ML20040E789
| ML20040E789 | |
| Person / Time | |
|---|---|
| Site: | 05000470 |
| Issue date: | 01/31/1982 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20040E788 | List: |
| References | |
| CENPD-255, CENPD-255-R03, CENPD-255-R3, NUDOCS 8202050369 | |
| Download: ML20040E789 (150) | |
Text
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CENPD - 255
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Rev 3 1
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CLASS IE l;
QUAllFICATION
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! QUALIFICATION OF CLASS IE ELECTRICAL EQUIPMENT o
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January,1982 l'
WPOWER
=iSYSTEMS CCMBUSTICN ENGINEERING. INC
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r LEGAL NOTICE This report was prepared as an account of work sponsored by Combustion Engineering, Inc. Neither Combustion Engineering nor any person acting on its behalf:
A.
Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefullness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or B.
Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, i
method or process disclosed in this report.
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ABSTRACT Qualification of Combustion Engineering Class lE Electrical Equipment (CENPD-255)
This report describes the methods used to meet the requirements of IEEE Std. 323-1974 and the " Category I" requirements of NUREG-0588.
The methods described herein apply to Combustion Engineering supplied Class lE electrical equipment for nuclear power plants committed to the above requirements. The general scope of various qualification programs is discussed. The types of equipment included and data on these systems, modules, and components are discussed. Type test, analysis, and other methods of qualification compliant with NUREG-0588 are presented. Documentation for qualification activities is described with a sample qualification data summary and evaluation form provided.
It is expected that this report may be referenced by license applicants for the scope and methods to be employed for qualification of C-E supplied Clast lE electrical equipment.
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QUALIFICATION OF CLASS lE ELECTRICAL EQUIPMENT d
TABLE OF CONTENTS Section Title Page No.
1.0 INTRODUCTION
1-1 1.1 Objectives 1-1 1.2 Background Information 1-1 1.3 Criteria and Standards 1-3 1.4 Summary 1-3
2.0 REFERENCES
2-1 3.0 SCOPE OF QUALIFICATION PROGRAM 3-1 3.1 Plants Referencing Report 3-1 3.2 Scope of Supply and Interface Requirements 3-1 3.3 Qualification Program 3-2 3.3.1 Aging 3-3 3.3.2 Seismic 3-4 3.3.3 Environmental 3-4 3.4 Environmental Conditions and Effects 3-5' 3.4.1 Temperature 3-5 3.4.2 Radiation 3-8 3.4.3 Vibration 3-10 3.4.4 Pressure 3-10 3.4.5 Humdity 3-10 3.4.6 Chemical Spray 3-11 3.4.7 Dust 3-11 3.4.8 Submergence 3-12 3.4.9 Power Supply Voltage and Frequency Variat on 3-12 11
TABLE OF CONTENTS (Cont.)
l Section Title Page No.
4.0 EQUIPMENT REQUIRING QUALIFICATION 4-1 4.1 Systems and Modules 4-1 4.1.1 Process Instrumentation 4-1 4.1.2 Nuclear Instrumentation 4-1 4.1.3 Reactor Coolant Pump Shaft Speed Sensing System 4-2 4.1.4 CEA Position Indication System 4-2 4.1.5 Plant Protection System Cabinet 4-2 4.1.6 ESFAS Auxiliary Relay Cabinet 4-3 4.1.7 DNBR/LPD Calculator System 4-3 4.1.8 Supplementary Protection System 4-4 4
4.1.9 Miscellaneous Modules 4-4 4.2 Isolators 4-5 4.2.1 Remote Input Subsystem 4-5 4.2.2 CEA Position Isolation Assembly 4-5 4.2.3 Process Signals 4-5 4.2.4 Digital Isolation Device Assembly 4-6 4.3 Nuclear Service Valves and Auxiliary Equipment 4-6 4.3.1 Electric Valve Motor Operators for Nuclear Service Valves 4-6 4.3.2 Electric Solenoid Process System Nuclear Service Valves 4-7 4.3.3 Electric Solenoid Operated Pneumatic Pilot Valves for Nuclear Service Valves 4-7 4.3.4 Electric Limit Switches for Open/Close Position Indication for Nuclear Service Valves
.4-7 4.4 Pump Motors 4-7 4.4.1 High Pressure Safety Injection Pump Motor 4-8 4.4.2
, Low Pressure Safety Injection Pump Motor 4-8 4.4.3 Containment Spray Pump Motor 4-8 4.4.4 Charging Pump Motor 4-8 4.4.5 Spray Chemical Addition Pump Motor 4-8 iii l
TABLE OF CONTENTS (Cont.)
Section Title Page No.
4.5 Non-Safety Related Equipment 4-9
- 4. 6 Equipment Qualification Requirements 4-9 4.6.1 Location 4-9 4.6.2 Environment 4-10 4.6.3 Design Basis Event 4-10 4.6.4 Operating Requirements 4-10 4.6.5 Equipment Categorization 4-11 5.0 METHODS OF QUALIFICATION 5-1 5.1 Type Tests 5-1 5.1.1 Equipment Specifications 5-1 5.1.2 Type Test Methods 5-2 5.1.3 Margins 5-3 5.1.4 Test Sequence 5-10 5.1.5 Type Test Reports 5-13 5.1.6 Environmentai Test Profiles 5-13 5.1.7 Acceptance Criteria 5-14 5.1.8 Test Anomalies 5-16 5.2 Analyses 5-17 5.2.1 Analyses Based on Partial Type Test Data and Equipment Specific Qualification Requirements 5-17
- 5. 2. 2 Environmental Conditions Calculations 5-19 5.2.3 FMEA 5-19 5.3 Aging 5-21 5.3.1 Aging Analysis and Conditioning 5-21 5.3.2 Periodic Replacement 5-26 5.3.3 Surveillance / Preventive Maintenance 5-27 5.4 Conservatism of Qualification Parameters 5-28 iv
L TABLE OF CONTENTS (Cont.)
Section Title Page No.
6.0 DOCUMENTATION 6-1 6.1 Equipment Specific Qualification Documentation 6-1 6.1.1 Aging Analysis Report 6-1 6.1.2 Qualification Plan 6-2 6.1.3 Age Conditioning Report 6-2 6.1.4 Qualification Test Procedure 6-2 6.1.5 Qualification Test Report 6-3 6.2 Qualification Data Summary and Evaluation 6-3 6.3 Supporting Analytical and Test Data 6-4 7.0 QUALITY ASSURANCE 7-1 8.0 ADMINISTRATIVE PROCEDURES 8-1 8.1 Equipment Specification 8-1 8.2 Vendor Design and Qualification Program 8-1 8.3 Qualification Task 8-1 8.4 Qualification Documentation and Submittals 8-1 l
l LIST OF APPENDICES Appendix Title Page No.
A Typical Class lE Electrical Equipment and Data Listing A-1 B
Typical Environmental Conditions and Test Profiles B-1 C
Typical Qualification Plan for Class lE Equipment Located in a Harsh Environment C-1 0
Typical Qualification Plan for Class 1E Equipment Located in a Non-Harsh Environment D-1 E-1 E
Bibliography j
F Basis for Pump and Valve Operation Parameters F-1 v
LIST OF TABLES Table Title Page No.
5-1 Typical Operation and Accuracy Requirements 5-29 5-2 Qualification Data Summary and Evaluation Form 5-30 TABLES OF APPENDI/, A A-1 Class 1E Electrical Equipment and Data Listing A-2 TABLES OF APPENDIX B B-1 Category "A-1" Environmental Conditions B-4 B-2 Category "A-2" Environmental Conditions B-5 B-3 Category "B" Environmental Conditions B-6 B-4 Category "C" Environmental Conditions B-7 B-5 Category "D" Environmental Conditions B-8 B-6 Category "E" Environmental Conditions B-9 B-7 Category "F" Environmental Conditions B-10 l
B-8 Category "G" Environmental Conditions B-11 B-9 Category "H" Environmental Conditions 8-12 B-10 Category "I" Environmental Conditions B-13 B-11 Category "J" Environmental Conditions B-14 B-12 Category "K" Environmental Conditions B-15 l
B-13 Category "V-1" Environmental Conditions 8-16 8-14 Category "V-2" Environmental Conditions B-17 TABLES OF APPENDIX C C-1 Equipment Qualification Plan - RCP Shaft Speed Sensor and i
Pulse Transmi.tter C-3 TABLES OF APPENDIX D l
D-1 Equipment Qualification Plan - Remote Shutdown Panel 0-3 l
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LIST OF FIGURES Figure Title Page No.
4-1 Typical Process Channel Instrumentation Channel Block Diagram 4-12 4-2 Nuclear Instrumentation System Block Diagram Safety Channels 4-13 4-3 Reactor Coolant Pump Speed Sensing System Block Diagram 4-14 4-4 CEA Position Indicating System Block Diagram 4-15 4-5 DNBR/LPD Calculator System Block Diagram 4-16 4-6 Plant Monitoring System Isolation Block Diagram 4-17 4-7 Electric Valve Motor Operators for Nuclear Service Valve Block Diagram 4-18 4-8 Electric Solenoid Process System Nuclear Service Valve Block Diagram 4-19 4-9 Electric Solenoid Operated Pneumatic Pilot Valve for Nuclear Service Valve 4-20 4-10 Electrical Limit Switches for Open/Close Position Indication for Nuclear Service Valves Block Diagram 4-21 4-11 Pump Motor Block Diagram 4-22 5-1 Maximum Time to Trip versus Steam Line Break Area for Indicated Trips 5-8 5-2 Maximum Time to Trip versus Steam Line Break Area for CPC Low DNBR Trip 5-9 FIGURES OF APPENDIX B B-1 Typical Containment Atmosphere Temperature Condition Following LOCA B-18 B-2 Typical Containment Atmosphere Pressure Ccndition Following LOCA B-19 B-3 Typical Annulus Atmosphere Temperature Condition Following LOCA/MSLB B-20 B-4 Typical Containment Atmosphere Temperature Condition Following MSLB B-21 B-5 Typical Containment Radiation Dose Following LOCA B-22 B-6 Typical Containment Gamma Dose Rate Following LOCA B-23 vii
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LISTOFFIGURES Figure Title Page No.
B-7A Typical Containment Building Environmental Test Profiles for Category "A-1" "A-2", and "V-1" Environmental Conditions B-24 B-7B Typical Containment Building Environmental Test Profiles for Category "A-1", "A-2", and "V-1" Environmental Conditions B-25 B-8 Typical Environmental Test i,1 file for Category "C" Environmental Conditions B-26 B-9 Typical Inside Cabinet Environmental Test Profile for Category "C" Environmental Conditions B-27 B-10 Typical Environmental Test Profile for Category "H" and "J" Environmental Conditions B-28 B-ll Typical Inside Cabinet Environmental Test Profile for Category "H" and "J" Environmental Conditions B-29 viii
LIST OF ACRONYMS Acronym Meaning A/E Architect / Engineer APC Auxiliary Protective Cabinet ARC Auxiliary Relay Cabinet CEA Control Element Assembly CEAC Control Element Assembly Calculator CEDM Control Element Drive Mechanisms CEDMCS Control Element Drive Mechanism Control System CHGP Charging Pump CIAS Containment Isolation Actuation Signal CPC Core Protection Calculator CPIA Control Element Assembly Position Isolation Assembly CPPS Compartmented Plant Protection Systems CPU Central Processing Unit CSP Containment Spray Pump CSAS Containment Spray Actuation Signal CSS Containment Spray System CVCS Chemical and Volume Control System DBE Design Basis Event DIDA Digital Isolation Device Assembly DNBR Departure from Nucleate Boiling Ratio ECCS Emergency Core Cooling System EFAS Emergency Feedwater Actuation Signal EMI Electro-Magnetic Interference ESFAS Engineered Safety Features Actuation System E/I Voltage-to-Current FMEA Failure Modes and Effects Analysis ix
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7 LIST OF ACRONYMS (Cont.)
Acronyms Meaning HPSIP-High Pressure Safety Injection Pump HWAS Hard Wired Annunciators System I/E Current-to-Voltagt I/O Input / Output IRS Iodine Removal System LOCA Loss of Coolant Accident LPD Local Power Density l
LPSIP Low Pressure Safety Injection Pump i.
MSIS Main Steam Isolation Actuation Signal 1
MSLB Main Steam Line Break NI Nuclear Instrumentation OCIS Optical Communications Interface System i
PWR Pressurized Water Reactor PMS Plant Monitoring System PPS Plant Protection System l
RAS Recirculation Actuation Signal.
RCP Reactor-Coolant Pump RCPSSS Reactor Coolant Pump Shaft Speed Sensor RDT Reactor Drain Tank I
RIS.
Remote Input Subsystem i
RPS Reactor Protection System RSPT Reed Switch Position Transmitter RTD Resistance Temperature Detectors X
+
. LIST OF ACRONYMS (Cont.)
Acronyms Meaning i
SAR Safety Analysis Report 1
SCAP Spray Chemical Addition Pump SCCS Secondary Chemistry Control System SCS Shutdown Cooling System SER Safety Evaluation Report SIAS Safety Injection Actuation Signal 1
SIS Safety Injection System SPLA Supplementary Protection Logic-Assembly S/PM Surveillance / Preventive Maintenance SPS Supplementary Protection System SS Sampling System SSAS Solid State Actuation System SSCCS Solid State Component Control Systems SSMUX Safety Status Multiplexer-1 SSPPS Solid-State Plant Protection Systems 4
TID Total Integrated Dose 1
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QUALIFICATION OF CLASS 1E ELECTRICAL EQUIPMENT
1.0 INTRODUCTION
1.1 OBJECTIVES This report discusses the methods used to meet the requirements of IEEE Std. 323-1974 (Reference 2.1) and the " Category I" requirements of NUREG-0588 (Reference 2.2).
The methods described herein apply to Class lE Combustion Engineering (C-E) supplied electrical equipment for use in nuclear power plants committed to the above requirements.
It is expected that this report may be referenced by license applicants for the scope and methods employed herein. Qualification documentation will be prepared by C-E and is described in detail in Section 6.0.
1.2 BACKGROUND
INFORMATION Applicants for operating licenses are required to demonstrate that Class lE electrical systems and equipment will perform their required Class lE functions throughout their design life under the expected no' mal and postulated accident conditions. Qualification programs must consider the effects of normal and accident environments, in-service and seismic vibration, radiation, temperature, pressure, chemical spray, humidity, submergence, dust, as well as the natural aging process for the individual equipment.
The goal of the qualification program is to provide a reasonable assurance that the specified eq ipment will operate within defined limits when exposed to the conditions associated with its required service environments.
In order to meet this goal the qualification program will address the following areas, as required.
A.
Performance or operating requirements for Class 1E equipment to demon-strate qualification; l-1
B.
The environmental conditions and exposure times for which the equipment must be qualified; C.
Simulation of environments or effects to determine qualification of individual components or modules; D.
Effects on these components of lon? or short term expo:ure to these environments; E.
Methods of observing or detecting these effects; F.
The methods for establishing a qualified life; G.
The required levels of documentation and quality assurance.
The integration of these areas is accomplished through a series of activities which include the following:
l 1.
Generation of an aging analysis plan and report which defines age susceptible components of the equipment.
This report also includes detailed procedures for age conditioning and define periodic replacement intervals as required; 2.
Generation of a qualification plan that incorporates the results of the aging analysis in defining the qualification methods and documenta-tion activities of the qualification program; 3.
Performance of the age conditioning sub-program and preparation of an age conditioning report, if required; 4.
Preparation of detailed qualification test procedures; l
5.
Performance of the qualification testing; 6.
Preparation of the final qualification test report and data summary and evaluation form.
1-2
4 This report will address each one of the above areas as applied to C-E supplied Class lE electrical equipment.
1.3 CRITERIA AND STANDARDS The qualification program is designed to meet the requirements of IEEE Std. 323-1974 (Reference 2.1) and the " Category I" requirements of NUREG-0588 (Reference 2.2).
This report may be referenced by applicants for plants @ nse Safety Analysis Reports conunit to equipment qualification meeting Reference 2.1 and Reference 2.2.
1.4
SUMMARY
A summary of the various sections of this report is given below:
Scope of Qualification Program (Section 3.0)
The general scope of supply and the various qualification programs planned are discussed. This report will cover C-E supplied Class lE electrical equipment including sensors, signal processors, protection systems, panels, miscellaneous instrumentation, nuclear service valves and auxiliary equipment, and pump motors.
Equipment Requiring Qualification (Section 4.0)
The types of components included and data on the systems, modules and compo-nents to be qualified are discussed.
Information will be included on the j
location of equipment, qualification environment and operating requirements.
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Methods of Qualification (Section 5.0) t Type tests, analysis and other methods of qualification compliant with Reference 2.2 are presented. The conservatism of the qualification parameters I
will be discussed.
1-3 t
Documentation (Section 6.0)
This section discusses the documentation required for qualification.
The qualification documentation products and their generation is discussed.
Documentation necessary to support the review on a particular applicant's docket will be available for audit.
Quality Assurance (Section 7.0)
.i C-E's quality assurance practices and documentation requirements associated with equipment qualification activities are discussed.
Administrative Procedures (Section 8.0)
Vendor participation and responsibility coupled with qualification program technical definition, management, and control are discussed.
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2.0 REFEREf1CES 2.1 IEEE Std. 323-1974, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations".
2.2 NUREG-0588 Rev.1 "Interin. Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," Published July 1981.
2-1
.s
3.0 SCOPE OF QUALIFICATION PROGRAM This section discusses the plants or applicants expected to reference this report, the general scope of supply and the various qualification programs planned. This report will cover Class 1E electrical equipment supplied by C-E.
This includes Class lE sensors and signal processors, protection systems, panels, miscellaneous instrumentation, nuclear service valves and auxiliary equipment, and pump motors required for accident mitigation, post-incident monitoring, and safe shutdown.
3.1 PLANTS REFERENCING REPORT The methodology provided herein will be used by C-E designed plants committed j
to demonstrating compliance with Reference 2.1 and Category I of Reference 2.2.
I 3.2 SCOPE OF SUPPLY AND INTERFACE REQUIREMENTS The normal C-E scope of supply for Class lE electrical equipment for plants expected to reference this report is shown in Table A-l.
In general, the C-E scope of supply for Class lE electrical equipment includes the following:
Process Sensors i
Signal Converters and Converters Control Room Indicators and Recorders Signal Isolators Plant Protection Systems and Associated Panels Pump Motors of Various Types Nuclear Service Valves and Auxiliary Equipment C-E's scope does not include support equipment such as environmental controls U
(heating, cooling, and ventilation) motor control centers, conduit, etc.
Where qualification of this equipment is required to assure continued operation of C-E supplied Class lE equipment, appropriate interface require-ments are provided to the responsible party (e.g., the Customer or Architect Engineer). These interface requirements are included in interface criteria 3-1
documents which are an integral part of overall design process.
These documents are subjected to the same levels of quality assurance and controls as other design documents.
The sy:;tems and equipment discussed herein represent the generic design of many different plants.
Plant specific equipment not referenced herein will be addressed in the applicable plant specific SAR.
3.3 QUALIFICATION PROGRAM The qualification program is established to meet the requirements of Refer-ence 2.1 and " Category I" of Reference 2.2.
In general, the qualification program has two approaches based upon the equipment location.
Equipment located in a harsh environment is not treated in the same fashion as equipment i
located in a non-harsh environment.
Regardless of equipment location, qualification will be demonstrated based on either pre-age conditioning, periodic replacement, surveillance / preventive maintenance and/or any combina-tion thereof.
The qualification methods associated with both approaches are as follows:
Harsh Environments Class lE equipment located in a harsh environment, such as in containment l
and in some auxiliary building areas, required to function during or after I
the design basis event (LOCA, MSLB, etc.) will undergo an aging analysis and an accelerated aging program.
Subsequent to age conditioning, the equipment will undergo type testing for the accident environment as specified in Sections 6.1, 6.2, and 6.3 of Reference 2.1 and Sections 2.0, 3.0 and 4.0 of Reference 2.2.
Equipment subjected to a postulated harsh environment is identified in Table A-1 via its equipment category designator (see Section 4.6.5) or in the plant specific SAR.
Such equipment includes Class 1E temperature, pressure, level, and flow transmitters, ex-core detectors, CEDM reed switch position transmitters, cables and connectors, reactor coolant pump shaft speed sensors, some process instrumentation, nuclear service valves and auxiliary equipment, and pump motors.
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Non-Harsh Environments Class 1E electrical' equipment located in a non-harsh environment, such as in the control building and some areas in the auxiliary building, will be qualified for the normal and abnormal local environment and a seismic event. An aging analysis will be performed prior to qualification type testing to determine whether or not known significant aging mechanisms exist for that equipmen't. The aging analysis will focus on the identifica-tion of known aging mechanisms that significantly increase the equipments susceptibility to its design basis event (seismic only for non-harsh environ-ments).
pending the results of the aging analysis, the equipment will either require an accelerated age conditioning program, periodic part l
replacement program, a surveillance / preventive maintenance (S/PM) program or any combination thereof to demonstrate and maintain qualification status.
4 This equipment will also undergo type testing as specified in Reference 2.1 and Reference 2.2.
Equipment subjected to a non-harsh environment is identified in Table A-1 via its equipment category designator (see Section 4.6.5) or in the plant specific SAR.
Such equipment includes Class lE plant protection system panels and modules, some process instrumentation (indicators, converters, and recorders) and miscellaneous electronic modules.
3.3.1 Aging l
The aging analysis and the age conditioning program will be conducted in accordance with Section 6.3.3 of Reference 2.1 and Section 4.0 of Reference 2.2.
As discussed in Section 3.3, the qualification program is determined by two approaches based on whether or not equipment is located in a harsh or non-harsh environment.
Regardless of equipment location an aging analysis, will be performed on all equipment. Thermal, radiation, humidity, cyclic operation, electromechanical effects will be addressed as appropriate.
The methodology utilized in the determination and evaluation of the equipment age related failure modes and mechanisms will include, as appropriate, the i
following types of information:
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3-3
A.
Arrhenius and/or activation energy data; B.
Failure rate data; C.
Failure Mode and Effects Analysis (FMEA) data; D.
Thermal stress data; E.
Electrical stress data; F.
Electromechanical and Operational cycling data; G.
Normal Operating Vibration Data; H.
Radiation component susceptibility data; I.
Major industry known synergistic data.
3.3.2 Seismic A description of the seismic qualification program for Class lE instrumenta-tion will be in accordance with IEEE Std. 344-1975 (Bibliography E.7) as defined in CENPD-182 (Bibliography E.15).
Seismic qualification of pump motors, and nuclear service valves and auxiliary equipment is per IEEE Std. 344-1975.
This report will not discuss seismic testing, methods, or results, other than to reference CENPD-182 and IEEE Std. 344-1975.
3.3.3 Environmental Equipment will be environmentally qualified, including margin, to levels at least as severe as the conditions specified in the Safety Analysis Report for normal, abnormal, and accident conditions.
A summary of typical environ-mental condition categories and qualification test profiles are provided in Appendix 8.
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3.4 ENVIRONMENTAL CONDITIONS AND EFFECTS The postulated environmental conditions, to which Class lE equipment are exposed, generally include long time periods at either moderate or low levels of temperature, pressure, humidity, and radiation, followed by, for equipment located in the containment, exposure to high levels of these same parameters for relatively short periods of time.
Operation under these high stress levels may be required in order to mitigate or monitor the effects of various accidents.
The level of exposure may also be affected by the location of the particular module or component.
See Appendix E, Bibliography E.21, E.22, E.23, and E.24 for background information.
Thus, for example a component located in the containment building may be exposed to moderate temperature, humidity, and radiation for long periods of time and then would be required to function for safety purposes under possible conditions of high temperature, pressure, humidity, radiation and chemical spray resulting from a Loss of Coolant Accident (LOCA) or Main Steam / Main Feed Line Break (MSLB, MFLB).
The purpose of the qualification program is to demonstrate that equipment will perform its Class lE function.
Plant specific environmental requirements which deviate from the generic requirements will be addressed in the applicants SAR.
3.4.1 Temperature
]
3.4.1.1 Harsh Environment The qualification of equipment to a harsh environment will be accomplished I
by performing a test defined by a qualification test profile.
Two environmental test profiles are included in Appendix "B" as Figures B-7A and B-7B and will be considered when defining the profile to be used.
Figure B-7A is a combined MSLB/LOCA profile and is designed to evelope a full spectrum of containment atmosphere conditions following a MSLB/LOCA 3-5
)
event.
Figure B-78 is a containment saturation condition profile and is designed to envelope a saturated steam condition following a DBE based on the containment pressure transient.
Qualification testing equipment and techniques dictate that tests like that defined in Figure B-7A are achievable only by raising the incoming steam tem;erature to a value significantly higher than the required test profile temperature.
1 A combined MSLB/LOCA test like that defined in Figure B-7A represents a severe test and generally results in significant overtesting.
The test profile defined in Figure B-7A will be used for qualification of equipment located in a harsh environment except where determined that overtesting will occur and, be harmful to the equipment.
In this situation the test as defined in Figure B-7B will be performed along with a thermal equivalency analysis.
This analysis will be used to verify that testing to a profile with lower peak temperatures results in equipment effects at least as severe as those of the limiti,ng DBA.
The determination of approp-riate qualification test profiles is summarized below:
1)
Where no previous qualification has been performed and the severity of the test defined in Figure B-7A will not constitute harmful overtesting, qualification to the profile of Figure B-7A will be performed, l
2)
Where no previous environmental qualification has been performed and the severity of the test defined in Figure B-7A will constitute harmful overtesting, testing to the profile of Figure B-78 along with a thermal equivalency analysis will be performed.
3)
Where previous environmental qualification has been performed to profiles less than that defined in Figure B-7A, or where previous qualification to a profile like Figure B-7A is inadequate for project specific and equipment specific conditions, the thermal equivalency analysis will be performed.
This analysis will show that the effects of the already completed test are, at least, as severe as the effects that would be experienced during any required DBA.
3-6
The analysis methodology defined in NUREG 0588 and its revisions will be used in the Thermal Equivalence Analysis to extend qualification from a lower tested profile to the higher plant specific anticipated DBA conditions.
The component peak surface temperature (s) (TCS) will be computed using NUREG-0588 Appendix B.
The component qualification temperature (TEQ) will be determined from the actual environment test conditions. Where components have been " bathed" in saturated steam or steam / air environment for extended periods (e.g., 10 minutes), the qualification temperature will be the test chamber temperature.
For components subjected to test conditions substantially removed from the steam saturation point or for short durations (e.g., less than 10 minutes).
The qualification temperature will be justified by experimental thermocouple readings on the component surface or analysis which minimizes the heat flux to the component.
If the component surface temperature is less than or equal to the component qualification temperature, this component will be considered qualified.
IF the component surface temperature is greater than the qualification temperature, then (A) we will provide additional justification that this component can operate in environments equal to or greater than that of the calculated peak surface temperature, or (B) the component will be requalified, or (C) appropriate protection to assure that the component surface temperature will not be greater than the qualification temperature.
The activity to define postulated high energy pipe breaks (HELB) and their associated environmental accident conditions and impact on specific equipment is not within the scope of this report. When a HELB is defined, several options exist for resolving the concern regarding environmental impact on specific equipment.
For example, equipment relocation, equipment redesign, additional safety analyses, or equipment qualification are all possible solutions.
Where equipment qualification is determined to be the method of resolution, that equipment will be qualified by the methods discussed in this report.
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1 3.4.1.2 Non-Harsh Environment Equipment located in general plant areas outside containment which is not subjected to a design basis accident environment will be qualified to the i
normal and abnormal range of environmental conditions postulated to occur at the equipment location.
Equipment that is served by Class lE support systems that may be secured during plant operation or shutdown will be qualified per defined environmental interface requirements, to the limiting environmental conditions that are postulated for that location.
Typical environmental test profiles, as illustrated in Figures B-8 through B-ll will be used as appropriate, for environmental qualification to the normal and abnormal environmental conditions.
3.4.2 Radiation 3.4.2.1 Harsh and Non-Harsh Environment Equipment will be qualified for the types and levels of radiation associated with normal operation plus the radiation associated with the limiting i
Design Basis Accident (DBA). These levels are defined in Appendix B.
If more than one type of radiation is significant, each type may be applied 4
separately.
4 l
Equipment which is exposed to radiation above 10 Rads will be irradiated to its anticipated Total Integrated Dose (TID) prior to type testing unless determined by analysis, supported by partial type test data, that radiation does not effect its ability to perform its required function. Where the application of the accident dose is planned during DBA testing, it need not be included during the aging process.
4 Equipment which will be exposed to radiation levels of 10 Rads or below will be analyzed to determined whether low level radiation could impact its ability to perform its required function. Where analysis supported by partial type test data, cannot demonstrate proper operation at the required radiation levels, type testing will be performed.
3-8
Equipment will be qualified to the typical radiation environments defined in Appendix B, as required.
Gamma Cobalt-60 is considered an acceptable gamma radiation source. Other sources may be found acceptable, and will be justified.
Equipment will be tested to typical gamma radiation levels defined in Appendix B.
Beta Equipment exposed to beta radiation will be identified and an analysis will be performed to determine if the operability of the equipment is affected by beta radiation ionization and heating effects. Qualification will be performed by test unless analysis demonstrates that the safety function will not be degraded by Beta exposure. Equipment will be tested and/or analyzed to the beta radiation levels defined in Appendix B.
Where testing is recommended, ganna equivalent radiation source will be used.
Neutron Equipment exposed to neutron radiation will be identified and neutron radiation levels defined. When actual neutron dose qualification testing is not perforned, an equivalent gamma radiation dose will be used for qualification testing to simulate neutron exposure. The basis for establish-ing an equivalent gamma radiation dose will be provided.
Paints / Radiation Effects An analysis will be performed addressing paint exposure to beta and gamma radiation, if required. Qualification of painted equipment will be performed by test, if analysis indicates that the safety function of the equipment could be impaired by paint failure due to radiation.
3-9
3.4.3 Vibration Vibration may be externally or self induced. Safety related piping systems (including components) are designed and observed under start-up or initial service conditions to ensure that externally or self induced. vibration of piping systems is in accordance with the ASME Boiler and Pressure Vessel Code,Section III (Bibliography E.28). Vibration effects of components (e.g., Class lE pump motors) are addressed by periodic measurement of vibration during inservice inspection tests of pumps in accordance with ASME Boiler and Pressure Vessel Code,Section XI (Bibliography E.28). For pump motors, acceptance vibration levels defined in the Hydraulic Institute Standards (Bibliography E.29) provide the maximum vibration levels acceptable to ensure continued qualified motor performance.
Where significant levels of continuous vibration are expected to exist during service, the effects of such vibrating, either externally or self induced will be analyzed via surveillance, preventive maintenance, analysis, partial type testing, or any combination of the above.
3.4.4 Pressure Class lE equipment in C-E designed nuclear power plants is not normally exposed to high pressure environments. However, after a postulated accident, such as the LOCA or MSLB, components located in the Conteinment Building will be exposed to significant external pressure from a combined steam-air mixture.
Equipment will be environmentally tested to these conditions and performance requirements demonstrated during and after the test.
See Figure B-2 for typical containment atmosphere pressure condition profile and Figure B-7A and B-7B for typical pressure test profile.
3.4.5 Humidity Equipment not subjected to steam environments during DBE testing will be environmentally tested to short term high humidity levels and performance 3-10
requirements demonstrated during and after the test.
Equipment that is subjected to steam environments will be subjected to the appropriate test profiles in Appendix B.
3.4.6 Chemical Spray Class lE equipment in C-E designed nuclear power plants is not normally j
exposed to chemical spray environments.
However, after a postulated accident, such as the LOCA or MSLB, components located in the Containment Building may be exposed to a chemical spray from a solution used to remove iodine from the containment building atmosphere.
Equipment will be environmentally tested to conditions at least as severe as these conditions and performance requirements demonstrated during and after the test. A single failure analysis of the spray system will be performed, as described in Section 5.2.3, to determine most severe spray composition.
Corrosion effects due to long term exposure will be addressed, as appropriate.
Where qualification for chemical spray environment is required, the simulated spray will be initiated at the time shown in Figure B-7A and B-78.
Typical values of chemical spray composition, concentration, and pH are defined in Appendix B, Tables B-1, B-2 and B-13.
3.4.7 Dust Dust environments will be considered when establishing service conditions and qualification requirements.
The potential effects of dust exposure will be evaluated relative to effects upon equipment safety function perfor-mance. Where dust could have a degrading effect on equipment safety function l
performance, it will be addressed in the qualification program through the development of a S/PM program and/or an upgrading of equipment interface requirements.
The following factors will be considered as appropriate when evaluating the effects of dust.
A.
Interface requirements and limits for the environmental control systems; 3-11
B.
Equipment filtering capabilities; C.
Dust density, composition, and accumulation rate; D.
Equipment utilizing high voltages or performing electromechanical functions; E.
Dust storms; F.
S/PM Program; 3.4.8 Submergence Equipment _ locations and operability requirements will be reviewed to establish whether or not specific equipment could be subject to submergence during its required operating time. Flood levels both inside and outside containment will be reviewed and potential impacts on equipment qualification appropriately addressed. Where operability during submergence is required, qualification will be demonstrated by type test and/or analysis supported by partial type test data. See Section 5.2.1 for additional discussion.
If simulation of hydrostatic pressure is required for subnergence testing, it will include the maximum containment pressure plus margin and the pressure due to its level of submergence. The duration of the test will be as specified in equipment specific qualification test procedures.
3.4.9 Power Supply Voltage and Frequency Variation Power supply voltage and frequency variation is addressed in several areas throughout the equipment design and verification process.
During the design process interface requirements dictate the acceptable range of power supply variation.
Equipment specifications incorporate these interface requirements into the design to ensure acceptable operation within the defined range of power supply voltage and frequency variation. Upon equipment fabrication and completion, design verification tests are performed to demonstrate design adequacy.
3-12
Class lE pump motors are designed and qualified to operate successfully under normal operating conditions at rated load with a variation in the voltage or frequency up to the following typical values:
A.
i 10% of rated voltage with rated frequency B.
1 5% of rated frequency with rated voltage C.
A combination of rated voltage of i10 % provided frequency variation does not exceed i 5% of rated frequency.
1 3-13
l 4.0 EQUIPMENT REQUIRING QUALIFICATION Equipment requiring qualification, is that equipment and systems that are essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, or are otherwise essential in preventing significant release of radioactive material to the environment.
This section discusses the types of equipment to be qualified and provides data on these systems, subsystems, and modules.
Qualification program information requirements (e.g., equipment type, category, equipment design specifications, and submittal requirements) per Appendix E of Reference 2.2 are discussed in Section 6.0.
Appendix A contains typical equipment specific data regarding operating requirements, equipment location, environment, category and interface requirements.
4.1 SYSTEMS AND MODULES The various types of Class lE instrumentation systems and modules requiring qualification are described below.
System design is described and a block diagram of each system is provided where necessary.
4.1.1 Process Instrumentation These systems typically consists of process detectors or transmitters, signal converters and panel mounted indicators or recorders. Types of channels include pressure, temperature, level and flow. A block diagram of a typical system is given in Figure 4-1.
Isolation from non-Class lE equipment, is provided as described in Section 4.2.
4.1.2 Nuclear Instrumentation This system consists of excore neutron detectors, preampli#iers and filters, and signal processing drawers. A block diagram is given in Figure 4-2.
Isolation from non-Class lE equipment is provided as described in Section 4.2.
4-1
_____a
4.1.3 Reactor Coolant Pump Shaft Speed Sensing System This system consists of proximity probes, pulse transmitters and signal processors. No indicators or recorders are used. A block diagram is given in Figure 4-3.
4.1.4 CEA Position Indication System This systems consists of reed switch position transmitters and signal isolating devices. The isolating devices are used to separate and isolate position signals between channels of the Core Protection Calculators (CPC) and CEA Calculators (CEAC) where required. A block diagram is given in Figure 4-4.
Isolation between Class lE equipment is discussed in Section 4.2.
4.1.5 Plant Protection System Cabinet This system includes the Reactor Protection System (RPS) and the Engineered Safety Features Actuation System (ESFAS). These systems consist of trip bistable units, trip logic matrices, trip path channels and trip circuit breakers. They receive inputs from various redundant Class lE sensing channels.
Isolation from non-Class lE equipment and redundant safety channels is discussed in Section 4.2.
The-Plant Protection System (PPS) cabinet contains the following subsystems or modules:
Bistable Control Panel PPS Power Supply Panel Matrix Test Module Actuation Reset Panel Nuclear Instrumentation Panel Initiation Relay Panel l
Auxiliary Equipment Bin Relay Card Rack Assembly 4-2
The cabinet contains Class lE and associated equipment, including internal wiring, miscellaneous switches.and indicating lights. The trip circuit breakers, which are the actuati'on devices, are discussed in Section 4.1.8.
Isolation from non-Class lE equipment is provided as discussed in Section 4.2.
4.1.6 ESFAS Auxiliary Relay Cabinet The ESFAS Auxiliary Relay Cabinet (ARC) houses the following subsystems or modules:
ESFAS Actuation Circestry ESFAS Test Modules The cabinet contains only Class lE or associated equipment, including internal wiring, miscellaneous switches and indicating lights.
Isolation from non-Class lE equipment is provided as discussed in Section 4.2.
4.1.7 DNBR/LPD Calculator Syst_em.
This systems consists of CPC I/O modules, CPC CPU and memory, CPC test panels, CEAC I/O modules, CEAC CPU and memory, signal isolators, operator's modules, and meters.
It receives inputs from Class lE sensing channels. A block diagram is given in Figure 4.5.
Isolation between redundant Class lE channels and from non-Class lE equipment is provided as described in Section 4.2.
The CPCs and CEACs are located in the Auxiliary Protective Cabinet (APC) or the Compartmented Plant Protection System (CPPS) Cabinet. The APC or the CPPS Cabinet houses the following class lE subsystems or modules:
Core Protection Calculator (CPC)
CEA Calculator (CEAC)
CEA Position Isolation Assembly (CPIA); (APC only)
I RCP Shaft Speed Sensing Signal Processor 4-3 l
Plant Monitoring System Remote Input Subsystem (RIS)
Ex-core Nuclear Instrument Safety Channel (CPPS only)
Optical Comunication Interface System (CPPS only)
Solid State Plant Protection System (CPPS only)
Digital Isolation Device Assembly (CPPS only) 4.1.8 Supplementary Protection System The Supplementary Protection Logic Assemblies (SPLAs) are the decision making elements of the Supplementary Protection System (SPS).
Each SPLA receives a signal from a transmitter monitoring pressurizer pressure in the Nuclear Steam Supply System (NSSS). The S?LA compares this signal to an internally generated fixed set point signal.
If the signal reaches the set point signal, the SPLA automatically generates an initiation signal.
The initiation signals provided by the SPLAs are used t6 actuate external devices to effect a reliable and rapid reactor shutdown.
4.1.9 Miscellaneous Equipment The following typical Class lE or associated instrumentation is located in various panels or cabinets:
DNBR/LPD Operator's Modules DNBR/LPD Remote Display Meters PPS Remote Control Modules PPS Local Status Panel Cooling Fans Isolation from non-Class lE equipment is provided as discussed in Section 4.2.
4-4
4.2 ISOLATORS Class lE and associated eq'aipment and systems are isolcted between redundant safety channels and from non-Class lE equipment.
In general, redundant safety channels are isolated by separating the entire process channels.
In some cases interfaces to non-Class lE equipment is required.
In these cases qualified isolation devices are used. A detailed discussion of the use and handling of associated circuits is contained in Bibliography E.16.
In addition to normal isolation tests these devices are qualified as Class lE for the isolation function for abnormal environmental and seismic condi-tions. Results c/ environmental qualification of these isolators will be reported as type tests.
Details on specific isolators are given below:
4.2.1 Remote Input Subsystem The Plant Monitoring System (PMS), a non-Class IE system, receives many inputs from Class lE equipment including process signals, and CPC/CEAC outputs.
Isolation for these inputs is provided by a Remote Input Subsystem (RIS). A block diagram of the RIS is given in Figure 4-6.
Output is in the form of " time-shared" output pulses on the digital output line to the non-Class IE computer systems. Feedback or adverse effects to the Class lE system from non-Class lE systems is prevented by the RIS.
4.2.2 CEA Position Isolation Assembly These devices provide a means of separating and isolating signals from the CEA position indication reed switches on each CEA and of directing these signals to the redundant CPC/CEAC channels.
Isolation is provided between channels.
4.2.3 Process Signals Isolation of Class lE equipment between channels and from non-Class lE equipment may be accomplished by using isolation devices that have no feedback effects on the input signals.
4-5
4.2.4 Digital Isolation Device Assembly The Digital Isolation Device Assembly (DIDA) is used in applications for interfacing between Class-lE and Non-Class-1E equipment. The signals i
interfacing through the DIDA are not required for the performance of a safety function. The absence of these signals would not result in the failure of any Class-lE equipment to perform its intended safety function.
4.3 NUCLEAR SERVICE VALVES AND AUXILIARY EQUIPMENT The various types of nuclear service valves and auxiliary equipment requiring qualification are described below. Equipment design is described and a block diagram of each type of equipment is provided. This equipment provides electromechanical functions and is located throughout the plant both inside and outside containment.
Equipment will be qualified for use in any location inside and/or outside containment by use of defined environmental categories and test profiles which envelope all possible conditions of exposure.
Solenoid energization equipment, motor starting equipment, cabling and conduit to the input terminals, and those actuation signals not provided by the equipment described in Section 4.1 will be addressed in the applicant's plant specific SAR.
4.3.1 Electric Valve Motor Operators for Nuclear Service Valves Electric valve motor operators are used to open and/or close valves in the SIS, SCS, CSS and CVCS in reponse to RAS, SIAS, CSAS, or CIAS actuation and may also be used in normal plant operation.
Auxiliary safety related functions of motor stop control, valve open/close position indication and continuous valve position indication are also provided. A typical block diagram is given in Figure 4-7.
4-6
4.3.2 Electric Solenoid Process System Nuclear Service Valves i
Electric solenoid process system nuclear service valves are used in the SCCS, SS, IR and CVCS and open and/or close in response to RAS, SIAS, CSAS, CIAS, EFAS, or MSIS actuation and may also be used in normal plant operation.
An auxiliary safety related function of open/close valve position indication is also provided. A typical block diagram is given in Figure 4-8.
4.3.3 Electric Solenoid Operated Pneumatic Pilot Valves for Nuclear Service Valves Electric solenoid operated pneumatic pilot valves are used to open and/or close pneumatic operated valves in the SIS and CVCS in response to RAS, SIAS, CSAS or CIAS actuation and may also be used in normal plant operation.
A typical block diagram is given in Figure 4-9.
4.3.4 Electric Limit Switches for Open/Close Position Indication for Nuclear Service Valves Electric limit switches are used to indicate the open and/or close position on nuclear service valves used in the SIS and CVCS which open and/or close in response to RAS, SIAS, CSAS or CIAS actuation and may also be used in normal plant operation. A typical block diagram is given in Figure 4-10.
4.4 PUMP MOTORS The various Class lE motors requiring qualification are described below.
The system design is described by a block diagram that is generically applicable to all pump motors (Figure 4-11). Motor starting equipment, cabling and those actuation signals not provided by the equipment described in Section 4.1.6 will be addressed in the plant specific SAR.
4-7
4.4.1 High Pressure Safety Injection Pump Motor The HPSIP motor drives the HPSIP, which is a component of ECCS, in the event of a SIAS or manual actuation. The HPSIP motor horsepower rating will vary slightly depending on plant specific requirements.
The HPSIP motor can be either air or water cooled and is nominally 1000 hp, 4160 i
volts, 60 hertz.
4.4.2 Low Pressure Safety Injection Pump Motor Tne LPSIP motor drives the LPSIP, which is a component of the ECCS, in the j
event of a SIAS or manual actuation. The LPSIP motor horsepower rating will vary slightly depending on plant specific requirements.
The LPSIP motor can be either air or water cooled and is nominally 500 hp, 4160 volts, 60 hertz.
4.4.3 Containment Spray Pump Motor The CSP motor drives the CSP, which is a compoent of the CSS, in the event of a CSAS or manual actuation. The CSP may not be provided for all plants but, when provided, the CSP motor horsepower rating will vary slightly l
depending on plant specific requirements. The CSP motor can be either air or water cooled and is nominally 800 hp, 4160 volts, 60 hertz.
4.4.4 Charging Pump Motor The CHGP motor drives the CHGP, which is a component of the CVCS, upon automatic level control actuation or manual actuation. The CHGP motor horsepower rating will vary slightly depending on plant specific requirements.
The CHGP motor is nominally 100 hp, 460 volts, 60 hertz and is air cooled.
4.4.5 Spray Chemical Addition Pump Motor The SCAP motor drives the SCAP, which is a component of the IRS, in the event of a CSAS or manual actuation. The SCAP motor horsepower rating will vary slightly depending on plant specific requirements. The SCAP motor is nominally 3 hp, 460 volts. 60 hertz and is air cooled.
4-8
)
4.5 NON-SAFETY RELATED EQUIPMENT The activity to identify non-safety related equipment that need not function in order to mitigate an accident, but that must not fail in a manner detri-mental to plant safety is not within the scope of this report. Several options exist for resolving this issue.
For example, equipment relocation, equipment redesign, additional safety analyses, or equipment qualification are all possible solutions. Where equipment qualification is determined to be the method of resolution, that equipment will be qualified using the methods discussed in this report.
4.6 EQUIPMENT QUALIFICATION REQUIREMENTS A data summary and evaluation forms has been developed for C-E supplied Class lE equipment.
This form was prepared on a generic basis, providing location, normal and accident environments, operating requirements and interface criteria, where appropriate. Qualification requirements for Class lE subsystems and modules in the C-E standard scope of supply are contained in the appropriate SAR. These requirements include equipment specific DBE's, location, normal and accident environment and operating time required under accident environments. A summary of environmental conditons for various categories of equipment is shown in Appendix a.
4.6.1 Location The location will determine the normal and accident environment of the equipment.
Equipment located in the Containment Building may be exposed to a normal, moderate temperature and radiation environment as well as a high temperature, pressure, radiation, humidity, and chemical spray accident envionn.c9t, including a possible seismic event. Most equipment located outside of Containment would only be subjected to e possible seismic event or a limited temperature / humidity excursion.
Because of its location, access to equipment in the Containment Building may be limited for S/PM or periodic calibration.
4-9
T' If it is determined that a particular piece of equipment is located in an area that exposes it to a defined environmental condition, (e.g, helb, j
flooding, or radiation due to recirculation fluids) then these conditions will be incorporated into the qualification program.
i I
4.6.2 Environment The environment to which equipment is exposed is contingent on location as discussed above, as well as on the type of accident.
For example, the LOCA would expose equipment to a different accident environment in the Containment Building than a Main Steam Line Break or a Seismic Event. The qualification requirements will impose the worst-case environment for each compor.ent, as applicable.
4.6.3 Design Basis Events Design basis events (DBE) are established for each piece of equipment based on the requirements of the safety analysis. To demonstrate that the equipment is qualified to function during and/or after a DBE, it will be qualified to a simulated test environment that exceeds, with appropriate margin, the defined environmental condition associated with that event.
4.6.4 Operating Requirements Operating requrements for specific equipment are established by the Safety Analysis for each accident. Some systems may be required to operate up to the initiation of the accident, others may be required to function during or after the accident and others may only be required to maintain structural integrity so as not to affect the operation of safety equipment.
Each of these factors has been considered in developing the qualification requirements for particular components in Appendix A.
4-10
e 4.6.5 Equipment Categorization Per the requirements of Appendix E of Reference 2.2, the equipment will be categorized into one of the following categories based on its functional requirements and location:
Category Definition 1.
All Class lE electrical equipment exposed to the harsh environments of design basis accidents, which must function to mitigate or monitor those events.
2.
All Class lE electrical equipment exposed to the harsh environments of design basis accidents which need not function for mitigation of said accidents but must not fail _ in a manner detrimental to plant safety during those events.
3.
All Class 1E electrical equipment exposed to the harsh environments of design basis accidents which need not function during those events and whose failure (in any mode) is deemed not detrimental to plant safety.
4.
All Class 1E electrical equipment not exposed to the harsh environments of design basis accidents.
Equipment categorization will be provided in the following areas:
A.
Appendix A of this report; B.
Equipment Specific Qualification Documentation; C.
Data Summary and Evaluation Form - Table 5-2.
4-11
Figure' 4-1 TYPICAL PROCESS INSTRUMENTATION CHANNEL BLOCK DI AGRAM
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l
F 5.0 METHODS OF QUALIFICATION This section discusses type tests, analysis, and other methods of qualifica-tion consistent with the requirements of Reference 2.2.
The analyses used to establish the environmental conditions for design basis events are discussed. The methodology used to perform an aging analysis is also discussed.
)
The qualification methods defined in Reference 2.1 will be used. They are I
as follows:
a.
Type Testing; b.
Operating Experience; c.
Qualification by Analysis; d.
On-going Qualification; e.
Combined Qualification, (any combination of methods a with b, c or d above).
5:1 TYPE TESTS The goal of type testing is to demonstrate that the equipment performance meets or exceeds the requirements of equipment performance specifications under the normal, abnormal and DBA conditions specified for that equipment.
Type testing is the preferred method and will be employed to the maximum extent practical. Where operating experience or analysis is used, partial type testing will be used to support assumptions made and conclusions reached.
5.1.1 Equipment Specification Class lE equipment specifications include a description of the equipment, the Class lE performance characteristics, design environmental conditions and where appropriate, the effect of changes in environmental conditions upon Class lE performance characteristics. Class lE performance character-istics will be specified with nominal, maximum, and minimum values, where 5-1
l applicable.
Design environmental conditions are specified with normal, abnormal, test, design basis event and post-design basis event ranges or conditions, where applicable.
Miscellaneous data, such as significant sequences, rate of change, and combinations of environmental conditions, operating, energy and environmental cycles, qualified life and unusual environmental conditions are specified as required.
The qualification data summary and evaluation form (Table 5-2) that is filled in for each piece of equipment undergoing qualification, will address in summary format the Class lE equipment specifications and environmental parameters.
The specific equipment documentation provides the customer special installation require-ments and the manner and frequency of maintenance requirements to maintain qualification.
5.1.2 Type Test Methods The type test demonstrates that the observed Class lE performance character-istics of the equipment meet or exceed its specified Class lE performance requirements.
The type test will consist of a planned sequence of test conditions that meet or exceed the expected or specified service conditions, including margin, and will take into account both normal and abnormal service conditions.
Prior to performing the type test, a written qualification test plan, aging analysis report, age conditioning report and qualification test procedures are prepared in accordance with Reference 2.1 and 2.2.
Equipment is mounted in a manner and position which simulates its in plant installation.
The Class 1E performance characteristics of the equipment are determined at the nominal controlled environmental and energy supply reference operating conditions.
Equipment is operated at rated load conditions over the range of its input and output parameters or other Class 1E functions.
The Class IE performance characteristics of the equipment are determined for the significant portions of the design range of each of the significant environmental parameters or each significant combination thereof.
5-2
The test is monitored using equipment that provides sufficient resolution for detecting meaningful changes in the measured variables. The test equipment is calibrated against auditable calibration standards and will have documentation to support such calibrations. The monitoring of perfor-mance characteristics and environmental parameters are of sufficient frequency as to provide an assured basis for evaluation of the Class lE performance characteristics of the equipment.
Performance characteristics will be monitored and recorded (as appropriate) before, during and after type testing.
Operability status of the equipment will be monitored and recorded (as appropriate) continuously during testing.
For long term testing (greater than one day) monitoring at discrete intervals is performed with justification provided.
5.1.3 Margin The qualification type testing includes provisions to verify that margin exists.
In defining the type test, increasing levels of testing, number of test cycles, or test duration are considered as methods of assuring that adequate margin does exist.
Margins provided in Section 6.3.1.5 of Reference 2.1 will be used as a guide.
Equipment specific qualification test procedures will define all margins and will utilize the environmental test profiles of Appendix B, as appro-priate.
Typical factors which are applied, as appropriate, to service conditions for type testing are as follows:
Temperature: i 15* F (18 C) 5-3
As stated in Section 3.4.1.1, Figures B-7A and B-78 define the environ-mental test profile for in-containment equipment.
The combined MSLB/LOCA profile of Figure B-7A has a 15 F temperature and 6 psig pressure margin added which is illustrated with a dotted line.
The saturation profile of B-78 has the saturation temperature and corresponding pressure values of 290 F and 60 psig (round off incorporated)
I and is based on the following typical pre-LOCA in-containment environmental conditions:
A.
Temperature:
120 F B.
Relative Humidity:
50%
C.
Pressure (total, steam + air):
14.7 psia A 15 F temperature and corresponding 15 psig saturation pressure margin were added to the saturation temperature and pressure values resulting in the environmental test profile illustrated by the dotted line in Figure B-78.
For equipment located outside containment a 15 F temperature margin was also added to the appropriate environmental test profile, as illustrated in Figures B-8 through B-11.
Pressure:
+10 percent of gauge, but not more than 10 psi, except for saturation profile which is 15 psig.
Radiation:
+10 percent of accident dose (Applied margin = plus 10 percent of accident dose plus uncertainty of measuring device if significant).
Where radiation dose is calculated based on Appendix D of Reference 2.2, additional margin will not be added.
5-4
Voltage:
See Section 3.4.9.
Time:
The time margin for equipment that is required by design to perform its safety function for a period of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or greater into the event is plus 10%. Where equipment need be operational to perform its safety function for a period of time less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or a short period of time (i.e. within seconds or minutes) a one hour test margin j
will be included in the test time envelope.
In selective cases an l
unusual time margin as explained below will be used.
Unusual Time Unusual time margins of less than one hour may be included in the test envelope.
These unusual time margins will be limited to those equipments which have very short operability time requirements and will typically be less than one hour.
Where this unusual time margin is utilized the following criteria will be demonstrated.
A.
The specified operating time, excluding margin, is the maximum required functional time for the entire spectrum of DBE's.
B.
Failure of the equipment after the specified operating time will not degrade the safety of the plant. Guidance provided to the i
operators will reflect the extent of qualification of equipment to help ensure that they are not mislead by false indication.
C.
The equipment will not be required after its primary function is accomplished.
The use of this " Unusual Time Margin" will be made on a selective case by case equipment susceptibility basis.
1 The methodology used for calculating the time (before the addition of margin) for equipment that is required by design to perform its safety function within a short time period into the event (i.e., within seconds or minutes) is as follows:
5-5 1
l Qualification times are obtained as a function of break area by evaluating each of the design basis events, steam line break, feedwater line break, CEA ejection, and LOCA, for a full spectrum of break areas.
To assure that these times are bounding, the initial conditions and trip setpoints which are used in these evaluations are chosen to maximize the time the equipment would be needed.
For example, minimum initial containment pressure is coupled with the upper limit on the High Containment Pressure trip setpoint and maximum initial steam generator pressure is coupled with the lower limit on the Low Steam Generator Pressure trip setpoint.
Protection System trips whose setpoints might not be reached for certain plant operating conditions, will not be credited with limiting the bounding time to trip.
Thus for each design basis event, this process yields a bounding time to i
trip as a function of break area for use in the qualification of most Protection System trips.
Margins are incorporated by adding a percentage increment to the bounding time to trip versus break area using the method identified in Section 6.3.1.5 of IEEE Standard 323-1974.
The curve of Figure 5-1 is an example of the bounding time to trip as a function of break area.
This curve shows the maximum time to occurrence of the High Containment Pressure trip for break areas below 3 ft.2 and the maximum time to occurrence of the Low Steam Generator Pressure trip for 2
break areas above 3 ft.
In addition to the above two trips the following trips are to be qualified to operate for the entire envelope defined by the curve of Figure 5-1:
Low Pressurizer Pressure trip, Low Steam Generator Level trip, and Low Steam Generator AP (low reactor coolant flow) trip.
Certain Protection System trips are not required either for the full spectrum of break areas or for time intervals of greater than several minutes.
For example, the Core Protection Calculator-Low DNBR trip, if required to provide protection against fuel failure, will encounter a trip condition within the first several minutes (maximum time for the Plant to reach a new steady state in the event of a small break).
Figures 15.1.3.2-2 through 5 from the CESSAR FSAR illustrate the early occurrence of a new steady state in an increased steam flow transient, similar to a small steam line break.
Core and primary system parameters stabilize at about 50 seconds.
A maximum stabilization time of 100 seconds has been calculated.
Therefore, protection 5-6
r-against DNB provided by the Core Protection Calculator-Low DNBR trip is required for a maximum time into the transient of 100 seconds, as indicated in Figure 5-2.
Consequently, the Core Protection Calculator-Low DNBR trip will be qualified for a time interval which bounds the maximum time to trip, but is more conservative than that obtained using IEEE 323-1974
-(e.g., 10 minute qualification time to cover 2 minute requirement).
Failure modes and effects analysis will demonstrate that subsequent failure of equipment will not prevent other equipment from performing its required function. Guidance provided to the operators will reflect the extent of qualification of equipment to help ensure ~that they are not mislead by false indications.
In this case a time margin of 400% (8 min.) has been applied to assure conservative testing.
5-7
Figure 5-1 MAXIMUM TIME TO TRIP vs STEAM LINE BREAK AREA FOR INDICATED TRIPS 10000_
I I
I I
ENVELOPE FOR:
o
~
LOW S.G.. PRESSURE g
HIGH CONT. PRESSURE g 1000 LOW PRZR. PRESSURE
=
Ed i
LOW S.G. LEVEL i
w LOW S.G.
6 P (LOW FLOW) o_-g l--
j2 100 w
E
~
p g
o M
10 E
l' l
l I
1 0
- 1. 0
- 2. 0 3.0 4.0 BREAK AREA, FT2 5-8
Figure ~ 5-2 MAXIMUM TIME TO TRIP vs STEAM LINE BREAK AREA FOR CPC LOW DNBR TRIP 1000
- \\
,a
-\\
z g
8 g
IX
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- 100 :
s m
k
~
E g
m EA 10 a
3 p
ENVELOPE FOR CPC LOW DNBR TRIP
<g I
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l.
1 0
- 1. 0
- 2. 0 3.0 4.0 2
BREAK AREA, FT 5-9
r 5.1.4 Test Sequence Type tests are run on the equipment in a specified order.
The same test samples will be exposed to the full testing sequence.
For most equipment and applications, the following constitutes the most severe sequence:
a.
Inspection is performed to assure that a test unit has not been damaged due to handling since manufacture and to determine basic dimensions.
b.
The equipment is then operated under normal conditions to provide a data base for comparison with performance under more highly stressed conditions.
Certain measurements such as rate of change with time of a parameter may be made at this time, c.
The equipment is operated to the extremes of performance character-istics given in the equipment specifications excluding design basis event and post design basis event conditions unless these data are available from other tests on identical or essentially similar equipment.
d.
Accelerated age conditioning is performed next (if required).
Key measurements are made following the aging process and compared with the data base of information gathered prior to aging. This comparison is performed to determine if the equipment is performing satisfactorily prior to subsequent testing and tc, verify the existance of potential age related failure mechanisms.
Section 5.3.1 provides additional discussion regarding the methods and procedures utilized if accelerated age conditioning is required.
e.
Normal and abnormal environmental testing is performed next.
f.
The equipment is subjected to simulated seismic vibration. Where it is determined that significant levels of external or internally induced vibration exists, qualification will be demonstrated based upon the methodology presented in Section 3.4.3.
5-10
g.
The equipment is next operated while exposed to the simulated design basis event (radiation may be excluded if incorporated above).
Those safety functions which must be performed during the simulated design basis event are monitored.
h.
The equipment is then operated while exposed to the simulated post accident conditions (following exposure to accident conditions).
Those safety functions which~ must be performed following the simulated design basis event are monitored during this simulation.
Submergence testing, if applicable, will b'e performed following seismic testing per the methodology of Section 3.4.8.
The temperature to which equipment is qualified, when exposed to the simulated accident environment will be monitored and verified by thermocouple readings located as close as practical to the surface of the components being qualified.
Theremocouple monitoring and verification of actual equipment surface temperature may be performed in support of heat soak analyses, if required, but is not the preferred method for direct verification of the simulated qualification temperature environment.
Caustic spray will be incorporated during the simulated event testing at the maximum pressure and at the limiting temperature condition that would occur when the onsite spray systems actuate.
Equipment is inspected or disassembled to the extent necessary for the determination of the status and condition of the equipment and the findings recorded.
Depending on equipment categorization (see Section 4.6.5) one'of the follow-ing type test sequences will be utilized.
Equipment in category
'l' and
'2'.
(1) Pre-Test Inspection (2) Performance Testing (Baseline Testing) 5-11
(3) Aging (4) Performance Testing (5) Seismic Testing (6) Performance Testing 1
(7) DBA Testing (8) Performance Testing (9) Post-Test Inspection Notes:
The following tests and monitoring are performed, as applicable, in addition to the sequence specified above.
- 1) Performance testing and/or monitoring of operability status durihg (5) and (7) will be performed to the extent practical.
ii) Submergence test following (7), if applicable.
Equipment in category '3' and
'4'.
(1) Pre-Test Inspection (2) Performance Testing (Baseline Testing)
(3) Aging (4) Performance Testing (5) Normal and Abnormal Environmental Testing (6) Performance Testing (7) Seismic Testing (8) Performance Testing (9) Post-Test Inspection Notes:
The following tests and monitoring are performed, as applicable, in addition to the sequence specified above.
l 5-12 l
- 1) Performance testing'and/or monitoring of operability status during (5) and (7) will be performed to the extent practicable.
The test sequence for Class lE pump motors will utilize a similar test sequence as outlined above. The aging analysis and age conditioning procedures will utilize the guidelines of IEEE Std 334-1974 (Bibliography E.6), IEEE Std.117-1974 (Bibliography E.3) and IEEE Std. 275-1966 (Bibliography E.4) as appropriate. All thermal and radiation age conditioning will be performed on motorettes or formettes made of the same insulating material as the actual full scale motor that is being qualified.
Performance tests will be made on the full scale motor utilizing the guide-lines of IEEE Std. 112A-1964 (Bibliography E.2).
5.1.5 Type Test Report Type test data used to verify the qualification of the equipment will be.
organized in an auditable form. The type test report will be consistent with the requirements of Reference 2.1 and 2.2.
Data for subsystems or modules will be compiled in reports prepared at the completion of the qualification program, and will be available for audit as discussed in Section 6.0.
5.1.6 Environmental Test profiles Typical test profile for equipment which is required to perform a Class lE function during or after a design basis accident and which is located in the Containment Building are shown in Figure B-7A and B-7B.
These profiles provides for margin requirements and include additional peak transients, as required by IEEE Std. 323-1974, Section 6.3.1.5 and Appendix A.
These profiles provide for establishing the design basis event peak transient environmental conditions, reducing to normal environmental conditions, then repeating the peak transient environmental conditions for the period of time over which the equipment is needed to perform its Class lE function.
Equipment will be exercised or monitored for its Class lE function.
5-13
r 1
l l
Typical test profiles for equipment located in non-harsh environments are provided in Appendix B, Figures B-8 through B-ll.
These profiles were developed based on normal and abnormal environmental conditions.
Equipment will be tested to the simultaneous temperature and humidity conditions for at least eight hours at the-low and high temperature levels and at high humidity at normal temperatures.
5.1.7 Acceptance Criteria Testing, or testing and analysis, will demonstrate that the equipment is qualified to perform its required safety function for all required service conditions with margin at the end of its qualified life.
Acceptance criteria is established prior to start of type testing and is included as part of the qualification test procedure document. The following is a list of typical acceptance criteria:
A.
Test environments are at least as severe as, and representative of, the required environmental profile.
B.
Operation of the equipment under normal environmental conditions to the extremes of performance and electrical characteristics is within the limits of accuracy required in the equipment specifications.
C.
Equipment has been aged, as appropriate, and has been exposed to the expected end-of-life radiation dose if applicable prior to design basis accident testing.
D.
Equipment has been subjected to seismic DBE testing.
E.
Operation of the equipment in its Class lE functions, while exposed to the design basis event environment is within the limits of accuracy required in the equipment specifications.
5-14
F.
Operation of the equipment in its Class lE functions, while exposed to the post-design basis event environment if applicable, is within the limits of accuracy required in the equipment specifications.
G.
Post-test examination of the equipment reveals no conditions which might have interfered with the ability of the equipment to perform its Class lE functions.
s H.
Instrument accuracy requirements are established from the assumptions used in the particular Safety Analysis for which the equipment performs its Class lE function. These requirements are reflected in the equip-ment specifications, and where applicable, in the safety system setpoints.
The most conservative limits on time and accuracy requirements would be used for qualification. However, it may be necessary to qualify several instruments to various levels based on the particular applications.
I.
For example, assume that a particular instrument (e.g., pressure transmitter) has Class lE operation and accuracy requirements as specified in Table 5-1.
In this case, the most conservative requirements are:
Operation for 20 minutes with +27, -81 psi accuracy. Thus the test temperature and pressure for this instrument would include the profile shown in Figure B-7A or B-7B with the test continuing for the time period required (in this case, 20 minutes plus margin).
Equipment which is required to function for post-accident monitoring would be tested to the profile shown in Figure B-7A or B-78 since long-term cooling extends for at least the time period of the profile.
Documentation that the acceptance criteria was properly defined and success-fully met will be recorded in the equipment specific qualification document-ation package and highlighted in the qualification data summary and evaluation form.
5-15
5.1.8 Test Anomalies In the event that anomalies are observed during qualification testing that violate defined acceptance criteria the following actions will be taken, as appropriate, prior to further qualification testing to ensure complete and satisfactory resolution:
A.
Verify operability status of monitoring and data acquisition equipment involved; B.
Re-evaluate acceptance criteria requirements, if appropriate.
C.
Establish the type of failure (random or common-mode);
D.
Formal notification submittal to C-E describing and evaluating the failure; E.
C-E's review and approval of recommended corrective action and for continuing qualification.
5.1.8.1 Random Failures If it is determined that the failure was random appropriate corrective action will be taken to eliminate the problem.
Replacement parts may be utilized to replace those that have failed. All replacement parts so used will have experienced the same accelerated age conditioning and qualification testing as did the original failed part prior to continuation of the qualification program.
All corrective actions taken will be documented and fully justified.
5.1.8.2 Common-Mode Failures If it is determined that the failure was coninon mode, appropriate corrective action will be taken to eliminate the problem.
5-16
Possible corrective action may include equipment / component redesign, part replacement, equipment relocation, additional analysis and/or any combination thereof.
Part replacement or redesign will be in accordance with the pre-conditioning requirements of Section 5.1.8.1.
Upon discovery of such a failure C-E will be notified prior to taking corrective action.
All corrective actions taken will be documented and fully justified.
i 5.2 ANALYSES As stated in Section 5.1, type testing is the the preferred method of qualification and will be employed to the extent practical.
If analysis is chosen as the primary method for qualification, partial type test data will be provided to support the analytical assumptions and conclusions reached.
The analytical methods used for calculating and establishing pressure and temperature envelopes and radiation levels to which equipment is to be qualified will be compliant with the methods defined in Reference 2.2.
5.2.1 Analyses Based on Partial Type Test Data and Equipment Specific Qualification Requirements If analysis is chosen as the primary method for qualification, partial type test data will be provided to adequately demonstrate functional operability.
An example demonstrating this approach is as follows:
If analysis is being used to demonstrate submergence capabilities for a particular piece of equipment, type test data on a similar unit may be employed as evidence used to demonstrate qualification for the equipment in question.
A structural and functional similarity evaluation between the
" equipment being qualified" and the "similar unit" will be performed to adequately demonstrate the applicability of the partial type test data.
5-17
I Equipment specific analyses may be utilized to justify elimination of submergence qualification if it can be shown that:
A.
Equipment safety function is-completed prior to submergence; B.
Adequate operability time margin is incorporated; C.
Subsequent failure will not degrade other equipment.
Where type testing is the preferred method of qualification, analysis may be used to support and justify the qualification test sequence and/or test makeup. An example demonstrating this approach is as follows:
4 Low level radiation qualification testing (to levels below 10 Rads) may be deleted from the qualification type test sequence if it can be demonstrated via a radiation susceptibility analysis, that low level radiation does not impact the equipment's ability to perform its required safety function.
In general, qualification analyses will consist of a mathematical or logical proof that the Class lE performance of the equipment to be qualified meets or exceeds its specified requirements when subjected to its specified normal and design basis event environments. This proof will be based on-established principles, operating experience data, partial type test data, or combinations of these. The analysis will be of a form that can be readily understood and verified by people qualified in the pertinent disci-pline of engineering or science.
Data for analysis will include:
The equipment performance specifications.
The interface or boundary conditions of the equipment.
The specific features, postulated failure modes, or the failure effects to be analyzed.
5-18
r The assumptions, empirically derived values, and mathematical models used together with appropriate justification for their use.
Description of analytical methods or computer programs used.
A summary of analytically established performance characteristics and their acceptability.
Analysis will normally only be used to justify qualification by similarity and will be supported by partial type test data.
5.2.2 Environmental Conditions Calculations To ensure compliance with the requirements of Appendix A, B, and D of Reference 2.2 a review will be performed that evaluates the actual methods and codes used to calculate the environmental parameters for design basis events.
Environmental condition verification is generally a joint activity n
between the customer, A/E and C-E.
~
Per the requirements of Section 1.4 (11) of Reference 2.2, components of the ECCS located outside containment will be qualified to withstand the radiation equivalent to that penetrating the containment plus the exposure l
from the contained fluid and the circulating fluids passing through individual ECCS components.
Equipment not associated with the ECCS but located in the same area will be addressed on a plant specific basis to meet the radiation qualification requirements.
5.2.3 FMEA a single failure analysis on the chemical spray system per Section 1.3 of Reference 2.2 will be performed to determine the resulting most severe chemical composition of the caustic spray. The results of this analysis will be incorporated into the qualification program. Where qualification has been completed utilizing chemical spray composition parameters less severe than as those required by Reference 2.2, an analysis may be performed, in lieu of retesting, for the purpose of demonstrating that t.he new, more 5-19 s
l
r e
severe chemical compositica, has no adverse'irapact on the equipments ability to perform iti ' safety function. Justification for analysis in lieu of retesting will be provided.
Some components of Class lE equipment do not perform a safety related function but due to a particular hardware configuration raust be so classified as Class -lE.
For this type of component, a FMEA will be performed that demonstrates by analysis that failure of that component, for a defined set l
l of worst case failure modes, does not have a degrading impact on all other interfacing Class lE components. A specific example, that outlines guidelines for performing such an analysis is as follows:
To summarize, the RIS (see Section 4.2.1) is classified as a Class lE system from an isolation standpoint only and not from a data acquisition standpoint.
The RIS provides ncn-safety related signal multiplexing and control functions on Class lE signal inputs as well as providing Class lE l
isolation. Because of this hardware configuration the multiplexing and control electronics are considered as Class lE components.
Therefore all components of the RIS, except for some test circuitry, are considered Class lE.
Reference 2.2 requires that Class lE components which are not required to perform a safety related function, be analyzed to determine that failure in L
any modesis deemed not detrimental to plant safety or accident mitigation.
Therefore, a FMEA will be performed that defines the set of postulated failure modes and evaluates their impact at the Class lE signal input terminals and Class lE power input terminals of the RIS.
l An evaluation will also be performed defining whether or not test circuitry l
should be classified as lE components. Test circuitry will be classified as Class lE if it could fail in a manner that results in perturbations exceeding defined-acceptance criteria.
t l
5-20 l
i
J 5.3 AGING As stated in Section 3.3.1, the aging portion of the qualification program is defined based upon whether or not equipment is located in a harsh or non-harsh environment. Equipment located in a harsh environment will undergo an aging analysis and an accelerated age conditioning program.
Equipment located in a non-harsh environment will undergo an aging analysis that focuses on the identification of known aging mechanisms that significantly l
increase the equipments susceptibility to its design basis event (seismic only for non-harsh environments).
If no known significant aging mechanisms are found, a surveillance / preventive maintenance (S/PM) program will be l
developed to monitor for degradation trends that suggest increasing seismic susceptibility.
If an aging mechanism is found that is known to significantly increase the equipments seismic susceptibility with time, then that mechanism will be analyzed to determine whether an accelerated aging program or a periodic part replacement program is appropriate.
The following sections discuss in detail the methods and documentation requirements associated with the development of an aging analysis and the resulting age conditioning program, periodic replacement program and/or the S/PM program, as appropriate, for the purpose of demonstrating qualification of the respective equipment / component.
i 5.3.1 Aging Analysis and Conditioning For equipment located in a harsh environment the following discussion defines the methodology for the development of an aging analysis and an accelerated age conditioning program.
This section may also be applicable for equipment and/or components located in non-harsh environments where it has been determined that known significant aging mechanisms exist and where accelerated age conditioning is appropriate.
The following is a listing of the major efforts that are required in the performance of an aging analysis.
5-21
i A.
Preparation of a complete component, module, subassembly, or assembly (as required) listing for the equipment; 4
B.
Identification of those components performing a safety related function.
i C.
Analysis of those components identified in (B) above for age related failure modes and mechanisms; D.
Development of an accelerated age conditioning procedure for those components identified in (B) above, that when implemented, will result in the equipment being aged to a projected end of life condition.
l Thermal, radiation, electromechanical, cyclic operation and synergistic aging effects will be considered.
Bill of Materials A bill of materials will be generated consisting of all components, modules, I
subassemblies, assemblies (as required) of the equipment.
Component / Failure Matrix t
For each component identified as performing a safety related function, corresponding information, as identified in Section 3.3.1 will be defined in an appropriate summary component / failure matrix fonnat.
An evaluation of this information will be performed to define dominant age i
related failure modes and mechanisms. An accelerated age conditioning i
procedure or a periodic part replacement program will be prepared based on i
this evaluation.
Qualified Life Estimating A goal of the qualification program is to demonstrate that the equipment has-a 40-year qualified life.
If a 40-year qualified life is not obtainable due to material or schedular constraints, then the age analysis will establish i
5-22
o various age conditioning procedures that define the efforts and parameters necessary to age the equipment. The selection of the lesser qualified life times is partially a function of the analysis and the physical properties of the equipment. A review will next be made to select one procedure to be implemented.
If qualification is to be based on periodic replacement of a life limiting component (s), that component (s) will specifically be identified and a periodic replacement program defined as part of the aging analysis, and included in the appropriate interface criteria.
Thermal Aging Arrhenius methodology will be used to address accelerated thermal aging, where appropriate; however if other methods are used, justification will be provided.
Electromechanical Cyclic Aging Electromechanical cyclic aging will be applied prior to qualification testing for the expected number of cycles plus margin under rated load.
The basis for pump and valve operation parameters in given in Appendix F.
Requirements The " cycle" and number of cycles plus margin will be defined and justified.
The cycle rate will be defined and will not result in excessive component heating beyond the manufacturers suggested limits.
Cycling will be performed while under electrical load if so required by the aging analysis. Both current and voltage loading parameters will be specified.
f The method for cycling components (e.g., electrical or mechanical actuation) will be defined.
5-23 1
>,.. -- - -,, ~ -
v,~
n-
F An explicit definition of the term " cycle", as related to electromechanical cyclic operation, will be provided.
Components undergoing cycling will be mounted in a manner that simulates or is conservative with respect to actual in service mounting.
Electromechanical components being tested will not be cleaned, calibrated, or adjusted during or after the cycling unless this action is part of the component's normal maintenance procedure and schedule. Normal maintenance procedures'and schedules will be identified and included as part of the aging analysis and included in the respective interface criteria.
(
Electromechanical cyclic aging will not be performed during thermal acceler-ated aging. Cycling, when required will be perfonned at normal operating temperatures.
Acceptance criteria will be defined to establish the bases for acceptable operation for the specified number of cycles and loading.
Test measurement procedures will be defined. Test measurements will be taken and documented before, during and after cyclic aging.
Power On and Off Cycling The number of power on and off cycles anticipated to occur plus margin will l
be defined and applied, where significant.
Power on and off cycling will be considered significant when the number of cycles is large or where there are significant stresses associated with power on and off cycling. The number of power on and off cycles to be used during age conditioning will l
be justified.
Radiation Aging l
l Radiation information and profiles utilized as input data to the radiation l
aging analysis will be in accordance with the typical radiation types, l
levels, and rates defined in Aopendix B and in accordance with equipment l
specific requirements, i
5-24 1
r-All component radiation susceptibility analyses will be supported by test data.
Electrical Energization The effects of electrical energization during the accelerated age condition-ing process will be addressed as part of the aging analysis.
Electrical energization will only be applied if this analysis indicates that inclusion of this effect, during the accelerated aging process, will have a significant effect on material degradation.
Synergistic Effects Major industry recognized age related synergism data will be addressed in the aging analysis and sequence.
Aging Sequence The determination and justification of the accelerated age conditioning sequence will be defined in the aging analysis.
Aging Rats The basis for all thermal, radiation, electromechanical and operational accelerated aging rates will be defined and justified in the aging analysis.
Equipment Storage Requirements Equipment qualification related storage requirements will be identified within the qualification documentation.
These requirements will be based on known significant storage related aging mechanisms.
5-25
r Documentation The results of the aging analysis will be documented and summarized in an aging analysis report. This report will contain all appropriate information used as listed in Section 3.3.1.
Accelerated Age Conditioning The procedures defined in the aging analysis report will be used to perform the actual accelerated age conditioning on the equipment.
Documentation.
The results of the accelerated age conditioning will be presented in an age conditioning report.
The accelerated age conditioning report will identify and analyze all equipir,cr.t failures occurring during the accelerated age conditioning process to determing whether the failure was random or comon mode.
5.3.2 Periodic Replacement As discussed in Section 5.3, equipment located in non-harsh environments will either undergo an accelerated age conditioning program, periodic part replacement program, S/PM program or any combination thereof.
For such equipment, the conclusions of the aging analysis will state the recommended approach.
The aging analysis associated with non-harsh environment equipment will be based on the same type of input data and methodology utilized for harsh environment equipment.
It is the correlation of this data with known significant aging mechanisms and with in-plant equipment accessib1 ity that may result in recommendations stressing periodic part replacement. Where periodic replacement is recommended for specific components, these components will be clearly identified in the age analysis and a replacement program defined and justified.
5-26
r 5.3.3 Surveillance / Preventative Maintenance For non-harsh environment equipment, if it is determined that no known aging mechanisms exist that significantly increase the equipment's suscept-ibility to its design basis event (seismic only for non-harsh equipment),
then a S/PM program will be developed.
The purpose of the S/PM program, which includes scheduled periodic surveil-lance testing under normal service conditions, is to monitor for degradation trends that suggest increasing susceptibility to a possible common mode failure due to a seismic event. The basis for the S/PM program is that for equipment located in environments which are unchanged during design basis accidents, having adequate capability for periodic testing and maintenance, and where no known significant age related failure mechanisms exist, then advanced age conditioning prior to qualification type testing may not be required if justified.
For equipment located in harsh environments, a S/PM program may be established, as appropriate to provide actual in-service trending data to support the qualified life established during qualification type testing.
This program will include guidelines and schedules for calibration and preventative maintenance. The requirements for the calibration and prevent-ative maintenance will be based upon the plant's normal inservice inspection tests, and maintenance program.
The preventative maintenance will include, as appropriate:
Virdal inspection Mechanical inspection Electrical testing i
Electronics testing Periodic tests Failure trending Incipient failure detection 5-27
It is anticipated that most of these tests are already included in Technical Specifications requirements.
Data maintenance, storage, in the central file and evaluation activities such as the surveillance preventative maintenance program is the responsibility of the utility.
5.4 CONSERVATISM 0F QUALIFICATION PARAMETERS The levels of environmental qualification required are specified in Appendix 8.
These requirements are established based on assumptions used in the appropriate Safety Analysis Report. Margins utilized per Section 6.3.1.5 of Reference 2.1, Section 3 of Reference 2.2, and as discussed in Section 5.1.3 will be documented in the appropriate qualification document and in the qualification data summary and evaluation form, Table 5-2.
Comparison of the qualification requirements to the environmental test parameters will demonstrate conservatism of the parameters. Margin identification and verification will be performed.
5-28
TABLE 5-1
- Typical Operation and Accuracy Requirements
- Accident Time Accuracy Small LOCA 20m.
+27, -81 psi Large LOCA 2m.
+27 -114 psi Steam Line Break 70s.
+27, -114 psi CEA Ejection 20m.
+27, -81 psi
- See Section 5.1.7 for table discussion and utilization.
\\
5-29
4 E
DATE QUALIFICATIO'i DATA SLRt1ARY AND EVALUATION FOR?1 CHECKED BY DATE P /E*:"P:TAL CL'*LIFICATIO*! REQUIREME*tTS TABLE 5-2
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- D!t:G I
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[A.00MENTAfJUN kEFERthCE CATEGORY
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QUALIFICATIG!:
SPECIFICATIO:4 QUALIFICATION METHOD ITD's
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6.0 DOCUMENTATION This section discusses the documentation for qualification.
The qualifica-tion documentation will verify that the equipment is qualified for its application and meets its specified performance requirements.
Equipment specific documentation products and data summary and evaluation forms are i
discussed. Qualification documentation and supporting test data will be l
t available for audit.
i 6.1 EQUIPMENT SPECIFIC QUALIFICATION DOCUMENTATION I
In order to demonstrate that the equipment qualification program has adequately addressed all pertinent qualification requirements the following equipment specific documentation products will be developed, as appropriate. The documentation will be organized in an auditable form and in accordance with the guidelines set forth in Section 6.3.1.1 and 8.0 of Reference 2.1 and with Section 5.0 and Appendix E of Reference 2.2.
f 6.1.1 Aging Analysis Report The aging analysis report, as discussed in Section 5.3 will contain the following types of information:
A.
Overview and Objective; B.
Equipment Description; C.
Bill of Materials; D.
Environmental Service Conditions; E.
Analytical Evaluations and Bases; I
F.
Age Conditioning Procedures (if required);
1' G.
Component Replacement Intervals (if required);
H.
Low Level Radiation Susceptibility Analysis and Bases (if required);
I.
Approval Signature and Date.
i 6-1 k
.-w-
- - - = -
m----
6.1.2 Qualification Plan The qualification plan outlines the necessary testing and documentation activities required in order to demonstrate qualification. The qualification plan will incorporate the results obtained in the aging analysis and any previous qualification testing into the overall qualification plan. The following information will be included in the plan.
A.
Scope of Responsibility; B.
Overview and Objective; C.
Equipment Description; D.
Test Sequence and Makeup (0verview);
E.
Seismic and Environmental Test Parameters; F.
Acceptance Criteria (0verview);
G.
Documentation Submittal Requirements; H.
Approval Signature and Date.
6.1.3 Age Conditioning Report The results of the accelerated age conditioning process will be presented in an age conditioning repcrt either as a separate document or as part of the final qualification test report. The purpose of this report will be to identify and analyze all equipment failures occurring during the accelerated age conditioning process to determine whether the failure (s) were random or common mode. Approval signature, and date will be obtained.
6.1.4 Qualification Test Procedure Detailed qualification test procedures and associated acceptance criteria will be defined prior to actual qualification testing. The following types of procedural information will be addressed, as appropriate:
A.
Overview and Objective; B.
Equipment Description; 6-2
c C.
Detailed Test Sequence; D.
Monitoring and Operability Check Procedures; E.
Baseline Performance Test Procedures; F.
Environmental and Seismic Test Profile Definition and Procedures; G.
Margin Verification; H.
Detailed Test Set Up Schematics and/or Description; I.
Required Test Instrumentation and Equipment; J.
Detailed Acceptance Criteria; K.
Equipment Mounting and Cable Connection Schematics and/or Description; L.
Approval Signature and Date.
6.1.5 Qualification Test Report Upon completion of qualification testing an equipment specific test report will be prepared sumarizing the test results, conclusions, and recomenda-tions. The following types of information will be addressed and included, as appropriate:
A.
Overview and objective; B.
Equipment description; C.
Description and justification for all test procedure deviations; D.
Description and evaluation for all observed abnormalities exceeding defined acceptance criteria; E.
Raw test data; F.
Calibration schedules and standards for all test instrumentation and equipment; G.
Summary, conclusions and recomendations; H.
Reference and/or pointer to all supporting qualification documentation; I.
Approval signature and date.
6.2 QUALIFICATION DATA
SUMMARY
AND EVALUATION Upon completion of the documentation products defined in Section 6.1, a qualification data sumary and evaluation package will be prepared.
This package will contain sumary qualification data per the formatting, sumary, and submittal requirements of Appendix E of Reference 2.2.
Table 5-2 6-3
v illustrates the type of form on which the summary information will be presented. Additional information associated with each " type" of equipment per Appendix E of Reference 2.2, will be supplied as appropriate to supple-ment the data to be provided in Table 5-2.
In addition to the information identified in Appendix E of Reference 2.2, the following information will be provided, as required:
A.
Discussion of how equipment qualification review was performed including consideration of quality assurance; B.
How the accident environmental profiles were developed; 1
C.
How Class lE equipment required for accident mitigation and safe shutdown of the plant was identified.
6.3 SUPPORTING ANALYTICAL AND TEST DATA All supporting raw test data and analyses generated during equipment qualifi-cation for the appropriate equipment specific qualification document will be attached or the location provided.
All other publications (e.g., reports, books, standards etc.) used to support the qualification program will be appropriately referenced to insure data traceability.
l l
l I
6-4
7.0 QUALITY ASSURANCE Equipment qualified per this report will be in accordance with the following:
7.1 All vendor and/or test labs directly utilized by C-E for performing Class 1E qualification services will be formally reviewed for their quality assurance practices.
Results of this review will be maintained.
7.2 For qualification tests, C-E group quality control surveillance practices will be applied.
7.3 C-E standard hardware procurement practices will be applied when procuring test samples.
7.4 Test procedures and analyses will be prepared to ensure repeatabi-lity of the qualification test program.
7.5 Qualification documentation will be reviewed in accordance with standard C-E review practices and quality assurance requirements.
7-1
8.0 ADMINISTRATIVE PROCEDURES 8.1 EQUIPMENT SPECIFICATION The performance requirements are set forth in the equipment specification which is generally written by C-E.
The requirements include normal, maximum and minimum values of performance parameters, and environmental conditions for normal and abnormal operation. The applicable standards for qualification are referenced by the specification. The specification is included in the engineering package which is sent to prospective vendors for bidding.
8.2 VENDOR DESIGN AND QUALIFICATION PROGRAM After the contract has been awarded, the vendor submits his design and qualification program to C-E for approval. The design is reviewed to ensure the equipment is capable of meeting performance and environmental requirements. The qualification program is reviewed for compliance with the requirements of the equipment specification and the referenced standard.
In most cases, the qualification program is written by the qualification facility which has been retained by the vendor.
In some cases C-E may
~
choose to perform its own testing of vendor's hardware.
8.3 QUALIFICATION TASK Although the task of qualification is normally performed by C-E's vendor, C-E follows the progress of the qualification effort and, in conjunction with the vendor interfaces with the qualification facility to insure that the equipment will be exposed to the proper qualification environment. The vendor is responsible for insuring that the electrical and operational performance of the equipment meets the acceptance criteria.
For the more involved tests, C-E may have witnesses present during testing.
8.4 QUALIFICATION DOCUMENTATION AND SUBMITTALS Throughout the qualificaMan program various defined documentation products (see Section 6.0) are generated. C-E will review and approve all document-ation products to insure proper program definition and control.
8-1 ll
(
1 The aging analysis report is prepared first defining all age conditioning results and. procedures and part replacement recommendations, as appropriate.
Next, the qualification plan is submitted outlining the overall program and verifies to C-E vendor / test lab understanding of services to be performed.
Accelerated age conditioning and its corresponding report is prepared, if j
required..In parallel with age conditioning, detailed qualification test procedures and acceptance criteria are developed.
After completion of age conditioning and test procedure development, actual qualification type testing is performed.
Upon completion of qualification testing, a test report will be prepared i
and submitted to C-E for approval. When the report is approved, it is accepted by C-E as a qualification report which contains sufficient informa-tion to allow QA traceability and repeatability. Qualification documentation will be available for audit.
Upon C-E approval of all required qualification documentation and supporting test data, a data summary and evaluation package, as discussed in Section 6.2 will be prepared as required and submitted to the customer for his approval. Customer participation in the review and approval cycle for all preceeding documentation is per customer specific contract requirements.
i l
1 8-2 i
ICE-98/(411CE-A)/ca-1 APPENDIX A TYPICAL CLASS lE ELECTRICAL EQUIPMENT AND DATA LISTING mm
ICE-98/(411CE-A)/ca-2 A.l PURPOSE The purpose of this appendix is to list types of Class 1E equipment, post accident operating requirements, location, design basis requirements, interface requirements and equipment category requirements. A detailed list of modules and panels, with post-accident operating times, is given in the plant specific SAR.'
t A-1
TABLE A-1
',s CLASS !E ELECTRICAL [QUIPHENT AND DATA LISTING (12) (7) (1) (15)
(2) (15)
-(3) (15)
(14) (15)
MODULE OR OPERATlfG REQUIREMENTS ENVIR.COND.
ENVIR. EQUIP.'
NOTES SYSTEM COMPONENT LOCA MSLB SEIS SSD_
LOCATION CATEGORY CATEGORY INTERFACE REF. 255 PAR S
Process Process Dectors Varies by Location and Varies by Varies by Varles by
. 4.1.1 g
Instrumentation Signal Converter Design Design Design Design Contained in Panel Mounted Recorder Appl { cation Application Application Varied Systems Panel Mounted Indicator Isolation Device I8)
I4)
Nuclear Instrmen-Fission Chanber x
x x
CB A2 1
(11) 4.1.2 tation System Detectors & Cable Pre-Amplifier & Filter x(8)
CB(5)
A2 1
(11) x x
4*1*2 Signal Processor for Log I0I Power & Linear Power x
x x
CR H
4 (9) (10) (11) 4.1.2 Safety Channels Reactor Coolant Proximity Probe for CB(6)
A2 1
(11) 4.1.3 Pump Speed Shaft Speed x
x Sensing System Extension Cable x
x CD A2 1
(11) 4.1.3 Pulse Transmitter x
x
- CB A2 1
(11) 4.1.3 Signal Processor x
x CR H
4 (9)(10)(11) 4.1.3 I4I A2 1
(11) 4.1.4 CEA Position Reed Switch Assy.& Cable x
x
.CB Indicating Refueling Disconnect Panel x
x CB(4)
A2 1
(11) 4.1.4 x
x CR H
4 (9) (10) (11)
System Isolato,r Plant Protection Reactor Protection System x
x x
x CR-AB H
4 (9)(10) (11) 4.1.5 System Cabinet Engineered Safety Features x
x x
x.
CR-AB H
4 (9) (10) I11) 4.1.5 Actuation System ESFAS Aux. Relay ESFAS Actuation Circuitry x
x CR H
4 4.1.6 Cabinet b
e O
1 y
TABLE A-1 CLASS IE ELECTRICAL EQUIPMENT AND DATA LISTING (12)(7)(1)(15)
(2) (15)
(3) (15)
(14) (15)
MODULE OR OPERATING REQUIREMENTS ENVIR.COND.
ENVIR. EQUIP, NOTES l
SYSTEM COMPONENT LOCA MSLB SEIS SED LOCATION CATEGORY CATEGORY INTERFACE RET. 255 PAR DNDR/LPD CPC I/O Hodules x
CR H
4 4.1.7 Calculator System CPC CPU and Memory x
CR H
4 4.1.7 CEAC CPU and Memory x
CR H
4 4.1.7 Signal Isolators x
CR H
4 Supplementry CB(5)
B 1
(9)(10)(11) 4.1.8 Protection System SPS Pressure XMTR.
x SPS Indicator x
CR H
4 4.1.8 Supplementary Protection x
CR H
4 (9)(10)(11) 4.1.8 System Logic Assy.(SPLA)
Remote Input Sub-RIS Isolation x
CR H
4 4.2.1 System Various Systens Digital Isolation Device x
x x
x CR H
4 (9)(10)(11) 4.2.4 Assy.
Nuclear Service Electric Valve Motor x
x x
x CB,0C V-1, V-2 1
(10) 4.3.1 Valves in Various Operators Systems as SIS.
Electric Solenoid Process x
x x
x CB,0C V-1, V-2 1
(10) 4.3.2 SCS, CSS, & CVCS System Valves Electric Solenoid Operator x
x x
x CB,0C V-1, V-2 1
(10) 4.3.3 Pneumatic Pilot Valves Electric Limit Switch for x
x x
x CB,0C V-1, V-2 1
(10) 4.3.4 Open/Close Position Indi-cator 4
I I..
g v
a
TABLE A-1 CLASS IE ELECTRICAL EQUIPMENT AND DATA LISTING (12) (7) (1) (15)
(2) (15)
(3) (15)
(14) (15)
MODULE OR OPERATING REQUIREMENTS ENVIR.COND.
ENVIR. EQUIP NOTES SYSTEM COMPONENT LOCA MSLB SEIS 550 LOCATION CATEGORY CATEGORY INTERFACE REF. 255 PAR Nuclear Service Pump High Pressure Safety x
x x
AB D
1 (10) (13) 4.4.1 Motors in Various Injection Pump Systess CVSC IRS.
Low Pressure Safety x
x x
x AB D
1 (10) 4.4.2 CSS & ECCS Injection Pump Containment Spray x
x x
AB D
1 (10) 4.4.3 Pump Motor Charging Pump Motor x
x x
AB D
1 (10)(13) 4.4.4 Chemical Spray Addi-x x
A8 D
1 (10) 4.4.5 tion Pump Motor 0
e b
e==.=-.
g g,
.e i
9 O
. Y.
8..
g
+
N.
j NOTES (1) LOCA - Loss of Coolant Accident MSLB - Main Steam Line Break SEIS - Seismic Event SSD - Safe Shutdown (2) CR
- Control Room or Control Building AB
- Auxiliary Building
- Containment Building (Auxiliary, Annulus, etc.)
CB
- Outside Containment OC 0S
- Outside Plant Buildings (3) See Appendix B (4) Inside primary shield l
(5) Outside secondary shield (6) Inside secondary shield p
(7) Specific operating requirements determined by safety analysis (8) CEA Ejection (9) Class lE ventilation, C-E supplies heat loads and temperature requirements (10) Class lE power supply, C-E supplies power requirements (11) C-E Supplies mounting and location requirements and interfacing environmental requirements as appropriate.
(12) Length of time required to perform safety related functions is determined by safety analysis-(13) Not supplied on all plants (14) See Section 4.6.5 for Category Definition (15) Component description is generic. Specific equipment models may not be applicable to al's the Operating Requirements, Location, Environmental, and Equipaent Categories shown.
9 APPENDIX B TYPICAL ENVIRONMENTAL CONDITIONS AND TEST PROFILES
B.1 PURPOSE The purpose of this appendix is to define typical environmental conditions and associated environmental test profiles.
B.2
SUMMARY
Figures B-1 through B-6 provide typical post accident environmental conditions. These figures are not " test" profiles therefore do not include IEEE margin.
Tables B-1 through B-14 developed for the purpose of defining a limisted set of clearly established environmental conditions that could be associated with specific equipment and/or locations.
These tables do not define actual test cemditions or parameters and therefore do not include IEEE margin.
Appenddix A utilizes and illustrates this approach by correlating generic pieces of equipment with its corresponding environmental category designator.
Tables B-5 through B-8 reference A note for time limit or 8 hrs.
This eight hour period was selected on the basis of engineered judgement as a reasanably conservative period for plant operators to:
- 1) recognize that actual conditions in the non-harsh environ-ments have exceeded their normal values and to, 2) restore those environments to within normal limits.
Figures B-7A and 7B are the in-containment tast profile that corresponds to the post accident environmental conditions defined in Figures B-l through 8-6 and Tables B-1, B-2 and B-13.
Figures B-7A and 78 incorporate and illustrate required IEEE margin.
l l
Figures B-8 through B-ll are test profiles for equipment located outside containment. These test profiles also incorporate required IEEE margin.
E.1 l
l Note:
All information in Appendix B illustrates " typical" parameters and conditions.
The test profiles included herein represent " typical" examples of qualification test profiles and are not intended to represent the complete set of all test profiles utilized.
B.3 ENVIRONMENTAL CONDITIONS A.
Tables B-1 and B-2 list typical parameters for design basis accident conditions inside containment (Environment Categories "A-1" and "A-2").
B.
Table B-3 lists typical parameters for normal environmental conditions inside containment (Environment Category "B").
C.
Tables B-4, B-11 and B-12 list typical parameters for normal environment conditions outside containment (Environment Categories "C", "J" and "K").
D.
Tables B-5 through B-10 list typical parameters for abnormal environment conditions outside containment (Environment Categories "D",
"E",
"F", "G", "H" and "I").
E.
Table F-13 lists typical " Worst Case" parameters for valves inside containment (Environment Category V-1).
F.
Table B-14 lists typical " Worst Case" parameters for valves outside containment (Environment Category V-2).
G.
Figures B-1 through B-6 provide profiles for typical post accident environment conditions.
H.
Figures B-7A and 7B will be used as simulated environmental profiles for equipment located inside containment, as appro-priate (Environment Categories "A-1", "A-2" and "V-1").
B-2 U
1.
Figures B-B and B-9 will be used to simulate environment conditions for equipment located outside containment, as appropriate (Environment Category "C").
J.
Figures B-10 and B-11 will be used to simulate environment conditions for equipment located outside containment, as appropriate (Environment Categories "H" and "J").
l l
B-3
TABLE B-1 CATEGORY "A-1" ENVIR0t!f1EllTAL CONDITIONS (LOCA:
IN-CONTAINMEllT)
ENVIRONMENTAL PARAMETERS RANGE AND DURATION TEMPERATURE, F
FIGURE B-1 PRESSURE, PSIG FIGURE B-2 SUPERHEt~iD STEAM /
HUMIDITY AIR MIXTURE RADIATI0fl, RADS FIGURES B-5 AND B-6 CHEF 11CALS NOTE '1' NOTE 1 - 4400 PPM BORON AS H 30,
50-100 PPM HYDRAZINE AS N H24 3
3 H
AND P 4 TO 10.
l l
l B-4
1
)
TABLE B-2 CATEGORY "A-2" ENVIRONMENTAL CONDITIONS (MSLB:
IN-CONTAINMENT)
I l
ENVIRONMENTAL RANGE DURATION PARAMETERS FIGURE B-4 0-12MIti.
~'
TEMPERATURE,
?
FIGURE B-1 (AFTER 12 MIN.')
i SAME AS LOCA PROFILE PRESSURE, PSIG FIGURE B-2 SH STEAM / AIR MIXTURE 0-12 MIN.
HUMIDITY
~
SAT. STEAM / AIR MIXTURE (AFTER-12 MIN.)
4 RADIATION, RADS 4.'5 X 10 y (TID)
CHEMICALS NOTE '1' I
f NOTE 1 - 4400 PPM.. BORON AS H B0, 50-100 PPM HYDRAZINE AS N Hg 3
3 2
(ANDFj4TO10.
I 1
l B-5
=
TABLE B-3 CATEGORY "B" ENVIR0t! MENTAL CONDITIONS (NORMAL:
IN-C0llTAINMENT)
ENVIRONMENTAL PARAMETERS RANGE DURATION i
TEMPERATURE',
F 55 TO 122 CONTINUGUS PRESSURE, PSIG 0-5 CONTINUOUS
' HUMIDITY, %
20-90 CONTINUOUS RADIATION, RADS (TID)
NOTE '1' CHEMICALS NOT APPLICABLE 4
NOTE 1 - DOSE VARIES WITii COMPONENT (SEE CESSAR-F, TABLE 3.11B-2) i B-6
TABLE B-4 CATEGORY "C" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL PARAMETERS
~
RANGE DURATION TEMPERATURE, F
55 TO 104 CONTINUOUS PRESSURE, PSIG 0
CONTINUOUS HUMIDITY, % 90 CONTINUOUS NOTE '1' RADIATION, RADS (TID)
NOTE '2' CHEMICALS NOT APPLICABLE 0
NOTE 1 - AT OR AB0VE 80 F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 800F (DEWPOINT OF 770F).
NOTE 2 - DOSE VARIES WITH COMPONENT (SEE CESSAR-F, TABLE 3.11B-2).
4
?
B-7
TABLE B-5 CATEGORY "D" ENVIRONMENTAL CONDITIONS-ENVIRONMENTAL RANGE OR PARAMETERS MAXIMUM DURATION 104-120 4 HR.
TEMPERAUTRE, F
104 TO 55 AFTER 4 HR.
ALL PRESSURE, PSIG 0
DURATION 20 HUMIDITY, %
0 E '1' NOTE '2' 6
~
RADIATION, RADS 4 X 10 y (TID)
CHEMICALS NOT APPLICABLE NOTE 1 - AT OR AB0VE 80 F,THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 800F (DEWPOINT OF 77 F).
AT OR AB0VE 1200F, THE M0ISTURE CONTENT U
IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT I
0 120 F (DEWPOINT OF 1130F).
NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED.
B-8
(
TABLE B-6 CATEGORY "E" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL RANGE OR PARAMETERS MAXIMUM DURATION 55 TO 330 0 - 3 MIN'.
TEMPERATURE, F
1011-55 AFTER 3 MIN.
3 0-3 MIN.
PRESSURE, PSIG O
AFTER 3 MIN.
100 0-3 MIN.
HUMIDITY, %
NOTE '2' AFTER 3 MIN.
(NOTE '1')
RADIATION, RADS
<103 (TID)
CHEMICALS NOT APPLICABLE NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED.
NOTE 2 - AT OR AB0VE 80 F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 800F (DEWPOINT OF 77 F).
B-9
.-.a.
.. =...
. =
- u. =..:..-. -.
2.
TABLE B-7 CATEGORY "F" ENVIR0f! MENTAL C0t!DITIONS ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, F
FIGURE B-3 (NOTE '2')
PRESSURE, PSIG 0
ALL DURATION HUMIDITY SAT. STEAM / AIR NOTE '2' MIXTURE RADIATION,. RADS NOTE 'l' CHEMICALS NOT APPLICABLE 4
NOTE 1 - FOR UNCONTROLLED ACCESS AREAS 1 X 10 Y (TID) AND FOR 6
CONTROLLED ACCESS AREAS 4 X 10 y (TID).
NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RAilGE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED.
B-10
u. u... - -.
TABLE B-8 CATEGORY "G" ENVIRONi';E:!TAL CONDITIONS ENVIRONMENTAL PARAMETERS RANGE DURATION FIGURE B-3 (NOTE 'l')
TEMPERATURE, F
PRESSURE, PSIG 0
ALL DURATION SAT. STEAM / AIR HUMIDITY
'MIXTilRE NOTE 'l' i
RADIATION, RADS 31 X 104 (TID) y CHEMICALS NOT APPLICABLE NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED.
B-ll
TABLE B-9 CATEGORY "H" ENVIRONMENTAL CONDITIONS t
ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE',
F 55 TO 104 NOTE '2' PRESSURE, PSIG 0
ALL DURATION 20-90 NOTE '2' HUMIDITY, %
NOTE '1' RADIATION, RADS
<103 (TID) i I
CHEMICALS NOT APPLICABLE I
NOTE 1 - AT OR AB0VE 80 F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 80 F (DEWPOINT OF 77 F).
l i
NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "J" UNLESS OTHERWISE SPECIFIED.
t B-12 i
i
TABLE B-10 CATEGORY "I" ENVIRONMENTAL CONDITIONS (0UTSIDE PLANT BUILT)lNGS) i ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, F
-30 TO 122 NOTE '1' l
PRESSURE, PSIG 0
ALL DURATION HUMIDITY, %
100 NOTE '1' RADIATION, RADS
<103 (TID)
CHEMICALS NOT APPLICABLE NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "K" UNLESS OTHERWISE SPECIFIED.
l l
l B-13 i
TABLE B-11 CATEGORY "J" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, F
65 TO 85 CONTINUOUS PRESSURE, PSIG 0
CONTINUOUS HUMIDITY,%
40-60 CONTINUOUS RADIATION', RADS
<103 (TID)
CHEMICALS NOT APPLICABLE I
i B-14
TABLE B-12 CATEGORY "K" ENVIRONMENTAL CONDITIONS (0UTSIDE PLANT BUILDINGS)
ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, F
-30 TO-120 CONTINUOUS PRESSURE, PSIG-0 CONTINUOUS 20-90 HUMIDITY, %
NOTE '1' CONTINUOUS I
RADIATION, RADS
<103 (TID) l CHEMICALS NOT APPLICABLE 0
NOTE 1 - AT OR AB0VE 80 F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 80 F (DEWPOINT OF 77 F).
AT OR ABOVE 120 F, THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 1200F (DEWPOINT OF 116 F).
B-15
. ~
TABLE B-13 CATEGORY "V-1" ENVIRONMENTAL CONDITIONS (WORST CASE:
IN-CONTAIUMENT):
NOTE 3 ENVIRONMENTAL PARAMETERS RANGE DURATION NORMAL 60 - 122 CONTINUOUS LOCA FIGURE B-1 TEMPERATURE, F
FIGURE B-4 0-12. MIN.
MSLB FIGURE B-1 AFTER 12 MIN.
I NORMAL 0-5 CONTINUGUS PRESSURE, PSIG LOCA FIGURE B-2 MSLB FIGURE B-2 NORMAL NOTE '1' SAT. STEAM / AIR ALL DURATION LOCA MIXTURE HUMIDITY, %
SH. STEAM / AIR MSLB MIXTURE 0-12 MIN.
SAT. STEAM / AIR AFTER 12 MIN.
MIXTURE RADIATION, RADS 1 X 108 (TID)
CHEMICALS NOTE '2' 0
0 NOTE 1 - 95% RELATIVE HUMIDITY (RH) AT 60 TO S0 F, FOR 80 F TO MAXIMUM 0
TEMPERATURE FIXED MOISTURE CONTENT IS EQUIVALENT TO 95% RH AT 80 F, NOTE 2 4400 PPM BORON AS H B0, 50-100 PPM HYDRAZINE AS N H2 g AND P H
3 3
4 TO 10.
NOTE 3 - COMBINED " WORST CASE" CONDITION FOR NORMAL /LOCA/MSLB ENVIRONMENTS.
B-16
TABLE B-14 CATEGORY "V-2" EtlVIR0!1i1EilTAL C0f!DIT10NS (WORST CASE: OUTSIDE C0ilTAIElMENT): NOTE 2 i
ENVIRONME!1TAL PARAMETERS RANGE DURATION
, NORMAL 60-104 CONTINUOUS LOCA FIGURE B-3 TEMPERATURE, F
60-330 0-3 MIN.
MSLB FIGURE B-3 AFTER 3 MIN.
_ NORMAL 0
CONTINUOUS LOCA 0
ALL DURATION PRESSURE, PSIG 3
0-3 MIN.
MSLB 0
AFTER 3 MIN.
NORMAL NOTE 'l' HUMIDITY, %
IUh ALL DURATION LOCA SAT. STEAM / AIR MSLB MIXTURE ALL DURATION RADIATION, RADS 5 X 107 (TID)
CHEMICALS NOT APPLICABLE NOTE 1 - 95% RELATIVE HUMIDITY (RH) AT 60 TO 80 F.
FOR 80 F TO MAXIMUM TEMPERATURE FIXED MOISTURE CONTENT IS EQUIVALENT TO 95% RH AT 80 F.
NOTE 2 - COMBINED " WORST CASE" CONDITION FOR NORMAL 7LOCA/MSLB ENVIR0flMENTS.
B-17
Figure B-1 TYPICAL CONTAINMENT ATMOSPHERE TEMPERATURE CONDITION FOLLOWING LOCA 500 400 7
s'300
\\
a E
M 200 RAMP TEMPERATURE FROM INITIAL y
AMBIENT CONDITION (120 F) TO PEAK 0
100 TEMPERATURE (350 F) OVER 10 SECONDS 0
i 0
1 2
3 4
5 6
10 10 10 10 10 10 10 TIME, MINUTES
Figure B-2 TYPICAL CONTAINMENT ATMOSPHERE PRESSURE CONDITION FOLLOWING LOC A 70 i
i i
i 60 50 S* 40 7
a5 m 30 M
RAMP PRESSURE FROM INITIAL AMBIENT 20 CONDITION (0~PSIG) TO PEAK PRESSURE (60 PSIG) 0VER 10 SECONDS 10 0
8 i
0 1
2 3
4 5
6 10 10 10 10 10 10 10 TIME, MINUTES
Figure B-3 TYPICAL ANNULUS ATMOSPHERE TEMPERATURE CONDITION FOLLOWING LOCAIMSLB 500 400 e-EE300
?
E B
E'200
- E b'
100 I
0 0
1 2
3 4
5 6
10 10 10 10 10 10 10 TIME, MINUTES i
l
\\
+.
m-
Figure B-4 TYPICAL CONTAINMENT ATMOSPHERE TEMPERATURE CONDITION FOLLOWING MSLB l
400 350 300 u-
.o E{
i2 l
g 250 t
E RAMP TEMPERATURE FROM INITIAL
- s AMBIENT CONDITION (120 F) TO PEAK TEMPERATURE 0
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Figure B-8 TYPICAL ENVIRONMENTAL TEST PROFILE FOR CATEGORY "C" ENVIRONMENTAL CONDITIONS 170 RH < 90%
(NO HUMIDITY CONTROL) l NOTES:
l NOTE 4 150 RH = 90% l
- 1. T = TIME TO STABILIZE TEST TEMPERATURE-EkTERNAL TO TEST ITEM lTS
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NOTE 4 l
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Figure B-10 TYPICAL ENVIRONMENTAL TEST PROFILE FOR CATEGORIES "H" AND "J" ENVIRONMENTAL CONDITIONS 170 RH < 90 %
(NO HUMIDITY CONTROL) 150 NOTES:
- 1. T = TIME TO STABILIZE TEST a
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Figure B-11 TYPICAL INSIDE CABINET ENVIRONMENTAL TEST PROFILE FOR CATEGORIES "H" AND "J" ENVIRONMENTAL CONDITIONS 170 j
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l NOTES-TE
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- * = = = - -
ICE-98/(411CE-C)/ca-1 APPENDIX C TYPICAL QUALIFICATION PLAN FOR CLASS lE EQUIPMENT LOCATED IN A HARSH ENVIRONMENT
, C.1 PURPOSE The purpose of this Appendix is to discuss an equipment specific qualification plans for typical Class 1E equipment located in a harsh environment.
This plan, so identified as Table C-1, supple-ments the equipment specific information provided in the main body of this report. The attached plan provides a summary plan and is not to be confused with detailed vendor prepared qualifica-tion plans discussed in Sections 6.0 and 8.0.
C.2 EQUIPMENT This Appendix uses the Reactor Coolant Pump Shaft Speed Sensing System located in the containment as sample equipment.
C. 3 TESTING SEQUENCE Testing will be conducted sequentially on production units as defined in Section 5.1.4.
C.4 ACCEPTANCE CRITERIA Acceptance criteria will be established based on the required Class 1E function.
In general, these criteria will take the form of instrument accuracies, or required actuation functions during and after specified periods under accident stress conditions.
These accuracies or functions and operating time values will be used as the basis for assumptions and results in the Safety Analysis in the SAR.
C.5 TEST UNITS Test units will undergo all required age condition and qualifica-tion testing. Where differences exist between models of a product line, qualification will be supported by analysis or similarity, demonstrating qualification.
C-1
C.6 AGING Aging will be addressed according to Section 5.3.
C.7 ENVIRONMENTAL' CONDITIONS AND EFFECTS Environmental conditions and effects will be addressed according to Section 3.4.
a 9
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C-2 m
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l 1
TABLE C-1 REACTOR COOLANT PUMP SHAFT SPEED SENSING SYSTEM t
TYPICAL QUALIFICATION PLAN i
Nuclear Power Systems P
COMBUSTION ENGINEERING INC.
Windsor, Connecticut 4
Prepared by Date a
Approved by Date 5
i Approved by Date I
Approved by -
Date Project Manager l.
9 This document is the property of Combustion Engineering, Inc. (C-E),
Windsor,fConnecticut and is to be used only for the purpose of the
'edroement with C-E pursuant to which it is furnished.
.. < s.
! t f
Issue Date f-
~
C-3
?k. -...
RECORD OF REVISI0!is fl0.
DATE PAGES IflVOLVED PREPARED BY APPROVALS 2
00 Original Issue l
1 C-4 l
TABLE OF CONTENTS Section Title Page No.
1.0 PURPOSE C-6 2.0 ASSIGNMENT OF RESPONSIBILITY C-7
3.0 REFERENCES
C-8 4.0 QUALIFICATI0fi PLAN REQUIREMENTS C-9 4.1 QUALIFICATION REQUIREMENTS C-9 4.2 TEST PLAN C-10 5.0 SCHEDULE C-15 6.0 DOCUMENTATION C-15 LIST OF TABLES Table No.
Title Page No.
I QUALIFICATION PARAMETERS C-16 II QUALIFICATION REQUIREMENTS C-18 i
LIST OF FIGURES i
l Figure No.
Title Page No.
1 GENERIC FLOOR REQUIRED RESPONSE SPECTRUM C-19 2
GENERIC MODULE REQUIRED RESPONSE SPECTRUM _
C-20 l
3 TYPICAL TEST PROFILE CONTAINMENT BUILDING C-21 4
ACTIVITY / RESPONSIBILITY MATRIX C-22 5
TASK PLAN C-23 C-5 i
i
, _ _. ~ - -.
1.0 PURPOSE This document provides the requirements, met'.od and overall plan for qualification of the Reactor Coolant Pump Shaft Speed Sensing System (RCPSSSS).
Nuclear Environmental Qualification of any safety-related device 1
to meet the intent of IEEE 323-1974 and NUREG 0588 is usually a three-step process, i.e., 1) radiation exposure; 2) aging; and 3)
Design Basis Event Qualification (seismic, and, for equipment inside containment. LOCA/MSLB). The purpose of the first two steps is to put the sample equipment to be used for qualification into a condition that represents the v;orst state of deterioration that a plant operator will permit prior to taking corrective action, i.e., its end-of-qualified-life condition. The next step demonstrates that it still has adequate margin remaining to withstand the added environmental stresses of specified design basis events and still perform its safety-related functions.
It is incumbent on the equipment supplier to assure that the components and materials contained in the equipment actually placed into service are.the same as those qualified. The specific details of the qualification are defined herein.
l l
i C-6 I
2.0 ASSIGNMENT OF RESPONSIBILITY Figure 4 identifies the major qualification activities with the corresponding responsible party. All activities and parties so indicated represent only a planned approach.
Final determination of responsibilities will be established upon final evaluations.
A listing of these activitiet is provided in the following sections.
2.1 All qualification type test plans, procedures and reports, will be provided by Combustion Engineering.
2.2 Aging analysis, procedures, and accelerated age conditioning will be provided by facilities contracted by Combustion Engineering (C-E).
2.3 Test units will be provided by Bently-Nevada Corporation.
f 2.3.1 Three Proximity Probe Assemblies (part no. Later) will be used for this program.
4 2.3.2 Three coaxial extension cables with mating connectors (part no.
i Later) will be used for this program.
2.3.3 Three pulse transmitters (part no. Later) will be used for this program.
l 2.3.4 Three signal processors (part no. Later) each consisting of a power supply, 4 pulse shapers, 4 voltage regulators and wiring will be used for this program.
i C-7
=
4 f
3.0 REFERENCES
3.1 NUREG-0588, Interim Staff Position on Environmental Qualification of. Safety-Related Electrical Equipment.
3.2 IEEE Standard 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations.
3.3 IEEE Standard 344-1975, IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.
I 3.4 Class 1E Qualification of Electrical Equipment CENPD-255, Rev. 3.
l l
1 C-8
4.0 QUALIFICATION PLAN REQUIREMENTS The following sections define the existing RCPSSSS qualification levels, performance requirements and new requirements necessary to meet Reference 3.1.
4.1 QUALIFICATION REQUIREMENTS The RCPSSSS is to be qualified for in containment environments and controlled environments of equipment rooms either in the control or auxiliary buildings.
4.1.1 Safety-Related Functions The safety classification of this equipment is Class 1E.
The subject equipment provides essential services in support of emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, or is otherwise essential in providing support to prevent significant release of radioactive material to the environment.
The safety ? elated functions are described in the following paragraphs.
4.1.2 Description The RCPSSSS is required to operate during and after a main steam line break and not during or after a loss of Coolant Accident.
All components shall be designed and installed such that no loss of system function will occur during and after a seismic disturbance of intensity up to and including that corresponding to the Design Basis Earthquake (DBE).
i C-9
4.2 TEST PLAN 4.2.1 Aging Analysis A detailed bill of materials will be prepared together with the design details of the equipment for use in obtaining an aging analysis. This analysis, will determine the aging processes for the components, develop failure times, evaluate the effects of low level radiation on the components and ultimately result in accelerated age conditioning procedures to be used for accelerated thermal aging. A definition of the expected qualified life will be part of the analysis.
4.2.1.1 Thermal aging qualification requirements remain as specified in Section 4.2.2.1.
4.2.1.2 Temperature / humidity requirements for qualification remain as specified in Table I.
4.2.1.3 Cycling aging qualification requirements remain as specified in Section 4.2.2.3.
4.2.1.4 Radiation aging qualification requirements remain as specified in Table I.
4.2.2 Accelerated Age Conditioning The procedures developed in the previous section will be used to age the test units of section 2.3 to their end of qualified life.
Thermal aging of these units will be done in the appropriate test facilities while the equipment is energized and functioning. The requirements of Table II will be performed as well as on/off cycling of the power to the units for a total of 5 cycles per year of qualified life.
C-10
4.2.2.1 Thermal age testing utilizing Arrhenius methodology will be accomplished to project a qualified life for each material or component in the system whose degradation could cause the equipment to fail to perform its intended function.
4.2.2.2 Radiation age testing will be accomplished and is accounted for in Section 4.2.4.2.
4.2.2.3 Cycle age testing is not required on the RCPSSSS. This system does not contain electro-mechanical components.
4.2.3 Performance Requirements The RCPSSSS safety function is to create a signal equivalent to Reactor Coolant Pump Shaft Sp'eed for use by the appropriate process instrumentation.
4.2.3.1 Signal transmission capability is a performance requirement during worse case environmental and seismic conditions.
4.2.3.2 Performance of this equipment is based on a power source input of 120 VAC + 10%, 60 Hz + 5%, sufficiently derated for continuous operation within the specified environmental conditions of Reference 3.5.
4.2.3.3 Input and output signal specifications will meet the necessary System Acceptance Criteria for that equipment.
4.2.3.4 Upon completion of the aging process, normal production tests will be performed. These tests will verify the equipments functional performance.
4.2.4 Environmental Tests Environmental testing to the profiles defined in Reference 3.4, Appendix B, Figures B-7A ( B-ll will be performed. These profiles include the appropriate margins of Reference 3.2.
C-ll
4.2.4.1 Temperature / Humidity Requirements The RCPSSSS will be qualified to the temperature and humidity conditions as defined by Table 1.
4.2.4.2
^ Radiation Requirements' The RCPSSSS will be qualified to the radiation levels as defined by Table 1.
4.2.4.3 Chemical Spray Requirements The RCPSSSS will be tested to chemical spray environments as defined by Table 1.
4.2.4.4 Pressure Requirements The RCPSSSS will be tested to pressure environments as defined by Table 1.
4.2.S Power Supply Variation During testing defined in Section 4.2.4 voltage and frequency will be varied to the limits defined in Section 4.2.3.2 and the functional capabilities will be monitored to assess impact, if any.
4.2.6 Subnergence The RCPSSSS in containment components will be located in an area which would not be expected to be subjected to subnergence even under the most extreme conditions.
l.
4 C-12
4.2.7 Dust Environments RCPSSSS components s 'ch could be adversely effected by dust accumulation will be protected against accumulation such that, provided the periodic maintenance as specified by Reference 3.4 is conducted, operational impairment will not occur.
4.2.8 Seismic The equ9 ment specified herein is seismic Category I and shall be qualified to withstand the effects of the Operational Basis Earthquake (0BE) and the Safe Shutdown Earthquake (SSE) without loss of functional or physical integrity. The 0.B.E. and S.S.E.
at the equipment mounting points are characterized by the required response spectra (R.R.S) curves, Figure 1 for the Proximity Probe Assembly and Pulse Transmitter and Figure 2 for the Signal Processor.
Compliance to the above requirements shall be demonstrated by test in accordance with Reference 3.3.
4.2.8.1 Physical Integrity During the seismic event no parts of the equipment shall loosen, bend or crack in a manner that impairs proper operation.
In addition, no parts of the equipment shall loosen and become a missile hazard. The stresses developed during the seismic event shall be less than the allowable yield stress for the material.
l 4.2.8.2 Functional Integrity l
During and after the seismic event there shall be no loss of function. The following shall constitute loss of function.
I pulse characteristics that deviate from specified tolerances.
C-13 i
Missed or extra pulses.
4.2.8.3 Vibration Non-Seismic vibration will be addressed by an engineering analysis on the Proximity Probe and Extension Cable portions of the RCPSSSS only.
4.2.9 Acceptance Criteria Each test will meet the necessary System Acceptance Criteria for that equipment.
e
}
{
l l
5.0
' SCHEDULE Figure 5 defines the sequence for each of the qualification
- activities.
6.0 DOCUMENTATION Detailed test plans, procedures and reports will be attached as appendices to this document as they become available. All specified items of Appendix E of Reference 3.1 will be addressed. Qualifica-tion documentation shall be in accordance with Section 8.4 of Reference 3.4.
t l
C-15 l
i
TABLE I QUALIFICATION PARAMETERS Proximity Probe and Extension Cable NORMAL DURATION WORST CASE DURATION TEMP 55-122*F Continuous See Figure 3 70 min PRESS 0-5 PSIG Continuous See Figure 3 70 min 7
7 RADIATION 4 x 10 R-g 40 yr int 4 x 10 R-g Total Accident HUM %
20 - 90%
Continuous See Figure 3 70 min CHEM (2)*
SPRAY N/A N/A Up to 4400 PPM 60 min Baron with hydra-zine sodium phos-phate solution pH 4.0 to 10.0 Pulse Transmitter NORMAL DURATION WORST CASE DURATION TEMP 55-122 F Continuous See Figure 3 70 min PRESS 0-5 PSIG Continuous See Figure 3 70 min 7
7 RADIATION 4 x 10 R-g 40 yr int 4 x 10 R-g Total Accident l
HUM 20 - 90%
Continuous See Figure 3 70 min CHEM (2)*
SPRAY N/A N/A Up to 4400 PPM Boron with hydra-zine sodium phos-phate sclution pH 4.0 to 10.0
- See notes for Figures in parentheses on following page.
l C-16
TABLE I (Cont.)
Signal Processor NORMAL DURATION WORST CASE DURATION II)
TEMP 75110 F Continuous 40*-137 F 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> HUM 50 i 10%RH Continuous 60 to 80*F-90%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 80* to 137'F-Fixed moisture content equivalent to 95%RH at 80 F 3
RADIATION Less than 10 R CHEMICAL SPRAY N/A PRESSURE N/A AGING 2000 Power Cycles SEISMIC Per Reference 3.3 Notes:
1.
Includes 15 F margin as required by IEEE-323-1974 2.
Chemical Spray shall consist of:
a) 4400 PPM Boron as H B0 3 3 b) 50-100 PPM Hydrazine, H H 24 c)
Sodium Phosphate pH 4.0 to 10.0, Na P0 3 4 2
d)
Flow rate 0.15 GPM/Ft C-17
2 TABLE II QUALIFICATION REQUIREMENTS QUALIFICATION REQUIREMENTS APPLICABILITY AGING ANALYSIS YES ACCELERATED AGE CONDITIONING YES TEMPERATURE / HUMIDITY YES PRESSURE Proximity Probe, Extension Cable and Pulse Transmitter 4
RADIATION YES CHEMICAL SPRAY Proximity Probe, Extension Cable and Pulse Transmitter POWER SUPPLY VARIATION YES SUBMERGENCE DUST YES SEISMIC YES I
PERFORMANCE REQUIREMENTS YES ACCEPTANCE CRITERIA YES REDESIGN CONSIDERATIONS YES DOCUMENTATION YES C-18 Y
FIGURE 1 Generic Auxiliary Building floor Recuired Response Spectrum Horizontal & Vertical OBE & SSE 1% Of Critical Damping
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TYPICAL CONTAINMENT BUILDING ENVIRONMENTAL TEST PROFILE FOR CATEGORY "A-1" AND "A-2" ENVIRONMENTAL CONDITIONS k
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ACTIVITY / RESPONSIBILITY MATRIX FIGURE 4 ASSIGNMENT OF RESPONSIBILITY
^
TEST LAB EQUIPMENT ACTIVITY C-E VENDOR VENDOR OTHER i
Qualification Test Plan Development.
X j
Aging Analysis.
X Accelerated Age Conditioning.
X Qualification Test Procedure Development.
.X Environmental Qualification Testing.
X Seismic Qualification Testing.
X 4
Test Sample Procurement.
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_ y __.g ENVIRONMENTAL TEST 4
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. TASK PLAN
APPENDIX D TYPICAL QUALIFICATION PLANS FOR CLASS 1E EQUIPMENT LOCATED IN A NON-HARSH ENVIRONMENT
ICE-98/(411CE-D)/ca-2 0.1 PURPOSE 1
The purpose of this appendix is to discuss an equipment specific qualification plan for typical Class 1E equipment located in a non-harsh environment.
This plan, so identified as Table 0-1, supplements the equipment specific information provided in the main body of this report.
The attached plan outlines only a summary plan and is not to be confused with detailed vendor prepared qualification plans discussed in Sections 6.0 and 8.0.
D.2 EQUIPMENT This Appendix uses the Remote Shutdown Panel located in a non-harsh environment as sample equipment.
0.3 TESTING SEQUENCE Testing will be conducted sequentially on production units as defined in Section 5.1.4.
D.4 ACCEPTANCE CRITERIA Acceptance criteria will be established based on the required Class 1E function.
In general, these criteria will take the form of instrument accuracies or actuation functions during and after specified periods under stress conditions. These accuracies or functions and operating time values will be used as the basis for assumptions and results in the Safety Analysis in the SAR.
D.5 TEST UNITS Test units will undergo required age conditioning and qualification testing.
Redundant equipment in cabinets or panels will have one of the bays tested. Where differences exist between models of a product line, qualification will be supported by analysis or similarity, demonstrating qualification.
l f
D-1 l
f
D.6 AGING Aging will be addressed according to Section 5.3.
.D.7 ENVIRONMENTAL CONDITIONS AND EFFECTS Environmental conditions and effects will be addressed according to Section 3.4.
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TABLE D-1 REMOTE SHUTDOWN PANEL TYPICAL QUALIFICATION PLAN Nuclear Power Systems COMBUSTION ENGINEERING, INC.
Windsor, Connecticut 4
Prepared by, Date Approved by Date Approved by Date Approved by Date Project Manager This document is the property of Combustion Engineering, Inc. (C-E),
Windsor, Connecticut and is to be used only for the purpose of the agreement with C-E pursuant to which it is furnished.
Issue Date D-3 1
RECORD OF REVISI0ftS fl0.
DATE PAGES If4VOLVED PREPARED BY APPROVALS 00 Original Issue e
0 D-4
TABLE OF CONTENTS Section Title Page No.
1.0 PURPOSE D-6 2.0 ASSIGNMENT OF RESPONSIBILITY D-6
3.0 REFERENCES
D-7 4.0 QUALIFICATION PLAN REQUIREMENTS D-8 4.1 QUALIFICATION REQUIREMENTS D-8 4.2 TEST PLAN 0-9 5.0 SCHEDULE D-13 6.0 DOCUMENTATION D-13 LIST OF TABLES Table No.
Title Page No.
1 ENVIRONMENTAL CONDITIONS D-14 2
NUREG-0588 ADDITIONAL REQUIREMENTS D-15 LIST OF FIGURES Figure No.
Title Page No.
1 GENERIC AUXILIARY BUILDING REQUIRED FLOOR RESPONSE SPECTRUM D-16 2
GENERIC MODULE REQUIRED RESPONSE SPECTRUM D-17 3
ENVIRONMENTAL TEST PROFILE D-18 4
ACTIVITY / RESPONSIBILITY MATRIX D-13 5
NUREG-0588 GENERAL TASK PLAN 0-20 1
D-5 i
1.0 P23 POSE Thir document provides the requirements, methods and overall plan for the qualification of the Remote Shutdown Panel.
It also provides in the Appendices, the detailed test procedures and reports developed during this qualification effort (Later).
2.0 ASSIGNMENT OF RESPONSIBILITY Figure 4 identifies the major qualification activities with the corresponding' responsible party. All activities and parties so indicated represent.only a planned opproach.
Final determination of responsibilities will be established upon final evaluations.
A listing of these activities is provided in the following sections.
2.1 All qualification type test plans, procedures and reports, will be provided by Combustion Engineering.
2.2 Aging analysis, procedures, and. accelerated age conditioning will be provided by facilities contracted by Combustion Engineering.
2.3 Components as required will be obtained from respective manufac-I turers/ suppliers by Combustion Engineering.
D-6 me;<
f "
?
3.0 REFERENCES
i 3.1 NUREG-0588, Interim Staft Position on Environmental Qualification of Safety-Related Electrical Equipment.
- e..
- 3. 2 IEEE Standard 323-1974, IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations.
k
/
3.3 Class 1E Qualification of Electrical Equipment CENPD-255 Rev. 03.
/
3.4-IEEE Std. 344-1975, " Recommended Practices for Seismic Qualifica-l
tion of Class 1E Equipment for Nuclear Power Generating Stations".
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4.0 Q'UALIFICATION PLAN REQUIREMENTS The following sections define the program for the qualification of the Remote Shutdown Panel.
4.1 QUALIFICATION REQUIREMENTS The Remote Shutdown Panel has been qualified for controlled environments of equipment rooms either in the control or auxiliary buildings. Table 2 defines the applicable requirements of Reference 3.3.
4.1.1 Safety-Related Functions The safety classification of this equipment is Class 1E. The subject equipment provides essential services in support of emergency reactor shutdown, containment isolation, reactor core cooling, containment and reactor heat renoval, or is otherwise essential in providing support to prevent significiant release of radioactive material to the environment. The safety related functions are described in the following paragraphs.
4.1.2 Description The Remote Shutdown Panel's Safety function is to house required Class lE instrumentation and controls to support remote plant shutdown.
l The Remote Shutdown Panel design provides the capability to monitor, achieve and maintain a Hot Shutdown Condition remote from the control room in the event of control room inaccessibility due to non-destructive causes. The RSP design also provides for single failure criteria and for concurrent loss of offsite power.
I l
D-8 l
l
4.2 TEST PLAN 4.2.1 Aging Analysis A detailed bill of materials will be prepared together with the design details of the equipment for use in obtaining an aging analysis.
This equipment will undergo an aging analysis that focuses on the identification of known aging mechanisms that significantly increase the equipments susceptibility to its design basis event (seismic only for non-harsh environments).
If no known significant aging mechanisms are found, a surveillance / preventive maintenance (S/PM) program will be developed to monitor for degradation trends that suggest increasing seismic susceptibility.
If an aging mechanism is found that is known to significantly increase the equipments seismic susceptibility with time, then that mechanism will be analyzed to determine whether an accelerated aging program or a periodic part replacement program is appropriate.
4.2.2 Performance Requirements The Remote Shutdown Panel's Safety function is to house required Class IE instrumentation and controls to support remote plant shutdown.
The majority of the equipment housed by the Remote Shutdown Panel is qualified individually and not as part of the cabinet. Qualifi-cation details for that equipment is described in respective qualification programs. Components located in the Cabinet not specifically addressed in an individual Qualification Program document (e.g., connectors, terminal blocks) will either be qualified in other cabinets (e.g., the CEDMCS Auxiliary Cabinet) or will be individually qualified to meet the requirements of Reference 3.1.
The Remote Shutdown Panel in its entirety will 0-9
not undergo testing in addition to that previously performed.
The components supplied by C-E will be addressed in accordance with this program.
Normal production tests will be performed as applicable to verify functional performance of the equipment.
4.2.3 Environmental Tests Environmental testing to the profiles defined in References 3.3, Appendix B, Figure 8-10 will be performed. These profiles include the appropriate margins of Reference 3.2.
During this testing, voltage and frequency will be varied as appropriate and the functional capabilities will be monitored to assess impact, if any exists.
4.2.3.1 Temperature / Humidity Requirements Temperature, Humidity and Cycling requirements for qualification remain as specified in Table 1, as no accident environments are expected in the vicinity of the cabinet.
4.2.3.2 Radiation Requirements Low level radiation for a qualitied life of 40 years will be 3
established at 10 Rads gamma TID. For qualified life of less than 40 years a proportional TID will be used.
4.2.3.3 Chemical Spray Requirements This equipment is outside containment so chemical spray is not considered in the qualification of this equipment.
D-10
4.2.3.4 Pressure P.equirements This equipment is outside containment so pressure conditions are not considered in the design.
4.2.4 Dust Dust environments will be addressed by an engineering analysis for applicable equipment.
4.2.5 Seismic Testing The cabinets specified herein are seismic category I and shall be designed to withstand the effects of the Operation Basis Earthquake (0.B.E) and the Safe Shutdown Earthquake (S.S.E) without loss of physical or functional integrity. The 0.B.E. and S.S.E. at the cabinet mounting points is characterized by the required response spectra (RRS) curve, Figure 1.
Compliance to the above require-ments shall be demonstrated by test.
The cabinets specified herein shall be sufficiently rigid to the seismic excitation described above, such that the seismic motions at the mounting points of the equipment supplied by others are less severe than those motions characterized by the required response spectra (RRS) curves provided in Figure E.
4.2.5.1 Physical Integrity During the seismic event, no parts of the cabinets shall loosen, bend, crack or become a missile hazard. The stresses developed during the seismic event shall be less than the allowable yield stress for the material.
l 1
D-ll i
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4.2.5.2 Out of Scope Equipment The mountings details, weight, center of mass and dimensions of equipment supplied by others will be forwarded by the Purchaser prior to the start of the seismic test.
This information is to be used for determining dummy loads for actual equipment simulation during seistnic testing.
l The accelerometer data from the simulated equipment is compared to the actual equipment accelerometer data from its generic module curve to insure that seismic integrity is maintained.
4.2.6 Acceptance Criteria Each test will meet the necessary System Acceptance Criteria for that equipment.
i D-12 l
.=
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4 5.0 SCHEDULE l
Figure 5 defines the sequence for each qualification activity.
6.0 DOCUMENTATION Detailed test plans, procedures and reports will be attached as appendices to this document as they become available. Qualifi-cation documentation will be in accordance with Section 8.4 of Reference 3.3.
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TABLE 1 1
-ENVIRONMENTAL CONDITIONS 3
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TEMPERATURE Normal 65*F - 85 F Abnormal See Figure 3 Duration 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> maximum HUMIDITY Normal 40% RH - 60% RH Abnormal See Figure 3 2
Duration 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> maximum 3
RADIATION Less than 10 1
l CHEMICAL SPRAY N/A PRESSURE N/A I
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D-14
l TABLE 2 QUALIFICATION REQUIREMENTS APPLICABILITY AGING ANALYSIS YES ACCELERATED AGE CONDITIONIh1 TEMPERATURE / HUMIDITY YES PRESSURE RADIATION YES CHEMICAL SPRAY POWER SUPPLY VARIATION YES
'1 SUBMERGENCE YES DUST YES SEISMIC YES j
PERFORMANCE REQUIREMENTS YES ACCEPTANCE CRITERIA YES DOCUMENTATION YES i
D-15
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Figure 3 TYPICAL ENVIRONMENTAL TEST PROFILE FOR CATEGORIES "H" AND "J" ENVIRONMENTAL CONDITIONS 170 RH <C 00 %
(NO HUMIDITY CONTROL)
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150 NOTES:
- 1. T3 = TIME TO STABILIZE TEST I
NOTE 4 l
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. M = M ll ITEM TS
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ACTIVITY / RESPONSIBILITY MATRIX FIGURE 4 ASSIGNMENT OF RESPONSIBILITY TEST LAB EQUIPMENT ACTIVITY C-E VEND 0R VEND 0R OTHER Qualification Test Plan Development.
X Aging Analysis.
X Accelerated Age Conditioning.
X Qualification Test Procedure Development.
X Environmental Qualification Testing.
X Seismic Qualification Testing.
X Test Sample Procurement.
X D-19
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s PREPARE AGING ANALYSIS BASELINE PERFORMANCE TESTS 4
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ENVIRONMENTAL TEST SEISMIC TEST FINAL BASELINE TESTS DOCUMENTATION
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l 2
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b
S APPENDIX E BIBLIOGRAPHY
_ ~..
s BIBLIOGRAPHY E.1 IEEE Std. 101-1974, " Guide for Statistical Analysis of Thermal Life Test Data".
E.2 IEEE ll2A-1964, " Test Procedure for Polyphase Induction Motors and Generators".
E.3 IEEE 117-1974, " Standard Test Procedure for Evaluation of Systems of Insulating Materials for Random-Wound AC Electric Machinery".
E.4 IEEE 275-1966, " Proposed Test Procedure for Evaluation of Systems of Insulating Materials for AC Electric Machinery Employing Form Wound Preinsulated Stator Coil.
E.5 IEEE Std. 278-1967, " Guide for Classifying Electrical Insulating Materials Exposed to Neutron and Gamma Radiation".
E.6 IEEE Std. 334-1974, " Standard for Type Tests of Continuous Duty Class lE Motors for Nuclear Power Generating Stations".
E.7 IEEE Std. 344-1975, "IEEE Recommended Practices for Seismic Qualification of Class lE Equipment for Nuclear Power Generating Sta tions".
E.8 IEEE Std. 352-1975, " Guide for General Principles for Reliability Analysis of Nuclear Power Generating Station Protection System".
E.9 IEEE Std. 381-1977, " Standard Criteria for Type Tests of Class lE Modules Used in Nuclear Power Generating Stations".
E.10 IEEE Std. 382-1972, "IEEE Trial Use Guide for Type Test of Class lE Electric Valve Operators for Nuclear Power Generating Stations".
E-1
E.ll IEEE Std. 383-1974, " Type Test of Class lE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations".
E.12 IEEE Std. 577-1975, " Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations".
E.13 IEEE Std. 650-1979, " Qualification of Class lE Static Battery
^
Charges and Inverters for Nuclear Power Generating Stations".
E.14 EPRI NP-1588, "Research Project 890-1, Final Report, "A Review of Equipment Aging Theory and Technology", September, 1980.
E.15 CENPD-182, " Seismic Qualification of C-E Instrumentation and Electrical Equipment", November 1975, C-E Power Systems.
E.16 TIS-4983, "The Practical Implementation of Regulatory Guide 1.75 on Nuclear Plant Instrumentation Systems," Davis, John W. and Schultze, Richard G., presented at symposium on Nuclear Power Systems, sponsored by IEEE, New Orleans, Louisiana, October 20-22, 1976.
E.17
" Metallurgical Failure Modes of Wire Bonds", Harmon, George G.,
12th Annual Proceedings, Reliability Physics, 1974, sponsored by IEEE, Las Vegas, Nevada, April 2-4, 1974; p. 137.
E.18
" Practical Applications of Acelerated Testing-Introduction", Peak D.
S., 13th Annual Proceedings, Reliability Physics, 1975, sponsored by IEEE, Las Vegas, Nevada, April 1-3, 1975; pgs. 253-254.
E.19 TIS-5206, " Meeting the Latest Qualification Requirements for Class lE Protection System Equipment - A Practical Approach",
Daigle, R.
P., and Breen, R.
J., presented to APC, Chicago, April 18-20, 1977.
E-2
E.20 MIL-HDBK-217C " Military Standardization Handbook, Reliability Prediction of Electronic Equipment".
E.21
" Aging of Class lE Modules", McGrath, Thomas J., IEEE Transactions on Nuclear Science, Volume NS-22, February 1975.
E.22 Report F-C3906, " Qualification Test of Electrical Cables under Simulator Reactor Containment Service Conditions Including Loss of Coolant Accident While Electrically Energized", Franklin Institute Research Laboratories, July 1974.
E.23 NASA CR-1785, CR-1786, CR-1787, CR-1834, CR-1873, Radiation Effects Design Manual", Vol. 1, 2, 3, 4, 5. 1971.
E.24
" Aging Technology," Roberts, Charles W., Wyle Laboratories, August 24, 1976.
E.25 ASTM D 2953-71, " Classification System for Polymeric Materials for Service in Ionizing Radiation".
E.26 NUREG/CR-0276 and NUREG/CR-0401, " Qualification Testing Evaluation Quarterly Reports".
E.27 NEMA MG-1, 1972, Motors and Generators E.28 ASME Boiler and Pressure Vessel Code i
E.29 Hydraulic Institute Standards l
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I E-3
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9 APPENDIX F BASIS FOR PUMP AND VALVE OPERATION PARAMETERS
i BASIS FOR PUMP AND VALVE OPERATION PARAMETERS F.1 PURPOSE The purpose of this appendix is to provide the basis upon which valve and pump motor electromechanical cycles will be developed.
The following information provides typical plant operation parameters which will form the basis for establishing the number of electro-mechanical cycles in support of equipment qualification. The actual number of cycles calculated plus margin will be defined in the appropriate equipment specific qualification documentation.
F.2 TYPICAL PLANT OPERATION PARAMETERS F.2.1 Normal Operation (40 year duration - Note 8)
A.
Plant Events Event Occurrences Notes Cold Shutdown 3/ year 4, 6 Refueling 1/ year 4
Hot Standby 2/ year 1,4,6 Inservice Testing 12/ year 2,10 Pre-Operational Testing 25 Valve Manufacturer's Testing 5
Pump Motor Manufacturer's Testing 1
9 F-1
~
B.
Systems Events System Event Occurrences Notes SIS, SCS Leakage Control 1000/ year 6
CSS & IR (Secondary Systems)
RAS, SIAS and CSAS actuation 4/ year SCCS System Maintenance a.
General Maintenance 4/ year b.
Blowdown line maintenance 40/ year c.
Chemical addition line maintenance 20/ year MSIS actuation 4/ year 6
EFAS actuation 4/ year 6
CVCS Resin Sluicing 1/ year Charging Flow Modulation 1000/ year 3
Drain RTD 100/ year General System Maintenance 4/ year SIAS and CIAS actuation 4/ year 6
SS Sampling 3/ day General System Maintenance 4/ year CIAS actuation 4/ year.
6 F.2.2 Post-DBE Operation (120 day duration) - Note 5 Event Occurrences Notes Cold Shutdown 1
6,7 NOTES i
l.
Cold shutdown can be utilized to encompass operations required for hot standby.
2.
It is assumed that operations for a cold shutdown refueling, or hot standby qualifies as an inservice test (when operation l
of a component is required during that plant maneuver).
F-2 I
I
3.
Charging pump sequence is assumed to be two primary pumps plus one on standby (to be initiated if required). Primary pump duty to be rotated between the three pumps and that total hours over 40 years will equalize for the three pumps.
4.
10 modulations of throttling valves per plant cooldown or start up is assumed.
5.
The event that causes a DBE is either a LOCA or MSLB.
6.
Cold shutdown and hot standby can be initiated by RAS, CSAS, SIAS, CIAS, MSIS or EFAS events.
System actuations are the result of actual events, instrument malfunctions, or spurious signals.
7.
Either via SCS or HPSI system long term cooling.
8.
It is assumed that there are 308 days of full power operation per year.
9.
Tests per IEEE 112A - 1966.
- 10. Tests per ASME Section XI.
F-3
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