AMP, Inc., PIDG High Temperature Terminal Lug: The terminal lugs of this qualification program are only subject to an ) "outside containment" envirornnent. The qualification of this equipment covered for the penetrations, under Contract 55, and reference is made to that summary report, 1/4-55-QS-1A.
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VENDOR EQUIPMENT QUALIFICATION PROGRAM l
SUMMARY
l l I. Equipment Identification Type: SkV Power Cables J Manufacturer: Okonite Company Model No.: Okonite Insulated Cable (Flame Retardant) II. Equipment Classification Safety Function: Safety function of these cables is to carry
rated voltage and current. DBA Exposure: This cable is used in many areas of the plant. It could be exposed to HELB outside containment. There are no applications of this cable inside containment on safety related equipment. s Time to Fulfill Safety Function: This cable is a component of various systems and has a time requirement imposed on it by these systems. III. Equipment Description
)
5000 volt single conductor power cable insulated with Okoguard (Flame Retardant - EP) overlayed with shielding tape and Okolon jacket.
, IV. Qualification Environment Normal: Temperature: 104F (40C)
Humidity: 60% Maximum Radiation: 10 rads / year Abnormal: Temperatur e: -llF (-24C) to 131F(55C) 3 Humidity: 5% to 100% Radiation: 10 rads / year Accident: HELB: The profiles for ex-containment high-energy-line-break events are currently under preparation. However, it is not anticipated that these profiles
~3 will approach the severity of the in-containment l accident conditions postulated for WNP-1/4, or l the DBA environments that were performed during '
the qualification testing. V. Summary of the Qualification Plan The objective is to satisfy the requirements of IEEE 383-1974 for the WNP-1/4 plant specifications.
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A. Aging: (D Thermal: Develop an Arrhenius plot by linear regression analysis of test data and deter-mine a time and temperature for acceleration aging of the cable to a 40 year life at 90C through extrapolation of that plot. Radiation: Samples to be gxposed to a cummulative dose of 2 x 10 rads from a Cobalt-60 source. Vibration: Self-induced vibration and vibration from nearby equipment is not a factor in contri-m buting to the aging of this equipment.
" Therefore, vibration aging is omitted from the qualification testing.
Operational Normal operation produces heating Offects, which are incorporated in the thermal aging portion of this program. B. Seismic The cabling is arranged and restrained raceways and trays. This equipment is analysed for seismic effects, which precludes the need for seismic testing of individual cables. [) C. DBA: Although not required, the plan included exposure to LOCA, see Figure 1. D. Other: IEEE-Std-393-1974, Par. 2.5 except that burner is set Flammability: at 210,000 BW/ hour. j VI. Summary of Test Results The analyses and test results demonstrate that this cable will perform its safety function under more severe environments than are anticipated by the ex-containment requirements listed in Part II of this summary report. Aging: Thermal: Insulation samples were aged at various temperatures for the times needed to reduce to 40% retention of elongation. From this y data an Arrhenius curve was developed by
's regression analysis for a 40 year life which is higher than 90C. To verify the curve, samples of jacketed cables were aged to three points on it and the retention of elongation of the insulation was measured. The results showed 60 to 90% retention of elongation, J a considerable margin. Also, the samples have operational experience correlation using data from cables installed in an actual fossil power plant.
, _ _
1/4-104-gs-1
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The flame test was not conducted on samples containing splices. However, an analysis was conducted to show that the heat producing material being added by the Raychem splice 'l II was only 5.1% of the total heat available and was therefore not significant. See Reference 1. VII. Modification to Equipment
) GD None VIII. Attachments Figure 1
) GD IX. References
- 1. Nuclear Qualification Report, Supply System 1178-1 for Okonite Okoguard Insulated Cable 5 and 15kV. WNP-1/4, Contract 104, C-5C.
- 2. Trip Report by P. F. Milliken, dated 8-22-79, " Observe Flame 3 gg Testing of 600 Volt Control Cables and SkV Power Cables".
- 3. Okonite IOC dated 8-20-79, " Flame Testing After Aging", T-24.
- 4. Okonite IOC (undated), " Flame Tests on Cables with Raychem Splices and Terminations", T-5D. , ,
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3 c J J l 1 D D APPENDIX B D WNP-1/4 D
, INSTRUMENTATION / ELECTRICAL EQUIPMENT LIST D
D D D
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D DESCRIPTION OF THE FIELDS OF THE SAMPLE CLASS 1E g __ INSTRUMENTATION AND ELECTRICAL EQUIPMENT LIST The Class IE sample list contains information on the various types of equipment supplied as balance of plant equipment for the 1/4 Project. An identical format will be used on the 3/5 Project. The following items are definitions of the fields. 3
. Field /Name(Alpha-Numeric Field Definition Length)
Equipment Number (24 CH.) Equipment identification code that uniquely identifies each piece of 3 equipment by system, component or detailed designation within the com-ponent type. Project (2 CH.) The project for which the equipment is used. D Description Code (3 CH.) A type of equipment classification such as RLY/001 (e.g., RLY for relay, 001 for detailed designation within the component type). 3 Composite Equipment Number The equipment piece number for which this (25 CH.) component is a part. Life (4 CH.) The qualified life of this equipment in years. Hours to Operate (8 CH.) The hours required to operate in an D accident environment.
. Document Location (20 CH.) This field indicates, for a major equipment type, where the summary report for that equipment is located. Detailed documenta-tion, such as test reports, are referenced 3 by the summary reports. For individual components, the detailed test report is referenced.
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C Field /Name Definition Safety Function (30 CH.) This field provides the function that the equipment is required to perform during 7 O postulated DBE. Manufacturer's Reference A code number which identifies the manu-Number (4 CH.) facturer of the component as defined in the Reporting Procedures Manual for the Nuclear Plant Reliability Data System Southwest >G Research Institute, Table 9. Manufacturer's Model Number The manufacturer's unique number which (20CH.) provides a means to identify the component. Quantity (3 CH.) The number of the same items associated with 3 e a major piece of equipmc.t (e.g., relays assigned to a MCC cabinet). Location (20 CH.) Location of a component given by 1) code
- Building (1 CH.) to identify the building in which the com-
- Elevation (3 CH.) ponent is located, 2) the elevation of the > g
- Detail (13 CH.) component above sea level, 3) building
- Zone (3 CH.) coordinates or containment AZIMUTH of the component, and 4) the zone assigned to distinguish the area in the plant where the component is located.
Description (50 CH.) The identifier which provides information ' O regarding the component or equipment name. Use (2 CH.) Contains codes which describe equipment use during accioent conditions and/or normal plant shutdown. > g; A code number identification has been used for the Seismic Qualification, Use and Environmental Qualification fields. The codes described in the following sections are used. SEISMIC QUALIFICATION INPUT FIELDS 2 WNP-1/4 AND WNP-3/5 CLASS lE LIST 9 Seismic Qualification Test Analysis SEISMIC QUALIFICATION
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TEST ANAL F/0 C0HP g XXX XX XX X 1 The Seismic Qualification Input Fields are to be arranged as indicated above. There are six fields in the layout format arranged into four groups. Each field is a single digit or dual digit, as indicated, numerical code entry. ' g Each field should have sort and call-up capability. l 9 t
O The following describes the individual fields and groups, and provides O representative codes with ti air definition. Additional codes with their definition will be develope , as the need is identified. Standard Input Array and Codes for Seismic Data Input
.X. .X. .X. XX X X .X.
The Test Group: (3 CH.) Input motion - such as for Random Mo' tion Multi-frequency a 1 would appear here. (1 CH.) g Code for the number of axes and manner of input motions was simultaneously applied. (1 CH.) A code for the method of resonance determination is entered here. (1 CH.) Note: These are three distinct fields and sort O capabilities should be provided on each field. The Analysis Group: (2 CH.) The code for analysis type is entered here. O The Functional Operability Group: (2 CH.) The code for type of Spurious Operation is entered here. . The Compliance Group: (1 CH.) O
-The code for compliance to IEEE-344 is entered here.
Codes for the Method of Resonance Determination: XXX XX XX O O Later or not required. 1 Resonance Sweep. A sinusoidal input (sine sweep) with continuously varying frequency is applied. The frequency band covers the range of frequencies from 1 to 33 hertz. This test is used as a reson-O ance search test at low input (.29 .4g) in support of sine Dwell (XX4) or sine heat (XX5) testing. 2 Resonance Analysis. The resonance of the specimen is determined by analysis. (The specimen is modeled using single degree of freedom oscillators.) Oo 1
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- Codes for the Number of Axes and Manner of Seismic Input:
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XXX XX XX O Later or not required. 1 Single axis input. The input motion is applied to each principle axes independently. ,g 2 Biaxial input. The input motion is applied to two principle axis simultaneously. The time phasing of the input is time-incoherent for Random Motion. Forsinglefrequencytests,suchas,singbeat,the inputs are applied in-phase and then 180 out-of- ) , phase. For both Random and single frequenc biaxial testing, the specimen is rotated 90 and the above procedure repeated. 3 Tri-axial input. The input motion is applied to each principle axes simultaneously. 4 Modified Bi-axial input. The specimen is mounted on the shake tgble in a fixture that supports the speci-men at a 45 incline from the vertical. The input motion is then applied colinear with the specimen mounting. The input amplitude is adjusted by the 2 to account for resultant forces produced in the ) 9 vertical and one principle horizontal axes. Thus, the time phasing of the input is in-phase for the axis (vertical and one horizontal) tested. Codes for the Maoer of Seismic Input Motion
) 9 XXX XX XX 0 Later or not required.
1 Random Motion Multifrequency Test. The amplitude of which is controlled in 1/3 octave or narrower, i g frequency bandwidth filters with individual output gain controls. Minimum duration of test is 30 i seconds. ! l 2 Random Motion Multifrequency with sine beat super-imposing. A composite excitation utilizing input ; motion of 1 with sine beat of (IEEE-344, 1975 8 6.6.3.4). 3 Complex Wave. Not used (IEEE-344,1975 6.6.3.5). 4 Continuous Sine Test (Sine Dwell). A continuous sinusoidal test conducted at the resonants fre- 'S quencies determined from resonance search or analysis or near 33 hertz if no resonances are present between 1 and 33 hertz. Any resonances are widely spaced. (IEEE-344, 1975 6.6.2.2). 9
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1 , Codes for the Manner of Seismic Input Motion (cont) J XXX XX XX 5 Sine Beat Test. A test consisting of the application of sine beats of peak acceleration corresponding to resonance frequencies of the D specimen or near 33 hertz if no resonances are present between 1 and 33 hertz. Any resonances are widely spaced (IEEE-344,1975 6.6.2.3). 6 Sine Sweep Test. A sinusoidal input with contin-j uously varying frequency is applied the input amplitude is equal to the ZPA of the RRS except at low frequencies where the value of the TRS may follow the RRS. Justification is provided. 7 Both 1 and 5 were performed. 8 Random Motion Multifrequency Test and Sine Beat Test. Both 1 and 2 were performed. 9 Continuous Sine Test (Sine Dwell) Over a Frequency Range. A continuous sinusoidal test conducted in 1/3 octave bands over the frequency range 1 to 35 Hz. Codes for Analysis Group: XXX XX XX , 00 Later or.not required.
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01 Static analysis is performed by applying the seismic forces through the center of gravity of the specimen in addition
- to all other applicable loads. A precondition to the use of static analysis is that the specimen must contain no 3 significant resonances below 33 hertz.
02 Oynamic Analysis. The specimen is modeled to best represent it's mass distribution and stiffness characteristics. A response spectrum model analysis technique or a time history analysis is a " used. Results are combined using the square-root of the sum of the square basis except for closely spaced or in-phase models where the absolute value is used. 03 Extrapolation. The results of testing on a proto- , type specimen is analyzed and the results extended J to cover a generic line of similar equipment. Where the differences are significant, justification is provided. 3
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I CODES FOR FUNCTIONAL OPERABILITY INPUT FIELD XXX XX XX X 3 0 0 Later or not required. 1 Spurious operation that does not effect the operation of the safety function; the devices' capability to perform the safety function is acceptable without modification. 3 8 2 Spurious operation; modification to the device was essential to performance of the safety function. The device was found to be acceptable after modification or substitution. 3 Spurious operation; combination of 1 and 2. ) G 4 No occurrance of spurious operation; devices' capability to perform its safety function has been found acceptable during and after qualification test or analysis. Type of Spurious Operation 3 g XXX XX XX X 0 Later or not required. 1 Contact Chatter , g 2 Loose parts due to vibration 3 Broken par..; due to vibration 4 Failure to operate , Codes for the Compliance Group TEST ANL F/0 C XXX XX XX X
> 0 i 0 The equipment's seismic qualification is not I required.
5 The equipment's seismic qualification complies with IEEE-344, 1975.
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1 1 _ _ _ . . _ _ _ _ _ _ - - _ _ - _
D "USE" Input Field 1/4 & 3/5 Class 1E List 4 The "USE" input field is to be arranged as 2, one digit fields. They shall be arranged as shown below. These fields should have sort and call-up capability. Standard Input Array and Codes for the "USE" Field (2 CH.) X _X. The code for the equipments use during plant shutdown is entered here. O The code for the equipment use during accident conditions is entered here. Codes for the Equipment "USE" During a Design Basis Accident & Normal Plant Shutdown O USE XX 0 The equipment is not required before, during, or after O "" 8CCid'"t-1 Equipment that will experience the environmental conditions of design basis accidents for which it must function to mitigate said accidents, and that will be qualified to demonstrate operability in the accident environment for the time required for accident miti ation with safety margin to O failure. (See Hours to Operate 2 Equipment that will experience environmental conditions of design basis accidents through which it need not function for mitigation of said accidents, but through which it must not fail in a manner detrimental to plant safety or accident O mitigation, and that will be qualified to demonstrate the capability to withstand any accident environment for the time during which it must not fail with safety margin to failure. 3 Equipment that will experience environmental conditions of O design basis accidents through which it need not function for mitigation of said accidents, and whose failure (in any mode) is deemed not detrimental to plant safety or accident mitiga-tion, and need not be qualified for any accident environment, but will be qualified for its non-accident service environment. g 4 Equipment that will not experience environmental conditions of design basis accidents and that will be qualified to demonstrate operability under the expected extremes of its non-accident service environment. This equipment would normally be located outside the reactor containment. O
Ol The Code for the Equipments "USE" During Plant Shutdown xx ,
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O The equipment is not required to operate to shutdown the plant during normal conditions. 1 The equipment is required to operate for Hot Shutdown only during normal plant conditions. g 2 The equipment is required to operate for Cold Shutdown only during normal plant conditions. 3 The equipment is required to operate for both Hot and Cold Shutdown during normal plant conditions. , ENVIRONMENTAL QUALIFICATION INPUT FIELDS & GROUPS 1/4 & 3/5 CLASS 1E LIST The uta provided in the attached sheets give the detailed description and definition of the fields and groupings of the Environmental Qualification for the 1/4 and 3/5 Class 1E List. ) 9 There are 7 fields contained in 3 groups. Each field is t .' gle digit numerical entry for the Aging and Compliance Group and a douvie digit entry for the DBE Group and should have sort and call-up capability. The output layout is as follows:
>G ENVIR0N QUAL AGEING DBE COMP XXXXXX XXX X Standard Input Array and Codes for Environmental Qualification Data Input
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The Aging Group (8 CH.)
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.X. .X. .X. X .X. XX X y
j The code for Humidity aging is entered here. (1 CH.) The code for Vibration aging is entered here. (1 CH.) ,
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The code for Radiation aging is entered here. (1 CH.) The code for Operational aging is entered here. (1 CH.) The code for Thermal aging is entered here. (1 CH.) The code for type of DBE is entered here. (2 CH.)
-The code for compliance to IEEE-323 is entered here. (1 CH.) ' S l e l
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General Codes for the Aging Group XXXXX XX X
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0 Later or not required. 1 Aging by this parameter has been addressed by inclusion in the type test. (IEEE-323, 1974 5.1) 2 Aging by the parameter has been addressed by Operating Experience. (IEEE-323 5.2) 3 Aging by the parameter has been addressed by Analysis. (IEEE-323,1974 5.2) ' D 4 Aging by this parameter was addressed by a combination of 1 and 2, (IEEE-323,1975 5.4) 5 Aging by this parameter was addressed by a combination of 1 and 3, (IEEE-323,1975 5.4) D 6 Aging by this parameter was addressed by a combination of 2 and 3, (IEEE-323,1975 5.4) 7 Aging by this parameter is being addressed by a program of on-going testing. (IEEE-323, 1975 5.5) 8 Aging by the parameter has been included in the DBE. 9 Aging by the parameter has been considered. It has been determined that either this parameter will have no affect on the speciman to perform its safety function or that due to the specimans mounting location in the 3 plant this parameter is of benign nature. The Codes for the DBE Simulation Test XXXXX XX X 3 00 Later oi not required. 01 LOCA test simulation. The speciman in its aged condition (including accident radiation) is subjected to the profile of pressure, temperature, and spray expected during a Loss of Coolant Accident as defined D in Chapter 15 (FSAR). 02 LOCA test simulation. The specin . in its aged condition is subjected to the simultaneous exposure of Accident radiation, temperature, pressure and spray expected during a Loss of Coolant Accident as 3 defined in Chapter 15. 3
___ . _ _ . _ _ ... __ _ . _ _ . _.- _ . _ _ _ _._ - _ _ _ . . . _-_.. _ - Pags 25 l l WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NLM ER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION WG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 55 APN-EPA-HJ2 APN-EPA-HJ2 R 440' 1B 121 00 19199 RTD's & Instrum Thermocouple Elec Pent Asly W120 WX-33125 221 DEG 40 5 07 4 i Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 ! 55 APN-EPA-HJ3 APN-EPA-HJ3 R 448 l'8 121 00 19199 Gerieral Use Low & Medium Power AC EPA W120 WX-33121 212 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HJ4 APN-EPA-HJ4 R 471 3C 121 00 19199 General Use Low & Meditsn . Power AC EPA W120 WX-33121 152 DEG 40 5 07 4
! Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HJ5 APN-EPA-HJ5 R 467 3C 121 00 19199 General Use Heavy Power AC Elec Pent Assembly W120 WX-33122 144 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HJ6 APN-EPA-HJ6 R 471 3C 121 00 19199 '
General Use Heavy Power AC . Elec Pent Assembly W120 WX-33122 147 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HJ7 APN-EPA-4J7 R 467 3C 121 00 19199
- General Use Control Power
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AC & DC EPA W120 WX-33120 152 DEG 40 5 07 4 , Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1
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Page 1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE. EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 CFC-FAN-17A CFC-FAN-17A R 435 3B 2ff 01 00000 Vaneaxial Fan B515 24D65 Tube Axial Column 9 ## 5 00 0 H2 Pocket IMS Vent 40 2400 23 1 1/4-22-QS-1 22 CFC-FAN-17B CFC-FAN-17B B 435 3B 2## 01 00000 Vaneaxial Fan B515 2t065 Tube Axial Column 8 ## 5 00 0 H2 Pocket IMS Vent 40 24ia 23 1 1/4-22-QS-1 22 CFC-FAN-18A CFC-FAN-18A R 405 4A 2ff 01 00000 Vaneaxial Fan B515 24D65 Tube Axial Column 1 ## 5 00 0 H2 Pocket LCC Vent 40 2400 23 1 1/4-22-QS-1 Fan / Train A 22 CFC-FAN-18B CFC-FAN-18B R 405 4A 2## 01 00000 Vaneaxial Fan B515 24D65 Column 1 ## 5 00 0 H2 Pocket LCC 40 2400 23 1 1/4-2J-QS-1 Vent Fan / Train B 22 HCA-FAN-2A HCA-ACT-1A G 479 19E 2fl 01 00000 Centrifugal Fan B515 980 BLD H-3 ## 0 00 0 RTRN Air FN for MK-UP 40 696 43 i PHP Area 22 HCA-FAN-2B HCA-ACT-1B G 455 19E 2## 01 00000 Centrifugal Fan B515 980 BLD H-3 ## 0 00 0 RTRN Air FN for MK-UP 40 696 43 1 _ _ _ _ _ _ _ _ _ _ ___ ._ _ _ _ _ .
_______ _ _ __ ___ ________ __ Paga 2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPf1ENT LIST MASTER REPORT l CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEY ZONE SEISMI'C ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HCL-FAN-1A HCL-AHU-1A G 479 19E 2ff 01 00000 Centrifugal Fan B515 600 HVH BIG BUFFALO G4 ff 0 00 0 Air Mover For MK-UP 40 696 43 1 22 HCL-FAN-1B HCL-AHU-1B G 399 30A 2f# 01 00000 Centrifugal Fan BS15 360 PCHW BIG BUFFALO C-3 ## 0 00 0 Air Mover for Control 40 # 43 1 Room 22 IICL-FAN-3A HCL-FAN-3A G 462 300 2ff 01 00000 Vaneaxial Fan B515 33A9 Adjustax D-2 ff 0 00 0 RTRN Air Fan for Control 40 # 43 1 Room 22 HCL-FAN-3B HCL-FAN-3B G 462 30D 2ff 01 00000 Vaneaxial Fan B515 33A9 Adjustax D-2 ## 0 00 0 RTRN Air Fan for Control 40 # 43 1 Room 22 HCL-FAN-4A HCL-FAN-4A G 501 11E 2ff 01 00000 Vaneaxial Fan B515 A 7/15 Axial K-9 ## 0 00 0 Exhaust Fan for Toile t 40 f 43 1
& Kitch 22 HCL-FAN-4B HCL-FAN-4B G 501 IlE 2f# 01 00000 Vaneaxial Fan B515 A 7/15 Axial K-9 ff 0 00; O Exhaust Fan for Toilet 40 # 43 1
& Kitch s c . . _ m . ; j l o . . . . . . . . . .
. . . - . - - - - . . _ - - _ - -.. . _ -_ .-
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Page 3
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMRER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HCL-FAN-5A HCL-FAN-5A Y 479 8 2## 01 00000 Vaneaxial Fan B515 2989 Adjustax REM AIR INT ## 0 00 0 Remt Emrg, Air, Intake 40 # 43 1 E. of RX 22 HCL-FAN-5B HCL-FAN-5B Y 479 8 2## 01 00000 Vaneaxial Fan BS15 29B9 Adjustax REM AIR INT ## 0 00 0 Remt Emrg, Air Intake 40 # 41 1 E. of RX 22 HCL-FAN-6A HCL-FAN-6A Y 479 5 2## 01 00000 Vaneaxial Fan B515 2989 Adjustax REM AIR INT ## 0 00 0 Remt Emrg, Air Intake 40 # 43 1 S. of RX 22 HCL-FAN-6B HCL-FAN-6B Y 479 5 2## 01 00000 Vaneaxial Fan B515 29B9 Adjustax REM AIR INT ## 0 00 0 Remt Emrg, Air Intake 40 # 43 1 S. of RX 22 HDG-FAN-2A HDG-AHU-1A G 429 20C 200 02 00000 Vaneaxial Fan B515 54D9 F-3 00 0 00 0 Air Mover for Diesel 40 696 43 I , Gen. Area ,
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__ l Pag] 4 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS IE EQUIPMENT LIST MASTER REPORT
CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HDG-FAN-2B HDG-AHU-1B G 429 19C 200 02 00000 Vaneaxial Fan B515 54D9 G-3 00 0 00 0 Air Mover for Diesel 40 696 43 1 Gen. Area 22 IIDG-FAN-4A HDG-FAN-4A G 429 20C 2ff 01 00000 Vaneaxial Fan B515 48D9 Adjustax E-2 ff 0 00 0 Emrg, Exhaust Fan 30 696 43 1 Diesel Gen. Area 22 HDG-FAN-4B HDG-FAN-4B J-3 2## 01 00000 Vaneaxial Fan B515 48C9 Adjustax ## 0 00 0 Emrg, Exhaust Fan 40 696 43 1 Diesel Gen. Area 22 HPT-FAN-1A HPT-AHU-1A G 399 30A 2ff 01 00000 Centrifugal Fan B515 480 ilVH BIG BUFFALO A-8 ff 0 00 0 Air Mover for Elec. & 40 696 43 1 Pipe Tunnel 22 HPT-FAN-1B HPT-AHU-10 G 399 30A 200 02 00000 Centrifugal Fan B515 480 HVH BIG BUFFALO A-8 00 0 00 0 Air Mover for Elec. & 40 696 43 1 Pipe Tunnel
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O O O- 0 O- 0 0 U U N v s Page 5 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 IIPT-FAN-2A HPT-FAN-2A G 399 30A 2## 01 00000 Vaneaxial Fan B515 4309 Adjustax D-10 ## 0 00 0 RTRN Air Fan /Elec. & 40 696 43 1 Pipe Tunnel 22 IIPT-FAN-28 HPT-FAN-28 G 399 30A 2ff 01 00000 Vaneaxial Fan B515 4309 Adjustax D-10 ## 0 00 0 RTRN Air Fan /Elec. & 40 696 43 1 Pipe Tunnel 22 HSC-FAN-1A HSC-AHU-1A G 399 30A 2ff 01 00000 Vaneaxial Fan B515 960 PCllW BIG BUFFALO C-3 ## 0 00 0 Circ. Fan for Switchgear 40 # 43 1 Area 22 HSC-FAN-1B ilSC-AHU-1B G 399 30A 2## 01 00000 Vaneaxial Fan B515 960 PCHW BIG BUFFALO C-5 ## 0 00 0 Circ. Fan for Switchgear 40 # 43 1 Area 22 HSC-FAN-3A HSC-FAN-3A G 421 308 25# 01 00000 Vaneaxial Fan B515 54D9 Adjustax C-4 ## 0 00 0 RTRN Air Fan Switchgear 40 # 43 1 Area ,
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Pag 3 6 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP N0 BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HSC- FAN-3B HSC-FAN-3B G 442 30B 2ff 01 00000 Vaneaxial Fan B515 54D9 Adjustax C-4 ## 0 00 0 RTRN Air Fan Switchgear 40 f 43 1 Area 22 HSC-FAN-4 HSC-FAN-4 G 421 30B 2ff 01 00000 Propeller Fan B515 28/18 LB BREEZO D-8 ## 0 00 0 Battery Room Exhaust Fan 40 f 43 1 22 HSC-FAN-5B HSC-FAN-5B G 421 30B 2ff 01 00000 Propeller Fan B515 28/18 LB BREEZO B-4 ## 0 00 0 Battery Room Exhaust Fan 40 # 43 1 B Train 22 HSC-FAN-6B HSC-FAN-6B G 421 30B 2ff 01 00000 Propeller Fan B515 28/18 LB BREEZO A-6 ff 0 00 0 Battery Room Exhaust Fan 40 # 43 1 B Train 22 HSC-FAN-7A HSC-FAN-7A G 431 30B 2ff 01 00000 Propeller Fan B515 28/18 LB BREEZO B-7 ff 0 00 0 Battery Room Exhaust Fan 40 # 43 1 A Train 22 HSC-FAN-8A HSC-FAN-8A G 421 30B 2ff 01 00000 Propeller Fra B515 28/18 LB BREEZO B-8 ff 0 00 0 Battery Room Exhaust Fan 40 # 43 1 A Train
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u u o u e u u e u u e Page 7 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG HGF MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE liRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HSC-FAN-9A HSC-FAN-9A G 501 10E 2## 01 00000 Vaneaxial Fan B515 22A5 Adjustax H-6 ## 0 00 0 Exhaust Fan Switchgear 40 # 43 1 Area 22 HSC- FAN-98 HSC-FAN-98 G 501 10E 2## 01 00000 Vaneaxial Fan B515 22A5 Adjustax H-6 ## 0 00 0 Exhaust Fan Switchgear 40 # 43 1 Area 22 HSF-FAN-1A HSF-ACT-1A G 519 25D 2ff 01 00000 Centrifugal Fan B515 730 BLD W-9.2 ## 0 00 0 Air Hvrs/ Spent. Fuel 40 # 43 1 Storage 22 HSF-FAN-1B HSF- ACT-1 B G 51 9 25D 2## 01 00000 Centrifugal Fan B515 730 BLD T-9.2 ## 0 00 0 Air Hvrs/ Spent Fuel 40 # 43 1 Storage 22 HSF-FAN-2A HSF-ACT-2A G 51 9 8E 2ff 01 00000 Centrifugal Fan B515 730 BLD R-9.2 ## 0 00 0 Air Hvrs/ Spent Fuel 40 # 43 1 Storage _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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Page 8 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST AHL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HSF-FAN-2B HSF-ACT- 2B G 519 8E 2ff 01 00000 Centrifugal Fan B515 730 BLD S-9.2 ## 0 00 0 Air Hvrs/ Spent Fuel 40 # 43 1 Storage 22 HSF-FAN-3A HSF-AHU-1A G 498 24C 2ff 01 00000 Centrifugal Fan B515 805BL U-7.2 ff 0 00 0 Air Hovers / Spent Fuel 40 # 43 1 Storage 22 HSF-FAN-3B HSF-AHU-1B G 479 6C 2## 01 00000 Centrifugal Fan B515 805BL U-7.2 ff 0 00 0 Air Movers / Spent Fuel 40 # 43 1 Storage 22 HSF-FAN-4A HSF-AHU-2A G 498 60 200 02 00000 Centrifugal Fan B515 SG5BL U-9.2 00 0 00 0 Air Movers / Spent Fuel 40 # 43 1 Storage 22 HSF-FAN-4B HSF-AHU-2B G 479 6C 200 02 00000 Centrifugal Fan B515 805BL U-9.2 00 0 00 0 Air Movers / Spent Fuel 40 # 43 1 Storage ' 22 IISG-FAN-1A HSG-AHU-01A G 501 14E 2ff 01 00000 Centrifugal Fan BS15 '20 PCH BIG BUFFALO S-3 ## 0 00 0 Air Movers for Safeguards 40 6'6 43 1 Area
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Page 9 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT 9 CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG HFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 HSG-FAN-1B HSG-AHU-018 G 501 14E 2ff 01 00000 Centrifugal Fan B515 720 PCH BIG BUFFALO S-3 ff 0 00 0 Air Movers for Safeguards 40 696 43 1 Area 22 HSG-FAN-2A ilSG-AHU-1A G 501 14E 2ff 01 00000 Centrifugal Fan BS15 9000LD U-3 ff 0 00 0 Air Movers for Safeguards 40 696 43 1 Area , 22 HSG-FAN-28 HSG-AHU-1B G 501 14E 2ff 01 00000 Centrifugal Fan B515 980DLD U-3 ff 0 00 0 Air Movers for Safeguards 40 696 43 1 Area 22 MER-FAN-1A MER-AHU-01A G 501 15E 2ff 01 00000 Centrifugal Fan B515 600 HVH BIG BUFFALO P-3 ## 0 00 0 Air Movers for Mech. Equip 40 696 43 1 Room 22 MER-FAN-1B MER-AHU-)1B G 501 15E 2ff 01 00000 Centrifugal Fan B515 600 HVH BIG BUFFALO P-3 ff 0 00 0 Air Movers for Mech. Equip 40 696 43 1 Room
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' CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 MER-FAN-2A MER-AHU-1A G 501 ISE 2ff 01 00000 Centrifugal Fan B515 980BLD K-3 ff 0 00' 0 Air Movers for Mech. 40 696 43 1 Equip. Room 22 HER-FAN-28 MER-AHU-1B G 501 15E 2ff 01 00000 Centrifugal Fan B515 980BLD K-3 ff 0 00 0 Air Movers for Mech. 40 696 43 1 Equip. Room 22 NER-FAN-4A MER-FAN-4A G 519 2ff 01 00000 Vaneaxial Fan B515 28/18 Vaneaxial P-5 ff 0 00 0 Exhaust Fan for Small 40 696 43 1 Equip. Room 22 MER-FAN-4B MER-FAN-4B G 51 9 2ff 01 00000 Vaneaxial Fan B515 28/18 Vaneaxial P-4 ## 0 00 0 Exhaust Fan for Small 40 696 43 1 Equip. Room
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22 NER-FAN-7A MER-FAN-7A G 449 22A 2ff 01 00000 Vaneaxial Fan B515 29A9 Adjustax W-6.5 ff 0 00 0 Exhaust FN/ Borated Wtr 40 696 43 1 Storage Area 22 MER-FAN-78 MER-FAN-78 G 449 22A 2ff 01 00000 Vaneaxial Fan B515 29A9 Adjustax W-6.5 ff 0 00 0 Wtr Storage Area 40 696 43 1
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CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 22 VAB-FAN-12A VAB-FAN-12A S 448 1A 2## 01 00000 Vaneaxial Fan 3515 29A9 Adjustax PP HSE A ## 0 00 0 Spray Pond /Pmp HS 40 696 43 1 Exhaust 22 VAB-FAN-228 VAB-FAN-22B S 448 1A 2ff 01 00000 Vaneaxial Fan 8515 29A9 Adjustax PP HSE B ## 0 00 0 Spray Pond /Pmp HS 40 696 43 1 Exhaust - i I 4 1
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_ _ _ _ _ _ _ _ _ _ Page 12 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST AHL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EA/A56 APN-SWG-EA/A56 G 421 30B 121 ff 31399 Instrument Compartment G187 Dwg 33-51659-B202 E-10 4# 5 04 4 Provide Monitoring Function 40 2400 43 1 47 APN-SWG-EA/A57 APN-SWG-EA/A57 G 421 30B 121 ff 31399 Instrument Compartment G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Provide Monitoring Function 40 2400 43 1 47 APN-SWG-EA/A58 APN-SWG-EA/A58 G 421 308 121 ff 31399 Instrument Compartment G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Under Voltage to EPSS 40 2400 43 1 47 APN-SWG-EA/A59 APN-SWG-EA/A59 G 421 30B 121 ff 31399 Instrument Compartment G187 Dwg 33-51659-B202 E-10 4# 5 04 4 Provide Monitoring Function 40 2400 43 1 47 APN-SWG-EA/A60 APN-SWG-EA/A60 G 421 30B 121 ff 31399 ALT Backup Feeder Breaker Compartment G187 Dwg 33-51659-8202 E-10 4f 5 04 4 Provide Backup On/0ff Control 40 2400 43 1 47 APN-SWG-EA/A61 APN-SWG-EA/A61 G 421 30B 121 ff 31399 Backup Feeder Breaker G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Provide Redundant Backup 40 2400 43 1 47 APN-SWG-EA/A62 APN-SWG-FA/A62 G 421 30B 121 ff 31399 Blank Electrical Cubicle G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Spare 40 0 00 1
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U U U U U U U U U V u Page 13 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT COMPOSITE EQUIP N0 BLDG ELEV ZONE SEISMIC ENVIRN CONTRACT EQUIPMENT NUMBER DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C SAFETY FUNCTION APN-SWG-EA/A63 G 421 30B 121 ## 31399 47 APN-SWG-EA/A63 Loop Cooling Water Pump CCW-PMP- 5A G187 Dwg 33-51659-B202 E-10 4# 5 04 4 Provide Power Loop CCW-PMP-5A 40 696 23 1 47 APN-SWG-EA/A64 APN-SWG-EA/A64 G 421 30B 121 ## 31399 Unit Substation EA1 G187 Dwg 33-51659-B202 E-10 4# 5 04 4 Distribute Power 40 2400 43 1 APN-SWG-EA/A65 G 421 30B 121 ## 31399 47 APN-SWG-EA/A65 Make Up Pump MUS-PMP-1A G187 Dwg 33-51659-8202 E-10 4f 5 04 4 Provide Power Mu PHP Motor 40 2400 43 1 47 APN-SWG-EA/A66 APN-SWG-EA/A66 G 421 308 121 ff 31399 Auxiliary Feedwater Pump FWA-PMP-1A G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Provide Pow Aux FWA-PMP-1A 40 2400 43 1 47 APN-SWG-EA/A67 APN-SWG-EA/A67 G 421 30B 121 ## 31399 Unit Substation EA4 G187 Dwg 33-51659-8202 E-10 4f 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EA/A68 APN-SWG-EA/A68 G 421 30B 121 ## 31399 Unit Substation EAS G187 Dwg 33-51659-B202 E-10 4# 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EA/A69 APN-SWG-EA/A69 G 421 30B 121 ## 31399 Emgr Shutdawn Pump ESW-PMP-1A G187 Dwg 33-51659-8202 E-10 4# 5 04 4 Provide Poder ESW-PMP-1A 40 2400 33 1
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______ _ .__ Pqge 14 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EA/A70 APN-SWG-EA/A70 G 421 30B 121 ff 31399 Make Up Dump MUS-FMP-3C G187 Dwg 33-51659-8202 E-10 4# 5 04 4 Provide vower MUS-PMP-3C 40 2400 43 1 47 APN-SWG-EA/A71 APN-SWG-EA/A71 G 421 308 121 ff 31399 Unit Substation EA6 G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EA/A72 APN-SWG-EA/A72 G 421 30B 121 ff 31399 Diesel Generator Breaker G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Connect Diesel Gen to Bus 40 2400 33 1 47 APN-SWG-EA/A73 APN-SWG-EA/A73 G 421 308 121 ff 31399 Shutdown Cooling Water Pump Breaker G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Provide Power, SD CW PMP Motor 40 2400 33 1 47 APN-SWG-EA/A74 APN-SWG-EA/A74 G 421 30B 121 ff 31399 Containment Spray Pump CSS-PMP-1A G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Provide Power CSS PHP Motor 40 2400 31 1 47 APN-SWG-EA/A75 APN-SWG-EA/A75 G 421 30B 121 ff 31399 Unit Substation EA2 G187 Dwg 33-51659-8202 E-10 4# 5 04 4 Distribute Power 40 2400 43 1 . 47 APN-SWG-EA/A76 APN-SWG-EA/A76 G 421 308 121 ff 31399 Decay Heat Removal Pump DHR-PMP-1A G187 Dwg 33-51659-B202 E-10 4f 5 04 4 Provide Power DHR PMP Motor 40 2400 33 1
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_ . Page 15 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION WG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EA/A77 APN-SWG-EA/A77 G 421 30B 121 ## 31399 Unit Substation EA3 G187 Dwg 33-51659-8202 E-10 4# 5 04 4 Distribute Power C 2400 43 1
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47 APN-SWG-EA/Z16 APN't"- M/Z16 G 421 30B 121 ## 31399 SWGR datt & Cable Spreading Area Chiller Glu A ; 45-51659-8202 E-10 4# 5 04 4' Provide Power to Chiller O C400 43 1 47 APN-SWG-EA/Z17 APN-SWG-EA/Z17 G 421 30B' 121 ## 31399 Containment Chiller CFC-CHL-1A G187 Dwg 33-51659-8202 E-10 /A 5 04 4 Provide Power CFC-CHL-1A 40 696 43 1 47 APN-SWG-EA/Z18 APN-SWG-EA/Z18 G 421 30B 121 D 31399 Containment Chiller CFC-CHL-2A G187 Dwg 33-51659-8202 E-10 #4 5 04 4 Provide Power CFC-CHL-2A 40 696 43 1 I 47 APN-SWG-EA/Z19 APN-SWG-EA/Z19 G 421 30B 121 ## 31399 Fuel Handling Containment Purge Chiller HSF-CHL-4A G187 Dwg 33-51659-B202 E-10 4# 5 04 4 , Provide Power HSF-CHL-4A 40 2400 43 1 ' 47 APN-SWG-EB APN-SWG-EB G 421 308 121 ## 31399 5 KV Switchgear G187 Dwg 33-51659-8202 E-4 4# 5 04 4 Maintain Circuit Continuity 40 2400 43 ! 47 APN-SWG-EB/A78 APN-SWG-EB/A78 G 421 30B 121 ## 31399 l Instrument Compartment G187 Dwg 33-51b59-B202 E-4 4# 5 04 4 4 Under Voltage to EPSS 40 2400 43 1 I
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ P:ge 16 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EB/A79 APN-SWG-EB/A79 G 421 30B 121 ff 31399 Instrument Compartment G187 Dwg 33-51659-8202 E-4 4# 5 04 4 Provide Monitoring Function 40 2400 43 1 47 APN-SWG-EB/A80 APN-SWG-EB/A80 G 421 30B 121 ff 31399 Main Feeder Breaker G187 Dwg 33-S1659-B202 E-4 4f 5 04 4 Provide On/0ff Control 40 2400 43 1 47 APN-SWG-EB/A81 APN-SWG-EB/AB1 G 421 30B 121 ff 31399 Alt Backup Feeder Breaker Compartment G187 Dwg 33-51659-B202 E-4 4# 5 04 4 Provide Backup Power 40 2400 43 1 47 APN-SWG-EB/A82 APN-SWG-EB/A82 G 421 30B 121 ff 31399 Backup Feeder Breaker G187 Dwg 33-51659-B202 E-4 4f 5 04 4 Provide Redundant Backup 40 2400 43 1 47 APN-SWG-EB/A83 APN-SWG-EB/A83 G 421 30B 121 ff 31399 Emgr Shutdown Pump G187 Dwg 33-51569-8202 E-4 4f 5 04 4 Provide Power 40 2400 43 1 47 APN-SWG-EB/A84 APN-SWG-EB/A84 G 421 30B 121 ff 31399 Unit Substation EB1 G187 Dwg 33-51569-8202 E-4 4f 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EB/A85 APN-SWG-EB/A85 G 421 30B 121 ff 31399 Contn Spray Pump 1-CSS PMP-2-8 G187 Dwg 33-51569-B202 E-4 4f 5 04 4 Provide Power CSS-PMP-2B 40 2400 31 1
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U U Page 17 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EB/A86 APN-SWG-EB/A86 G 421 30B 121 ## 31399 Decay Heat Renoval Pump DHR PMP-2-B G187 Dwg 33-51569-8202 E-4 4f 5 04 4 Provide Power DHR-PMP-28 40 2400 33 1 47 APN-SWG-EB/A87 APN-SWG-EB/A87 G 421 308 121 ##- 31399 Shutdown Water Cooling Pump NSW-PHP-28 G187 Dwg 33-51569-B202 E-4 4f 5 04 4 Provide Power NSW-PMP-2B 40 2400 33 1 47 APN-SWG-EB/A88 APN-SWG-EB/A88 G 421 30B 121 ## 31399 Instrument Compartment G187 Dwg 33-51569-8202 E-4 4# 5 04 4 Under Voltage to EPSS 40 2400 43 1 47 APN-SWG-EB/A89 APN-SWG-EB/A89 G 421 30B 121 ## 31399 Unit Substation EB2 G187 Dwg 33-51569-8202 E-4 4f 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EB/A90 APN-SWG-EB/A90 G 421 30B 121 ## 31399 Auxiliary Feedwater Pump FWA-PMP-2B G187 Dwg 33-51569-8202 E-4 4# 5 04 4 Provide Power FWA-PHP-28 40 2400 43 1 47 APN-SWG-EB/A91 APN-SWG-EB/A91 G 421 30B 121 ## 31399' Blank Electrical Cubicle G187 Dwg 33-51569-8202 E-4 . 4# 5 04 4 Spare 40 0 00 1 47 APN-SWG-EB/A92 APN-SWG-EB/A92 G 421 30B 121 ff 31399 Diesel Generator EDG-DG-18 G187 Dwg 33-51569-B202 E-4 4f 5 04 4 Connect Diesel Gen to Bus 40 2400 33 1
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - _ _ _ Pag 3 18 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACI EQUIPMENT NUMBER COMPOSITE EQUIP N0 BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EB/A93 APN-SWG-EB/A93 G 421 308 121 ff 31399 Unit Substation EB3 G187 Dwg 33-51569-B202 E-4 4f 5 04 1 Distribute Power 40 2400 43 1 47 APN-SWG-EB/A94 APh-SWG-EB/A94 G 421 30B 121 ff 31399 Loop Cooling Water Pump Con PMP 68 G187 Dwg 33-51569-8202 E-4 4f 5 04 4 Provide Power PMP 6B 40 696 23 1 47 APN-SWG-EB/A95 APN-SWG-EB/A95 G 421 30B 121 ff 31399 Make Up Pump MUS-PMP-2B G187 Dwg 33-51569-8202 E-4 4# 5 04 4 Provide Power MUS-PMP-2B 40 2400 43 1 47 APN-SWG-EB/A96 APN-SWG-EB/A96 G 421 30B 121 ## 31399 Auxiliary Feedwater Pump FWA-PMP-2B G187 Dwg 33-51569-B202 E-4 4f 5 04 4 Provide Power FWA-FMP-28 40 2400 43 1 47 APN-SWG-EB/A97 APN-SWG-EB/A97 G 421 30B 121 ff 31399 Unit Substation EB4 G187 Dwg 33-51569-8202 E-4 4f 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EB/A98 APN-SWG-EB/A98 G 421 30B 121 ff 31399 Unit Substation EB5 G187 Dwg 33-51569-B202 E-4 4# 5 04 4 Distribute Power 40 2400 43 1 47 APN-SWG-EB/A99 APN-SWG-EB/A99 G 421 30B 121 ff 31399 Unit Substation EB6 G187 Dwg 33-51569-8202 E-4 4# 5 04 4 Distribute Power 40 2400 43 1
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_ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . Page 19 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 47 APN-SWG-EB/Z21 APN-SWG-EB/Z21 G 421 308 121 ff 31399 Swgr Batt & Cable Spreading Area Chiller G187 Dwg 33-51569-3202 E-4 4# 5 04 4 Provide Power 40 2400 43 1 47 APN-SWG-EB/Z22 APN-SWG-EB/Z22 G 421 30B 121 ## 31399 Containment Chiller G187 Dwg 33-51569-8202 E-4 43 5 04 4 Provide Power 40 696 43 1 47 APN-SWG-EB/Z23 APN-SWG-EB/Z23 G 421 30B 121 ## 31399 Containment Chiller CFC-CHL-28 G187 Dwg 33-51569-B202 E-4 4# 5 04 4 Provide Power CFC-CHL-28 40 696 43 1 47 APN-SWG-EB/Z24 APN-SWG-EB/Z24 G 421 308 121 ## 31399 fuel Handling Containment Purge Chiller G187 Dwg 33-51569-8202 E-4 4# 5 04 4 Provide Power 40 2400 43 1 47 APN-TOS-AB/SBS APN-TOS-AB/SBS G 399 14A Duplex Switch U-3 1 47 BCS-MON-1/ RAS RCS-MON-1/ RAS I 423 2A 121 ## 31399 Reactor Coolant Pump Monitor G187 ISOL VLV 4# 5 04 4 1 47 RCS-MON-2/RA6 RCS-MON-2/RA6 I 423 2A 121 ## 31399 Reactor Coolant Pump Monitor G187 ISOL VLV 4# 5 04 4 . 1
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Pag 3 20 WASHING 10N PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER - COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE IIRS OPR USE QTY DOCUMENT LOCATION F0 C DCE C 47 RCS-MON-3/RA7 RCS-MON-3/RA7 I 423 2A 121 ff 31399 Reactor Coolant Pump Monitor G187 IS9L VLV 4# 5 04 4 1 47 RCS-MON-4/RA8 RCS-MON-4/RA8 I 423 2A 121 ## 31399 Reactor Coolant Pump Monitor G187 ISOL VLV 4# 5 04 4 1 55 APN-EPA-HAI APN-EPA-HAI R 428 4A 15 KV Power Elec Pent Assembly W120 WX33118 55 DEG Provide Cont Isolation 40 2400 43 1 1/S-55-QS-1 55 APN-EPA-HA3 APN-EPA-HA3 R 428 4A 15 KV Elec Pent Assembly W120 WX33118 57 DEG Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HAS APN-EPA-HAS R 428 4A 15 KV Elec Pent Assembly W120 WX33118 60 DEG Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HA7 APN-EPA-HA7 R 428 4A 15 KV Power Elec c Pent Assembly W120 WX33118 62 DEG Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HB4 APN-EPA-HB4 R 495 30 121 00 19199 Control Rod Power Elec Pent Assembly W120 WX33130 95 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 . ~ . , , e -- -- s -, . _ - - _ _ _ - _ _ - . - - _ _
_ _ _ . . . _ _ . _ ._. ._.. _ . ._ .. . _ __. . _ . _ - _ _ . ._. Page 21 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT
- CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL .
TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C D8E C l 55 APN-EPA-HB5 APN-EPA-HB5 R 495 30 121 00 19199 Control Power Rod Elec Pent Assembly W120 WX-33130 99 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HB6 APN-EPA-HB6 R 495 3D 121 00 19199 Control Power Rod Elec Pent Assembly W120 WX-33130 104 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HB7 APN-EPA-HB7 R 495 30 121 00 19199 Control Power Rod Elec Pent Assembly W120 WX-33130 108 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HB8 APN-EPA-HB8 R 495 30 121 00 19199 Control Power Rod Elec Pent Assembly W120 WX-33130 112 DEG 40 5 07' 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HB9 APN-EPA-HB9 R 491 30 121 00 19199 Control Rod Position Indicator Elec Pent Assembly W120 WX-33130 95 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-hcl APN-EPA-hcl- R 491 30 121 00 19199 Control Rod Position Indicator Elec Pent Assembly W120 WX-33131 99 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 j l ___ _ _
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ WASHINGTON PUBLIC POWER SUPPLY 5" STEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 55 APN-EPA-HC2 APN-EPA-HC2 R 491 30 121 00 19199 Control Rod Positior. Indicator Elec Pent Assembly W120 WX-33131 104 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HC6 APN-EPA-HC6 R 491 30 121 00 19199 Control Rod Thermocouple Elec Pent Assembly W120 WX-33126 108 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HC9 APN-EPA-HC9 R 444 IB 121 00 19199 Pressurized Heaters Power Elec Pent Assembly W120 HX-33132 218 DEG 40 5 07 4 P: ovide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HD1 APN-EPA-HD1 R 444 IB 121 00 19199 Pressurized Heaters Power Elec Pent Assembly W120 WX-33132 221 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HE2 APN-EPA-HE2 R 467 1C 121 00 19199 Signal Cable Reactor Protect Sys Elec Pent Asly W120 WX-33127 207 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HE4 APN-EPA-HE4 R 467 1C 121 00 19199 General Use Control Power AC & DC EPA W120 WX-33120 212 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1
- _ . J O . _ - - - - - -
* * * * * * * *
- _ _ - _ _ _ _ _ _ - _ - .
- U U U U U U U U U C C
. Page 23 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP N0 BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 55 APN-EPA-HE8 APN-EPA-HE8 R 471 1C 121 00 19199
'
General Use Low & Medium Power AC Elec Pont Asly W120 WX-33121 215 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HF6 APN-EPA-HF6 R 467 1C 121 00 19199 Instrum Thermocouples
& RTD's Elec Pent Asly W120 WX-33123 215 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HG4 APN-EPA-HG4 R 444 3B 121 00 19199 Signal Cable Incore Instrum Elec Pent Assembly W120 WX-33128 158 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-R11 APN-EPA-HH1 R 444 3B 121 00 19199 Signal Cable Incore Instrum Elec Pent Assembly W120 WX-33129 167 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HH3 APN-EPA-HH3 R 444 3B 121 00 19199 Signal Cable Reactor Protection Sys Elec Pent Asly W120 WX-33127 101 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HHS APN-EPA-WIS R 444 3B 121 00 19199 Instrum Thermocouples & RTD's Elec Pent Asly W120 WX-33123 112 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . Paga 24 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C OBE C 55 APN-EPA-HH6 APN-EPA-HH6 R 444 38 121 Ob 19199 General Use Control Power AC & DC Elec Pent Asly W120 WX-33120 107 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HH8 APN-EPA-HH8 R 448 38 121 00 19199 General Use Low & Medium Power AC EPA W120 WX-33121 112 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HIS APN-EPA-HIS R 444 IB 121 00 19199 Signal Cable Reactor Protect Sys Elec Pent Asly W120 WX-33127 207 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HI7 APN-EPA-HI7 R 444 1B 121 00 19199 General Use Control Power AC & DC Elec Pent Asly W120 WX-33120 212 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 . 55 APN-EPA-HI8 APN-EPA-HI8 R 448 IB 121 00 19199 l General Use Heavy Power AC Elec Pent Asly W120 WX-33122 212 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HJ1 APN-EPA-HJ1 R 448 18 121 00 19199 General Use Heavy Power AC Elec Pent Asly W120 WX-33122 221 DEG 40 5 07 4 Provide Cont Isolation 40 2400 43 1 1/4-55-QS-1 i
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O O V O O O O O 0- G- V -- Page 25 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C OBE C 55 APN-EPA-HK3 APN-EPA-HK3 R 463 3C 121 00 19199 Signal Cable Reactor Protect Sys Elec Pent Asly W120 WX-33127 141 DEG 40 5 07 4 Cont Isol-Maint CKT Integrity 40 2400 43 1 1/4-55-QS-1 55 APN-EPA-HK5 APN-EPA-HK5 R 463 3C 121 00 19199 Instrum Thermocouple & RTD's Elec Pent Assembly W120 WX-33124 152 DEG 40 5 07 4 Provide Cont Isolation 40 .2:400 43 1 1/4-55-QS-1 87 FWS-V-16B FWS-V-16B I 463 1B 000 01 00000 Main Feedwater Isolation Valve A391 A/DV Dwg 54-14730 VLV HSE 43 5 00 0 Prov FW Line Containmt Isolat 40 2400 43 1 1/4-87-QS-1 87 FWS-V-17A FWS-V-17A I 463 IB 000 01 00000 Main Feedwater Isolation Valve A391 A/DV Dwg 94-14731 VLV HSE 4: 5 00 0 Prov FW Line Containmt Isolat 40 '2400 43 1 1/4-87-QS-1 87 FWS-V-288 FWS-V-28B I 463 2C 000 01 00000 Main Feedwater Isolation Valve A391 A/DV Dwg 94-14730 VLV HSE 43 5 00 0 Prov FW Line Containmt Isolat 40 2400 43 1 1/4-87-QS-1 87 FWS-V-29A FWS-V-29A I 463 28 000 01 00000 Main Feedwater Isolation Valve A391 A/DV Dwg 94-14731 VLV HSE 43 5 00 0 Prov FW Line Containmt Isolat 40 2400 43 1 1/4-87-QS-1
_ _ _ _ _ _ _ _ _ _ _ _ Page 26 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPOR1 CONTRACT EQUIPMENT NUMBER COMPOSITE EQUIP NO BLOG ELEV ZONE SEISMIC ENVIRN DESCRIPTION MFG MFG MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C 87 MSS-V-1C MSS-V-1C I 471 1C 000 01 00000 Main Steam Isolation Valve A391 A/DV Dwg 94-14396 VLV 95f. 43 5 00 0 , Prov HS Line Containmt Isolat 40 2400 43 1 1/4-Bi-QS-1 87 MSS-V-2C MSS-V-2C I 471 1A 000 01 00000 Main Steam Isolation Valve A391 A/DV Dwg 94-14395 VLV HSE 43 5 00 0 Prov MS Line Cnntainmt Isolat 40 2400 43 1 1/4-87-QS-1 87 MSS-V-3C MSS-V-3C I 471 2C 000 01 00000 Main Steam 7 ation Valve A391 A/DV Dwg 94-14395 VLV HSE 43 5 00 0 Prov MS Line uontainmt Isolat 40 2400 43 1 1/4-87-QS-1 87 MSS-V-4C MSS-V-4C I 471 2C 000 01 00000 Main Steam Isolation Valve A391 A/DV Dwg 94-14397 VLV HSE 43 5 00 0 Prov MS Line Containmt Isolat 40 2400 43 1 1/4-87-QS-1 104 APN-ELC-GA25/030 APN-ELC-GA25 G ### ff 53193 Electrical Power Cable-1/C-250MCM-5KV 0040 114-23-2533 General Plant if f 01 4 Cond Elect-Maint CKT Integrity LOT 1/4-104-QS-1 104 APN-ELC-GA35/031 APN-ELC-GA35 G fil ## 53193 Electrical Power Cable-1/C-350MCM-5KV 0040 114-23-2537 General Plant il f 01 4 Cond Elect-Maint CKT Integrity LOT 1/4-104-QS-1 104 APN-ELC-GA41/029 APN-ELC-GA41 G ### ## 53193 Electrical Power Cable-1/C-350MCM-5KV 0040 114-23-2531 General Plant if f 01 4 Cond Elect-Maint CKT Integrity LOT 1/4-104-QS-1
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U U U ,, U U U U U U _U U Page 27 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CLASS 1E EQUIPMENT LIST MASTER REPORT
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CONTRACi EQUIPMENT NUMBER COMPOSITE EQUIP NO BLDG ELEV ZONE SEISMIC ENVIRN DESCRIPTION WG W G MODEL NUMBER LOC. DETAIL TEST ANL AGING SAFETY FUNCTION LIFE HRS OPR USE QTY DOCUMENT LOCATION F0 C DBE C , 104 APN-ELC-GA50/032 APN-ELC-GA50 G ### ## 53193 Electrical Power Cable-1/C-500MCM-5KV 0040 114-23-2543 General Plant ## # 01 4 Cond Elect-Maint CKT Integrity LOT 1/4-104-QS-1 , ! 4 i _ _ - - - - - - - - -
3 I WASHINGTON PUBLIC POWER SUPPLY SYSTEM ACCEPTANCE CRITERIA FOR CLASS 1E EOUIPMENT QUALIFICATION ! O 1.0 PURPOSE AND SCOPE This instruction establishes the criteria to which Class IE equipment qualification plans and test results are evaluated to determine adequacy to meet the requirements of IEEE 323-1974, or its daughter O standards that are endorsed by Regulatory Guides and/or NRC documents. 2.0 EF)4ITIONS~ The definitions section provided in IEEE 323-1974, or its daughter standards apply. 3.0 PROCEDURE The following criteria shall be considered when Class 1E equipment qualification documents are being reviewed. 3.1 Contents of the Vendor Qualification Program g The following information is required of all Class IE qualifica-tion programs.
- 1. Identification of all Class IE equipment, components and sub-components as follows:
O
- a. Functional designation
- b. Manufacturer
- c. Manufacturer's type number and/or model number
- d. Applicable equipment, component, or sub-component description (motor control center, relay, transistor, O etc.)
- 2. Equipment safety function category:
'
- a. Equipment that will exoerience the environmental conditions of design basis accidents for which it must function to
.g mitigate said accidents, and that will be qualified to demonstrate operability in the accident environment for ' the time required for accident mitigation with safety margin to failure.
- b. Equipment that will experience environmental conditions Uy of design basis accidents through which it need not function for mitigation of said accidents, but through which it must not fail in a manner detrimental to plant safety or accident mitigation, and that will be oualified to demonstrate the capability to withstand any accident environment for the time during which it must not fail' 1 with safety margin to failure.
g _ _ _ _ - _ - _ _ _ _ _ _ _ _ __ _. - - . -_ - -
O tad
- c. Equipment aht will experience environmental conditions of design basis accidents through which it need not function for mitigation of said accidents, and whose '
g failure (in any mode) is deemed not detrimental to plant safety or accident mitigation, and need not be qualified for any accident environment, but will be qualified for its non-accident service environment.
- d. Equipment that will not experience environmental O conditions of design basis accidents and that will be '
qualified to demonstrate operability under the expected extremes of its non-accident service environment. This equipment would normally be located outside the reactor containment.
- 3. For each type of eautoment in the categories of equipment > #
listed in item 2 above, provide separately the equioment design specification requirements, including:
- d. The system safety function reouirements,
- b. An environmental envelope as a function of time that ) G includes all extreme parameters, both maximum and minimum values, expected to occur durino plant shut-down, normal operation, abnomal ooeration, and any design basis event (including LOCA and MSLB), includinn post-event conditions.
- c. Time required to fulfill its safety function when sub-jected to any of the extremes of the environment envelope specified above.
- d. Technical bases should be provided to justify the placement of each type equinment in the categories g 2.b and 2.c listed above.
4 Provide the qualification test plan, test procedures, and acceptance criteria for at least one of each groun of equip-ment of item 1.d as appropriate to the category identified in item 2 above. If any method other than type testing was used for qualification (operating experience, analysis, 8 i combined qualification, or ongoinq qualification), describe l the method in sufficient detail to permit evaluation of its adequacy. l -
- 5. For each category of equipment identified in item 2 above, ~,
state the actual qualification envelope simulated durino G testing (defining the dcration of the hostile environment and the margin in excess of the design requirements). If any method other than type testing was used for cualification, identify the method and define the equivalent " qualification envelope" so derived. O
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- 6. A sumary of test results that demonstrates the adequacy of the qualification program. If analysis is used for
)
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oualification, justification of all analysis assumptions must be provided.
- 7. Identification of the qualification documents which contain detailed supporting infonnation, including test data, for items 4, 5 and 6.
The Equipment Qualification Check List is included as part of the documentation package. The list is included in this Appendix as an attachment. I 3 J J J J J J
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3 , TABLE I ) MARGINS TO BE USED IN CONJUNCTION WITH SPECIFIED SERVICE CONDITIONS
- 1. Temnerature +15 F (8 C) - for saturated congi-tions. Test shall not exceed Sat
) + 10 psi for the peak service temperature.
- 2. Pressure +10% of gauce but not more than 10 psi.
J 3. Radiation +10% on accident dose.
- 4. Voltage +, -5% of rated value unless otherwise specified. *
- 5. Time +10% of the time period the
- ) equipment is required to be function 31 following the DBE -
1 hour, minimum. *
- 6. Environmental Transients The initial transient and the swell at peak temperature shall be applied g, _ at least twice.
- 7. Vibration +10% added to the acceleration of the response spectrum at the mounting point of the eauipment.
3 D D D
*A lesser margin may be used--provided adeauate justification is provided.
3
.
) ATTACHMENT CHECK LIST ECUIPMEN* OUALIFICATION This check list is designed as an aid in reviewing Class 1E Equipment Qualification Reports to assure that the objectives of IEEE 323-1974
) and NUREG-0588 have been met. Like components with the same environ-mental and seismic characteristics can be listed on one sheet, as a supplement to this list.
.
D I. IDENTIFICATION Equipment Equipment Functional tocation Manufacturer Manufacturer WPPSS WPPSS Designation Model/ Type Technical Tag Bldg. Elev. Specification Number (s)
) Number
__ D ADDITICNAL INFORMATICN (REF: NUREG-0588, APPX. E, SECICN 1d) : D II. OPERABILI*Y RECUI?L'4ENTS Environmental Design Time Required Nature Equipment Designator Basis To Operate of Category (F m le Accident During DBA Cperation (NUREG-0588, Appx. E, Sect.2)
)
1 D EQUIPMENT FUNCTICN: I ! l , P ! t i , t
, _ _ _ _ _ _ _ _ _ _ . _ _ , . _ , _ _ . . _ _ , _ _ _ _ _ _
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III. OUALIFIED ENVIRCNMENT Complete Exhibit 1 (Attached). Compare Exhibit 1 to FSAR designated service cond'. tion. Does supplier's qualified service meet or exceed 3 ' (D ; the FSAR requirements? _
,
YES - Proceed to Item IV
~~~ -1 GD NO - Describe the difference. Indicate whether differences will
---- impair the equipment function. Justify any conclusions that qualification to less than full service requirements is acceptable. (Attach additional sheets as required.)
) GD
' GD
)
GD IV. MARGIN Identify margins, if any, provided by the equipment qualification on Exhibit 2 (attached). Compare the listed margins to the suggested IEEE 323-1974 values. Provide justification for any margin values gg listed less than the recommended IEEE 323-1974 values. The radiation margin suggested in IEEE 323 may be neglected if the metnods in Appendix D of NUREG-0588 are used. Time margins indicated for short time period functioning devices must be justified if the margin indicated is less than 1 hour. . O Are the margins acceptable?
.-
YES - Proceed to Item V. _.
" " ~ O NO - Describe differences and indicate whether differences are
'
__ - significant
-
SIGNIFICAIC NOT SIGNIFICAIC
-
9 JUST!FICATICN:
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be V. _ EQUIPMENT MCUan NG AND CRIENTATION
- 1) was equipment qualified for a unique installed orientation (horizontal, vertical, etc)? Specifv orientation of required
] installation (check all that are T.armissible).
- -
HCRIZCNTAL (FLCCR) HCRIZCNTAL (WALL) ;
- -
3 _ VERTICAL (FLCCR)
-
VERTICAL (WALL) _ -
-
HCRIZONTAL, ELE 7ATED (PIPING, DUCT, ETC.)
-
VERTICAL, ELEVATED (PIPING, DUCT, ETC.) CANTED AT DEGREES FRCM VERTICAL (PIPING, DUCT, ETC.) )' CTHER - CIARIFY ,
- 2) Seismic test c:cunting method (welding, bolts, rivits, etc.)
) Was test mount the same as the intended site installation?
-
YES - Proceed to Item VI.
.
J( _ NO - Explain -
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D-D
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D g.
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O VI. QUALIFICATION METHCD SEISMIC
- 1) Identify qualification method ENVIRCf0(ENTAL 1
0
- TYPE TEST - REPORT No.
- ANALYSIS - REPORT No.
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- CPERATING EXPERIENCE - REPORT No.
-
-
CN-GOING QUALIFICATICN - REPORT No. O
>
_ _ CCMBINATION OF METHCDS (CHECK AND IDENTIFY ALL THAT APPLY)
-
- 2) Describe the qualification method. Identify codes and standards utilized. ) $
Discuss all extrapolations from test data that supplier claims qualify different items by extension. If on-going qualification is used, describe initial qualified life of the equipment and identify the scope of inspec-tien, re-testing or analysis to maintain and extend this qualified life. (Attach a separate sheet, if required.)
>G
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- 3) Were type tests conducted in the following sentence? List supplier justification for emitted steps or variation in test sequence.
O
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- a. Inspection YES - Proceed to 4).
- b. Operation (Baseline) -
- c. Operation (Environmental Extremes)
Aging: NO - Provide supplier d. i) Thermal
- justification and g compare actual test
- 11) Radiation lii) Humidity sequence severity.
iv) Mechanical Cycling v) Vibration
- e. Cperation (Baseline)
- f. Seismic '
O
- g. Operation (Baseline)
- h. DBA Cperation
- 1. Post-CBA Operation & Inspection ,
ECUIPMENT IS NOT QUALIFIED 9 l
-
i
- ,x
- 4) Are any synervistic effects known to exist with this equipment?
~
YES - Describe the method used to age the eculpment ]
-
.
l- _ NO - The test sequence in Item 3) applies, as necessarf.
- 5) Are chemical effects, existing in the equipment's mounting space, detrimental to the equipment safety function?
-
YES - Explair. means of protection D
-
NO - Not Applicable
-
) 6) Is submergence a factor in the location of this equipment?
-
YES - Explain means of protection
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] ,
-
NO - Kot a factor.
-
D
- 7) Does the equipment perform satisfactorily in its eperational mode before, during and after the testing?
) YES - Cescribe the operational parameters monitored _ NO - Explain the corrective action ] D-
. . . - - - - - -- - - - - . . _ _ - - . . - _-
.
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- 8) Provide additional test information as follows:
1 O
- a. The environmental extremes ir. Exhibit 1 meets or exceeds the parameters of the FSAR, Table 3.11.1- , plus margin.
-
YES
-
- G NO - Justify
-
>G
- b. Thecul Aging Methods
-
Arrhenius, describe adequacy ) g
-
l ' _ Other, describe adequacy
-
) S
.__
- c. Was the aging justification of IEEE 650-1979, Section 5.1.2.1- 1 used?
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'
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YES - Explain the adequacy of the stress analysis presented and
-
justify the non-harsh environment in which the equipment is to be used. O 1 l , I , J
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Not Applicable 9
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Ov 1
- d. Radiation exposure (aging and accident dose) value (Exhibit 1) conforms to the value specified in FSAR, Table 3.11.1- , plus margin.*
l 0 \ l
-
YES -
-
NO - Explain and justify
-
- 9
,_
- Margin may be omitted if the values in FSAR, Table 3.11.1-U were derived usin-J the methods of ICREG-0588, Appx. D. s
- e. Humidity aging was addressed by 0'
- f. Vibration aging was addressed by 3
o
.
. D 3 1 1
)
_ _ . . . ._
.
.
3 ()
- g. Test temperatures were measured by:
-
Direct Mounted Thermocouples .- Other - Describe and justify
-
, GD
- h. Seismic Qualification Method
-
Random, Multi-Frequency, Biaxial Testing - Proceed to 1. ) GD
-
.- Single Axis Testing - Proceed to j.
- -
45 Degree Inclined Plane, Biaxial Testing - Proceed to k. , gg
- -
Analysis - Proceed to 1.
-
ID
- 1. The seismic testing consisted of 5 CBE's and 1 SSE per equipment orientation for a total of 12 test runs?
-
TES - Proceed to Item m.
""" ,
q)
-
NO - Explain and justify
,,,
9
- j. Single axis testing was justified by one of the following?
-
The characteristics of the seismic input motion produce equipment motion
"""
dominated by a single frequency (i.e., structural filtering effects). O The anticipated response of the equipment is represented by one mode.
-
The test input motion has sufficient intensity and duration to excite all
---' modes to the required amplitudes, such that the testing response spectra '
gg will envelope the corresponding response spectra of the individual modes.
-
None of the above, explain and justify
-
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$) r '
- k. The seismic testing consisted of 5 CBE's and 1 SSE per equipment
.
orientation for a total of 24 test runs.
-
_ YES - Proceed to Item m.
-
,,,
NO - Explain and justify
- 2) ,
- 1. The equipment stress analysis report was reviewed and approved?
-
YES - Proceed to Item m. D NO - Explain and justify
-
D
- m. The seismic testing and/or analyses envelope the WPPS3 specified seismic levels?
D YES - Proceed to Item n.
-
-
NO - Explain and justify
-
D
- n. The performance characteristics monitored were:
O D u
C' i
- o. Satisfactory perfonnance was exhibited under nominal and extreme power supply conditions? g Envim nmental "'estina hiemi- *==*4~-
YES YES
-
_ l NO - Explain NO - Exclain g _ i O
- p. Performance characteristics during testing were monitored in what manner?
Environmental Testina seismic Testinc
~
) G
.-
Continuously Continuously
-
,-
M Intermittently, at intervals Intermittently, at intervals _,
) G Other - Explain Other-Explain i e
- q. Does the test report (s) identify that ':he instrumentation was in current calibratier. and traceable to the National Bureau of Standards?
Envircranental Testing Seismic Testina G
,- -
YES YES
-
-
NO - Explain NO - Explain g
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- 10) Did the qualification test interfaces (electrical connections, piping, i supports, etc.) simulate the installed condition?
-O Seismic Testina Environmental Testing
-
YES YES
- -
- 1
-
NO - Explain MO - Explain )
- - ;
Q 'g VII. EVALUATICN .
- 1) The equipment qualified life ist f
-
O 40 Years i
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Other - Specify life and replacement schedule
-
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- 2) Cocumentation l
i Supplier Summary Proprietary (YES/MO,
- O Report Number (s) Report Number Subject (If Yes, Identify Location)
I . Q 4 3) Is the qualification report (s) acceptable to WPPSS? Envircnmental Repcrt Seismic Report i ,0 - YES YES _ 'j - - NO - Exp'ain l NO - Explain O _ i l l G 1 0 l
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EXHIBIT 2
% QUALIFICATICN MARGIN CCMPARED WITH THE REQUIRED CESIGN PARAME'"ERS (FSAR TABLE 3.11.1- )
CONDITICN CESIGN BASIS ACCICENT 'O PAFAMETER
" ^
MSLB LCCA TEMPERATURE, % PRESSURE, % RADIATICN, % _ VOLTAGE, % FREQUENCY, % TIME, % O( E!NIROt24E! CAL f3ANSIENTS, t VISRATICN, % O Q' E
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) I D g The above is true and correct to the best of my knowledge. PFLMY RWIEWER (AE) (CA3) )r SECONCARY REVIEWER (WPPSS) (DATE) 0( 0' 3 ,. D'
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_ _ _ - . _ _ _ _ - -_ _.. . _ _ _ _ _ - _ - . _ _ _ - - _ ~}}