ML20040C645
ML20040C645 | |
Person / Time | |
---|---|
Site: | Shoreham File:Long Island Lighting Company icon.png |
Issue date: | 01/15/1982 |
From: | STONE & WEBSTER, INC. |
To: | |
Shared Package | |
ML20040C640 | List: |
References | |
IEB-79-01B, IEB-79-1B, NUDOCS 8201290116 | |
Download: ML20040C645 (400) | |
Text
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Revision 1 January 15, 1982 ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS 1E EQUIPMENT FOR SHOREHAM NUCLEAR POWER STATION - UNIT 1 LONG ISLAND LIGHTING COMPANY O
O STONE S WEBSTER ENGINEERING CORPORATION CKOhhoh22 PDR
TABLE OF CONTENTS O'
v Page Section Title
SUMMARY
.. .. ... . . . . . . . . . . . . . . . . . . . S-1 1 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.2 SCOPE . . . .. . . . . . . . . . . . . . . . . . . . . 1-1 1.3 SHOREHAM POSITION . . . . . . . . . . . . . . . . . . . 1-3 2 DEFINITION OF SAFETY-RELATED ELECTRICAL EQUIPMENT . . . . 2-1 2.1 METHODOLOGY .. . . . . . . . . . . . . . . . . . . . . 2-1 2.2 SPECIFICATIONS WITH EQUIPMENT REQUIRING . . . . . . . . e-2 ENVIRONMENTAL QUALIFICATION 2.3 MISCELLANEOUS COMPONENTS AND ACCESSORIES . . . . . . . 2-4 2.4 SYSTEMS REVIEWED . . . . . . . . . . . . . . . . . . . 2-5 2-6 2.5 EQUIPMENT SAFETY FUNCTIONS . . . . . . . . . . . . . .
3 ENVIRONMENT APPLICABLE UNDER ACCIDENT CONDITIONS . . . . 3-1 3.1 METHODOLOGY ... . . . . . . . . . . . . . . . . . . . 3-1 3.2 ENVIRONMENTAL ZONE MAPS . . . . . . . . . . . . . . . . 3-1
. . . . . . . . . . . . . . . . . . . 3-2 3.3 SERVICE CONDTIONS 3-2 3.3.1 Normal Service Conditions . . . . . . . . . . . . . .
3-2 3.3.2 Postulated Accident conditions . . . . . . . . . . .
3-2
(* 3.3.2.1 Loss of Coolant Accident . . . . . . . . . . . . .
3.3.2.2 P1pe Break Outside Containment . . . . . . . . . . 3-3 3-4 3.3.2.3 Radiation . . . . . . . . . . . . . . . . . . . . .
3.3.2.4 Sprays . . . . . . . . . . . . . . . . . . . . . . 3-4 3.3.2.5 Flooding . . . . . . . . . . . . . . . . . . . . . 3-5
. . . . . . . . . 3-5 3.4 METHODOLOGY FOR AGING CONSIDERATIONS 3.4.1 Introduction . . . . . . . . . . . . . . . . . . . . 3-S 3-5 3.4.2 Radiation . . . . . . . . . . . . . . . . . . . . . .
3-5 3.4.3 Cycle Aging . . . . . . . . . . . . . . . . . . . . .
3-6 3.4.4 Thermal Aging . . . . . . . . . . . . . . . . . . . .
3-6 3.4.5 Arrhenius Methodology . . . . . . . . . . . . . . . .
3-7 3.4.6 100C Rule Methodology . . . . . . . . . . . . . . . .
3-8 3.5 MARGINS . . . . . . . . . . . . . . . . . . . . . . . .
4-1 4 DETERMINATION OF QUALIFICATION STATUS . . . . . . . . . .
4.1 EQUIPMENT STATUS . . . . . . . . . . . . . . . . . . . 4 -1 4-1 4.2 METHODOLOGY FOR EQUIPMENT QUALIFICATION . . . . . . . . 4-3 4.3 ENVIRONMENTAL QUALIFICATION DOCUMENTS . . . . . . . . . 4-3 l
4.4 EQUIPMENT QUALIFICATION ACCEPTANCE LRITERIA 4-4 l 4.5 EQUIPMENT LIST UPDATE . . . . . . . . . . . . . . . . . 4-4 4.6 ENVIRONMENTAL QUALIFICATION STATUS REPORT . . . . . . .
5 SURVEILLANCE AND MAINTENANCE . . . . . . . . . . . . . . 5-1 6 REFERENCBS . . . . . . . . . . . . . . . . . . . . . . . b-1 1
TABLE OF CONTENTS (Cont)
O Section Title APPENDIX A ENVIRONMENTAL QUALIFICATION REPORT EVALUATION FORM APPENDIX B ENVIRONMENTAL QUALIFICATION
SUMMARY
SHEETS APPENDIX C ENVIRONMENTAL ZONE MAPS APPENDIX D RADIATION, TEMPERATURE, AND PRESSURE DATA APPENDIX E dNVIRONMENTAL PROFILE CALCULATIONS
! APPENDIX F ENVIRONMENTAL QUALIFICATION STATUS REPORT APPENDIX G EQUIPMENT WITH INCOMPLETE QUALIFICATION DOCUMENTATION APPENDIX H LIST OF ABBREVIATIONS FOR EQUIPMENT TYPE O
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SUMMARY
This report is produced for NRC review of environmental g2allrication of safety-related electrical equipment at the Shoreham Nuclear Power Station - Unit 1.
Section 1 discusses the purpose and scope of the program, and the Shorenam position on environmental qualitication.
Section 2 defines the methodology for determining the safety-related electrical equipment requiring qualification for a harsh environment. The systems and safety functions reviewed to maxe this determination are also given.
Section 3 presents the environment considered as applicable under accident conditions. Because specific areas of the plant will be subject to different environmental conditions during an accident, the plant has been divided into " zones" as shown in Appendix C.
The bases for the determination of particular environmental conditions are also given. The environment calculated for each zone is given in Appendix D. Appendix E contains the description of calculations which provide the bases for the selection of appropriate environmental conditions.
Section 4 discusses the methodology used for determining the qualitication status of equipment. The equipment is listed in Appendix F, the Environmental Qualification Status Report (EQSR) ,
O with the qualification status of each piece of equipment and data which provide the requirements f or that qualification. Equipment trom the EQSR for which qualification documentation is considered deficient is listed in Appendix G. Appendix G also presents additional information and/or proposed resolution for the deticiencies in qualitication documentation. Appendix H provides a list of the abbreviations used in the EQSR and in Appendix G.
Section 5 describes qualification aspects or the surveillance and preventive maintenance program for the station.
Based on the information contained herein, this report provides the assurance that the Shoreham Nuclear Power Station -
Unit 1 can be brought to safe shutdown following a LOCA, HELB, or MELB without harm to the environment or public health and safety.
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SECTION 1 INTRODUCTION I
1.1 PURPOSE l Tne purpose of the Environmental Qualitication (EQ) Program for one shoreham Nuclear Power Station is to provide assurance that all electrical equipment (saf ety-related Class la equipment and equipment required by Regulatory Guide 1.97) located in potential harsh environments maintain functional operability wnen required to mitigate the consequences of a postulated accident or to bring the plant to a cold shutdown condition afterwards. This assurance is provided by comparing environmental Antormation contained in electrical equipment qualification documents against the postulated environment to which the equipment may be subjected. This review results in one of the following:
- a. documentation ot environmental qualitication ot equipment to demonstrate that requirements are adequately met, or
- b. upgrading of qualification or requalification ot equipment which does not meet minimum requirements, or
- c. modification of design to meet the applicable
( requirements, or V) replacement of any equipment which lacks sufficient d.
evidence of qualitication with qual 2 fied equipmen.t.
1.2 SCOPB The equipment identitled for environmental qualification include:
- a. satety-related Class 1E Electrical Equipment (herearter ref erreo to as equipment) located in potentially narsh environments, and required to operate during or arter such an environment, D. sensing devices locateo in potentially harsh environments for display instruments which monitor the condition or the plant during and atter postulated accidents as required by hegulatory Guide 1.97, (tnese are designated with "RG" in the rightmost column of the Equipment Qualification Status Report (EQSR) in Appendix F) , and
- c. Three Mile Island ('lMI) Lessons Learneo modifications to safety-related systems including control and monitoring devices located in potentially harsh environments.
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r Environmental conditions to which the above equipment may be subjected consist of the following:
- a. pressure
- b. temperature
- c. relative humidity
- d. radiation
- e. 11ooding/ submergence
- f. fluid spray Equipment qualification documents are reviewed with respect to the following:
- a. service Conditions to which equipment is subjected,
- c. operating time, or the time during which the equipment is required to perform a function so as to mitigate the consequences of the design basis event, and qualification methodology based on the Operating Codes
[\J d.
defined in Appendix E of NUREG-0588 .
- e. aging considerations
- f. margins The review is accumented on the Environmental Qua1111 cation Report Evaluation Form (EQREF) , the Environmental Qualification Summary Sheet (EQSS) , and tabulated in the computerized Environmental Qualification Status Report (EQSR) .
Equipment successfully tested for an environmental prot 11e whicn meets or exceeds postulated service conditions satisties the qualitication conditions and the qualification report is approved.
It a qualification report does not provide sufficient eviaence of qualitication, then alternative qualitication methods are evaluated, including:
- a. obtain additional qualitication documentation,
- b. perform additional environmental testing or analysis,
- c. modity the equipment aesign or material selection, U(s 1-2
- d. turther analyze the equipment's environment and/or its
/7 function to refine the adverse service conditions that (s ,/ pertain to the actual location and use or the component,
- e. provide enclosure or shielding,
- t. relocate in a less severe environmental zone,
- g. include considerations of potential equipment "
degradation in the plant preventive maintenance program to provide a basis for extension of equipment qualitled -
life,
- h. establish a limited quallfled lite and a schedule for ,
future replacement, or ,
- 1. select better qualitied equipment as replacement.
Qualification programs for specific equipment, such as cables, ,
valves, motors, and electrical penetrations, that are designed to ,'
conform with the requirements of daughter standards or IEEE-323, ~,
are acceptable for demonstrating compliance with the objectives -
of IEEE Std. 323. The daughter standards include IEEE Std. 383 - -
tor cables, IEEE Std. 382 for motor operated valves, IEEE Std. 334 tor electric motors, and IEEE Std. 317 for electrical penetrations.
Dynamic quallilcation of equipment is performed in accordance
with the requirements or IEEE Std. 344 and is addressed in separate documentation. ,
LILCO maintains primary responsibility for the Environmental Qualification Program for the Shoreham Nuclear Power Station.
LILCO is also responsible for the performance of those organizations who have been assigned specific tasRs, and imposes.
upon them the requirements ot the LILCO Quality Assurance i Pr ogram. The review of balance of Plant (BOP) equipment has Deen l
dssigned to the Stone & Webster Engineering Corp. (SWEC) and the review or Nuclear Steam Supply System (NSSS) equipment to EDS s ts l Nuclear Inc. Both these organizations have acceptable Quality .
Assurance Programs which meet the requirements ot 10CFR50 Appendix B, and implementation of the respective programs specitic to the assigned tasks is monitored by LILCO.
l 1.3 SHOREHAM POSITION Snoreham Nuclear Power Station Class 1E electrical equipment are qualitied as follows:
I
- a. Equipment purchased through May 23, 1980 is evaluated and considered environmentally quallfled it it satisries
! IEEE Standard 323-1971 and NUREG-0568 Category,II , .
positions as a minimum.
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- b. Equipment purchased af ter May 23, 1980 la evaluated and accepted to IEEE Standard 323-1974 and NOREG-0588 Os Category I positions, where possible. It such equipment is not available and cannot be made available, equipment is evaluated and considered environmentally qua11 tied if it satisfies IEEE Standard 323-1971 and NUREG-0588, Category II positions as a minimum.
In some cases, the DOR Guidelines may be used to clarify the requirements ot IEEE Standard 323 and NUREG-0588.
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SECTION 2 DEFINITION OF SAFETY-RELATED ELECTRICAL EQUIPMENT 2.1 METHODOIDGY The identification of equipment for environmental qualification requires the examination of the applicable project documents.
These documents include flow diagrams, electrical one-line diagrams, logic diagrams, elementary diagrams, and instrument loop diagrams. Examination of these documents entails the following:
- a. Review of electrical one-line diagrams to identify electrical equipment which distributes safety-related power to satety-related electrical systems.
D. Review of system flow diagrams, related system descriptions, and FSAR system function sections (including Chapter 15 -
accident analysis and Appendix 3C pipe failure outside primary containment) to identify the electrical equipment within each system, analyze and tabulate emergency events for each equipment item and the corresponding safety function required to mitigate the emergency event,derine operating codes as referenced in Appendix E of NUREG-0588, and determine O tne amount of time required for perrormance of the operability requirement.
- c. Review of elementary and loop diagrams for each Class 1E electrical equipment item on marked-up flow diagrams to identity miscellaneous safety-related equipment required to control or monitor the equipment.
Equipment identified in this manner is listed on the Environmental Qualitication Status Report (EQSR) , and is cross-referenced against the Project Equipment System (PES) computer listing to confirm the identification and location of the equipment, and to aid in the location of applicable procurement documents.
To provide additional assurance that all requirec electrical equipment is identified, the plant Emergency Operating Procedures will be reviewed against the computerized report (EQSR).
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2.2 SPECIFICATIONS WITH EQUIPMENT REQUIRING ENVIRONMENTAL QUALIFICATION Osing the procedure outlined in Section 2.1 and discussed in detail in the following sections, a list of BOP safety-related Class IE electrical equipment located in a potentially harsh evironment has been developed. The specifications listed below are applicable to this equipment.
SPECIFICATIONS FOR SAFETY-RELATED ELECTRICAL EQUIPMENT LOCATED IN A HARSH ENVIRONMENT Specification Number Title Sill-39 4,160 V Metal Clad Switchgear Sill-62G Centrifugal Pumps Sill-ti8AD Carbon Steel MOVs Sill-88V Carbon Steel MOVs SH1-102 Centrifugal Fans
Sill- 105 Charcoal Filter Trains Sill-111 Ventilation Buttertly Valves Sill-115 480 V Motor Control Centers S111-124 Miscellaneous AC and DC Distribution Panelboards S111-127 5 KV Power Cable SH1-128 BOO V Power Cable Sill-129 300 V and 600 V Fire-Resistant Control and Instrument Cable SH1-130 Instrument Cable Sill- 131 Thermocouple Extension Wire SH1-134 Reactor Containment Electrical Penetrations
! Sill- 159 Electrical Work h
a 2-2
Specification Number Title SH1-168 DC Motor Control Centers SH1-172 Prinary Containment Isolation Valves SH 1-175 Drywell Floor Relief Valves SH1-197 Motor Operated Butterfly Valves SH1-203 Manually Operated Diaphragm Valves -
Carbon Steel SH 1-214 Manually Operated Stainless Steel Valves SH1-232 Special Check Valves SH1-235 Loop Level Pumps SH1-248 Miscellaneous Transformers SH1-253 Motor Operated Steel Valves
() SH1-270 SH1-276 Axial Flow Fans Unit Coolers SH1-281 Bronze Valves SH1-289 Hydrogen Recombiner Units SH1-310 Electric Motor Operated Controls Valves SH1-318 Air Operated Control Valves SH1-319 Automatic Temperature Control Systems for HVAC SH1-332 Radiation Monitors SH1-344 Primary Containment Gas Analyzers SH1-348 Pressure and Temperature Switches SH1-406 Electronic Transmitters and RTDs i SH1-40bA RTDs lO 1
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Specification Number Title
%)
SH1-407 Level Switches SH1-423 Air Operated Butterfly Valves ASME III SH1-438 Automatic Transf er Switches SH1-439 480 V Motor Generator Set SH1-455 Low Capacitance Fire-Resistant Instrument Cable SH1-456 Reactor Containment Electrical Penetrations SH1-457 Leakage Return Pump SH1-473 Level Transmitters SH1-475 Post Accident Radiation Monitoring SH1-484 Control & Instrument Cable
[ SH1-485 Thermocouple Extension Wire 15.54 Valcor Solenoid Valves The equipment items within the NSSS scope of supply are included under Specification SE1-003.
2.3 MISCELLANEOUS COMPONENTS AND ACCESSORIES Tne environmental qualification or miscellaneous electrical components and accessories is addressed in the same manner as the equipment which is identified from the review of project drawings. Examples of miscellaneous components include control stations, terminal lugs, splicing materials, and internal panel wire. These components are not identified witn a specitic equipment identification number but, instead, are documented on a separate list attached to the Environmental Qualitication Status Report (EQSR) in Appendix F. Most or the miscellaneous electrical components and accessories have been procured under Specification SH1-159.
2-4
2.4 SYSTEMS REVIEWED
() The systems reviewed to identify the equipment requiring environmental qualification are presented below. In parentheses alongside the systems are alternate names to describe the system or portions thereof.
SYSTEM SYSTEM CODE Nuclear Boiler (Includes Some Safeguards Activation) 1B21 Reactor Water Recirculation (Reactor Coolant) 1B31 Control Rod Drive Hydraulic Control 1C11 Stannby Liquid Control 1C41 Neutron Monitoring 1C51 Reactor Plant Remote Shutdown 1C61 Reactor Protection 1C71 Process Radiation Monitoring 1D11 Area Radiation Monitoring 1D21 Residual Heat Removal (Includes Containment Spray) 1E11 Core Spray 1E21 MSIV Leakage Control 1E32 High Pressure Coolant Injection 1E41 Reactor Core Isolation Cooling 1E51 Radwaste 1G 11 Reactor Water Cleanup 1G33 Puel Pool Cooling and Cleanup 1G41 Main Control Room Panels 1H11 Local Panels and Racks 1H21 f~d')
s RBSVS & Control Room Chilled Water 1M50 Main Steam 1N11 Condensate and Feedwater 1N21 Miscellaneous Drains 1N23 Condensate Transfer and Storage 1P11 Demineralized & Makeup Water 1P21 Sample 1P33 Service Water 1P41 Reactor building Closed Loop Cooling Water 1P42 Compressed Air 1P50 Metal Clad Switchgear 1R22 Unit Substations 1R23 Motor Control Centers 1R24 Power Cable & Wire 1R31 Control Canle & Wire 1R32 AC Control and Instrument Power 1R35 AC Uninterruptible Power 1R36 DC Instrument Power 1R41 Battery Power (125V D-C) 1R42 Diesel Emergency Power 1R43 Reactor Building Superstructure 1T22 Reactor Primary Containment 1T23 Primary Containment Inerting 1T24 Reactor Building Ventilation 1T41
(~N Reactor Building Standby Ventilation (StandDy 1T46 2-5
Gas Treatment) ps Primary Containment Cooling 1T47 Primary Containment Atmospheric Control (Combustible 1T48 l] Gas Control)
Miscellaneous HVAC 1X41 Diesel Generator Ventilation 1X60 Control Room HVAC 1X61 Excess Flow Check Valves 1Z92 Post Accident Monitoring 1Z93 Post Accident Sampling 1Z96 (Energency Condenser not applicable to Shorenam) 2.5 EQUIPMENT SAFETY FUNCTIONS Safety-related electrical equipment in this qualification program perform safety functions required to mitigate the. consequences of a Loss of Coolant Accident (LOCA) , a High Energy Line Break (HELB) , or a Moderate Energy Line Crack (MhLB). The equipment also performs safety f unctions required to maintain the reactor in a safe shutdown condition. Safety functions and tnelr anoreviations are listed below.
SAFETY FUNCTIONS SAFETY FUNCTION ABBREVIATION Automatic Depressurization ATDP
/~N Component Auxiliary Cooling CAUC
(_s) Containment Isolation CISL Core Spray CSPR Emergency Power EMPO Feedwater Isolation FISL Fuel Pool Cooling FLCL Post Accident Hydrogen Control HCNT HELB Mitigation HELB High Pressure Coolant Injection HPCI Residual Heat Removal HTRM Safety-Related HVAC HVAC Leakage Control LCNT Low Pressure Coolant Injection LHSI MELB Mitigation MELb Post Accident Monitoring PACM Reactivity Control RCCL Raactor Core Isolation Cooling RCIC Regulatory Guide 1.97 Criteria REGG Reactor Trip Protection RTRP Engineered Safety Function SAFE Main Steam Isolation SISL Suppression Pool Pump Back SPPB Service Water SWAT Ultimate Cooling ULCL O
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To determine which equipment is saf ety-related, it is useful to s assign specific saf ety functions to the systems. This is done
! most easily by regrouping, under larger system headings, the systems listed in Section 2.4.
Safety functions for applicable systems are listed below:
SYSTEM SAFETY FUNCTIONS SYSTEM SAFETY FUNCTIONS Main & Auxiliary Steam Nuclear CISL, SISL, HTRM, ATDP, Boller (1821) LHSI, CSPR, HELB, MELB, SAFE, LCNT, REGG Feedwater (1B21, 1N21) LCNT, CISL, FISL, HPCI, RCIC Reactor Building Sampling CISL, LCNT (1b31, 1P33)
Reactor Water Recirculation S AFE, HTRM, LHSI (1831)
Radiation Monitoring PACM, REGG, LCNT, RTRP, (1D11) SAFE, CISL Control Rod Drive (1C11) RTRP, LCNT, REGG Standby Liquid Control (1C41) RCCL, CISL, REGG Neutron Monitoring (1C51, 1C61) CISL, REGG Residual Heat Removal LHSI, HTRM, CISL, SAFE, (1E11) LCNT, ATDP, REGG, HCNT Core Spray (1E21) CSPR, CISL, LCNT, SAFE, ATDP, REGG Main Steam Isolation CISL, SISL, LCNT Valve Leakage Control (1E32)
Reactor Core Isolation RCIC, REGG, LCNT, CI5L, Cooling (1E51) HELB, MELb Reactor Building Vents CISL, LCNT, SPPB, HELB, and Drains (1G11) REGG Reactor Water Cleanup CISL, HELB, LCNT (1G33)
Fuel Pool Cooling and CISL, FLCL, ULCL, REGG
~$g Cleanup (1G41)
(O 2 -7
SYSTEM SAFETY FUNCTIOt'S O Local Panels and Racks (1H21) SAFE Main Steam-Turbine Side LCNT, SISL, SAFE of Main Steam Isolation Valves (1N11, 1b21, 1C71)
Secondary Plant Drains LCNT, SISL (1N23)
Metal Clad Switchgear (1R22) EMPO, SAFE Motor Control Centers EMPO, SAFE (1R24)
Power Cable and Wire (1R31) EMPO, SAFE Control Cable and Wire (1R32) EMPO, SAFE AC Control and Instrument Power (1R35) EMPO, SAFE, REGG 125 V DC Battery EMPO, SAFE Power (1R42)
[~') Fuel Oil Transfer (1R43) EMPO, SAFE V
High Pressure Coolant REGG, HPCI, HELB, CISL, Injection (1E41, 1Z93) LCNT Drywell Floor Seal CISL Pressure Monitoring (1T23)
Demineralized and Make- HPCI, SAFE Up Water (1P11, 1P21)
Service Water (1P41) SWAT, PACM, HTRM, FLCL, SAFE Reactor Building Closed CISL, CAUC Loop Cooling Water (1P42)
Instrument and Service CISL, SAFE Air (1P50)
Reactor Primary Containment CISL, SAFE, EMPO (1T23)
Reactor Building Normal S RBSVS SAFE, CISL, HVAC Ventilation (IT41, 1T46, 1T47)
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SYSTEM SAFETY FUNCTIONS O Primary Containment CISL, SAFE, HCNT, REGG Atmospheric Control and Inerting (1T48, 1T24)
The system safety tunctions for equipment items identified are documented in the SSW Engineering Files and will be provided in a report to LILCO.
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SECTION 3 ENVIRONMENT APPLICABLE UNDER ACCIDENT CONDITIONS 3.1 METHODOLOGY In order to determine what safety-related electrical equipment is located in a harsh environment, it is necessary to establish the environmental conditions experienced in the areas of the plant in which the equipment is located.
Environmental profiles are determined for detined spatial zones noth inside and outside the primary containment. Radiation source terms are developed in accordance with the requirements of NUREG-0737. Temperature, pressure, and humidity data are based upon applicable sections of the FSAR including Appendix 3C (Pipe Failure Outside Primary Containment) . The rollowing environmental parameters are included in the analyses of equipment environmental qualification:
- a. Normal Environment
- 1. Radiation - 40 year integrated dose
- 2. Temperature - expected range
- 3. Humidity - expected range
- 4. Pressure - expected range
- b. Postulated Accident Environment
- 1. Radiation - radiation dose received from the accident environmenc for the time period of interest.
- 2. Temperature - temperature expressed as a function of time for the duration of the accident transient.
- 3. Humidity - highest relative humidity levels during the accident transient, conservatively assumed at 100 percent for both the primary and secondary containments of the Reactor Building.
- 4. Pressure - maximum levels postulated for the accident transient.
3.2 ENVIRONMENTAL ZONE MAPS Environmental zone maps illustrating the harsh environmental spatial zones are shown in Appendix C. The harsh environmental s
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4 service conditions experienced by each zone are given in
-Appendix D.
v 3.3 SERVICE CONDITIONS The environmental parameters f or each zone are determined for the normal and postulated accident service conditions. These parameters are the specific qualification requirements for the equipment to ne qualified. The normal and accident profiles (temperature, pressure, and radiation) for each zone are illustrated as a function of time in Appendix D.
3.3.1 Normal Service Conditions Normal service conditions are the environmental conditions in each zone which are maintained during normal plant op erations .
This includes all levels of power generation, start-up, hot standby, shutdown, and refueling. For equipment qualification, normal service conditions are assumed continuous over the 40 year life of the plant. Pressure, temperature, and humidity values are cased on normally operating HVAC systems and are shown on Table 3-1. Radiation values are based on normal radionucifde invento ry and are cumulative during the 40 year plant lite.
3.3.2 Postulated Accident Conditions Accident conditions generate the most severe environmental
- Os parameters for the environmental qualification of equipment.
Values of temperatura, pressure, humidity, and radiation are postulated to occur ac the end of the 40 year plant lite.
Specific environmental parameters are determined ny investigating the postulated accident conditions discussed celow:
3.3.2.1 Loss of Coolant Accident j a. The method of analysis for pressure and temperature i
response for Loss of Coolant Accident (LOCA) within the primary containment is described in Section 6.2 of the FSAR.
- b. The pressure and temperature for the secondary containment are defined in Appendix D as taken trom Section 6.2.3 of the FSAR. The pressure transient in the secondary containment due to a LOCA is also snown in Figure D-43 as taken trom FSAR Figure 6.2.3-2.
- c. The Turbine and Control Buildings do not experience extremes of temperature and/or pressure due to LOCA within the Reactor Building.
3 -2
3.3.2.2 Pipe Break Outside Containment
- a. Short-Term Response to High Energy Line Breaks (HELB)
High energy line breaks have been selected and analyzed in accordance with the specific criteria outlined in Appendix 3C of the FSAR. Achieving cold shutdown during a HELB event is discussed in FSAR Appendix 3C together with the required systems and postulated conditions.
The analysis described in Appendix E, Section E.2 provides further detail of particular HELBs and their effect upon additional areas of the plant through the use of more retined temperature zones.
- b. Snort-term Response to Moderate Energy Line Cracks (MELB)
The following moderate energy line failure is considered and represents the limiting design condition for temperature effects due to MELBs: Twenty-four inch RHR pipe crack in the Reactor Building, elevation 40 ft.
Calculations are described in Appendix E, Section E.3.
This failure and other MELBs are listed in Appendix 3C ot the FSAR and are analyzed with the applicable criteria of that section.
- c. Long-Term Response
\-- The long-term response analysis for all breaks is a determination of the elapsed time from the moment the break occurs to the time the building environment returns to the initial starting temperature (generally 104 *F) .
The Reactor Building secondary containment is considered one volume.
Tne amount of energy in BTU's discharged into the I secondary containment by the break is determined based j on a reference of 104*F.
Heat is removed f rom the building by one of two trains of RBSVS coolers and by air exchange with the atmosphere.
The elapsed time is calculated by dividing the total I energy disenarged by the sum of the RBSVS cooler and atmospheric air exchange heat removal rates.
I No credit is taken for heat sinks and the entire secondary containment is assumed to cool down uniformly.
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- d. Summary of Conservatisms Used in the Analyses
- 1. Frictionless flow is assumed for blowdowns.
- 2. No credit is taken for air coolers during the short-term analyses of Section a.
- 3. No automatic closure signals for isolation valves occur until the entire zone rises to the setpoint temperature.
- 4. Metal heat sinks are neglected.
- 5. The Reactor Building remains isolated to mass and energy transfer out of the building until the sheet metal roof panels relieve during the short-term analyses.
- 6. No credit is taken for radwaste sump pumps.
- 7. No credit is taken for passive heat sinxs in the long-term analyses.
3.3.2.3 Radiation The accident radiation cources and integraten radiation doses are derived as discussed in Appendix E, Section E.4 in accordance
(~^)
(_s with NUREG 0737,Section II. B.2.
3.3.2.4 Sprays The only equipment subject to spray is that equipment within the primary containment during the post accident containment cooling mode of RHR (reter to FSAR Section 6.2) . The design of this system causes a uniform mist within the containment, which is bounded by the 100 percent humidity /saturaten steam conditions specified for the qualification of equipment. Refer to Appendix 3C ot the FSAR for the detailed analysis of HELB and MELB tluid effects outside the primary containment.
An analysis was performed to evaluate the effects of containnent spray due to the drywell and wetwell spray nozzles. The impinging effect is assumed to be considerable only when the spray droplet velocity has a horizontal component. This is a conservative assumption because the horizontal component of the velocity in some areas can be larger than the terminal velocity of the droplets. The area outside the spray impingement zone is assumed to be equivalent to 100 percent humicity due to the small size of the droplets and gravity as the only driving force.
Based on these assumptions, qualification of equipment in the following areas requires consideration of the spray impingement effect:
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Drywell: An annular volume from 10' above to 10' 11" below
'N elevation 109* 9" (elevation 98' to 120*) and radially 33' l outward from the location of nozzles on elevation 109' 9".
hetwell: An annular volume from elevation 41' to 54' (2* 1" above and 10 *2" below elevation 5189") and radially 17'2" outward from the location of nozzles on elevation 5189".
3.3.2.5 Flooding Equipment required for accident mitigation is not subject to submergence in the Shoreham design. A detailed evaluation or possible flooding eff ects outside the primary containment due to HELBs and MELBs is presented in Appendix 3C of the FSAR.
3.4 METHODOIDGY FOR AGING CONSIDERATIONS 3.4.1 Introduction The intent of aging in the qualification process is to bring the tested equipment to the equivalent of its "end of life" condition prior to subjecting it to the conditions of the Design Basis Event (DBE). The time period corresponding to this "end of lite" condition becomes the " qualified life" of the tested equipment when the equipment demonstrates operability when subjected to its required service conditions.
() The aging mechanisms that equipment are exposed qualified lite are: radiation, cycling, and heat.
to during 3.4.2 Radiation The determination of qualified life includes assurance that the equipment was radiation aged to an amount equivalent to its 40 year plus accident integrated radiation dose. The preferrea method f or this type of qualification is type-testing. However, in some cases, type-testing was insufficient to quality the device for its required radiation dose. In these cases, an analysis of the materials used in the tested equipment has been performed to determine the sensitivity of these materials (based on previous testing experience) to its applicable radiation environment. The radiation tolerence of the most sensitive material was assumed to be the radiation tolerance or the entire tested equipment.
3.4.3 Cycle Aging For devices which have moving parts or t unction in some repeatable manner, the devices are cycle aged for the number or postulated operations that can De expected during the installed lite. In the qualification test process, cycle aging is typically pertormed prior to initiation of the thermal and design basis accident tests.
J 3 -5
3.4.4 Thermal Aging Thermal aging is the deterioration of equipment components when subjected to elevated temperatures over a period of time. During qualification testing, this process is intended to produce the actual installed end-of-lite condition of the equipment prior to application of tne accident environment. In the case of thermal aging, analysis may be used to augment actual type testing.
One of the methods used in consideration of thermal aging is the determination that the materials in the equipment are not sensitive to thermal degradation. This determination may include either recognizing that the materials are metallic or utilizing tne Arrhenius parameters for each material to determine an
" expected life." Expected life can be defined as the amount of time a material can be expected to retain a certain property in a purely thermal environment without the imposition of other aging mechanisms. When this time is much greater than the 40 yr plant lite, it can be concluded that thermal degrada tion is insignificant in relation to other harsh envirnomental ef fects and the DBE, and thus the component may be exempted from the artificial thermal pre-aging.
When the expected life does not greatly exceed the 40 year plant life, accelerated thermal aging may be included in the qualification test program. Arrhenius parameters are utilized to determine the time and temperature of the accelerated aging O. required to bring the equipment to an equivalent age of 40 years at normal service temperatures . When the accelerated aging parameters are less than those required for a 40 year equivalent, d determination iS made of the actual equivalent. This equivalent age is the " qualified lite" of the equipment, it it successfully completes other applicable aging tests and tne accident sbnulation.
3.4.5 Arrhenius Methodology l Section 4.4 of NUREG 0588 and Paragrapn 5.2.4 of the DOR guidelines defines Arrhenius techniques as an acceptable method for aging determinations. This methodology allows the relative thermal life or nonmetallic materials to be determined by the extrapolation of an Arrhenius plot of the natural log or life as a function of reciprocal absolute temperature tor that particular material.
For many nonmetallic materials, it is known that the degradation process can De defined by a single temperature-dependent reaction that tollows the Arrhenius equation:
K = A exp (-(E a/N B T)) (4 where:
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k = reaction rate A = frequency factor exp = exponent to base e Ea = activation energy kB = Boltzmann e s Constant T = absolute temperature It is further noted, that for many reactions, the activation energy can be considered to be constant over the applicable temperature range. That is, that a single aging mechanism or reaction, is controlling the rate of thermal degradation.
Equation (1) can be transformed into a form which yields a time compression factor.
The equation is:
ts/t, = exp ((E /kB !1 ~ ! 8I II where:
t = accelerated aging time at temperature T tr = normal service time at temperature Te exp = exponent to base e E
a
activation energy (eV) kB
Boltzmann's Constant (8.617 x 10-5 eV/*K)
T = accelerated aging temperature (*K)
Te = normal service temperature (9K)
It is this equation which is used to provide a quallfled life ot devices at T, (normal service temperatures) when the activation energy of the most temperature sensitive material in the device can be determined by material textbook references or actual type testing.
3.4.6 100C Rule Methodology l The qualitied life for certain equipment was determined by the 10*C rule, rather than Arrhenius techniques. The 100C rule (each 10*C rise shortens life by one-half) was the state or the art for aging prior to the development of Arrhenius techniques. Where the 10*C rule was used as the qualitication basis, the results 3 -7
are verified by obtaining activation energies tram published data and calculating service life via the Arrhenius method as
( discussed above or by demonstrating that application or tne 100C rule yields a more conservative qualified life than the Arrhenius methodology for the equipment involved.
3.5 MARGINS The analyses used to determine environmental parameters f or normal and accident service conditions include various conservative assumptions as described previously. Therefore, the postulated values of pressure, temperature, humidity, and radiation for each environmental zone are in excess of the values that would be realistically expected for the conditions analyzed.
Equipment which is required to operate must be qualitied to an environmental profile which envelopes the postulated protile and results in a supplemental margin. In addition, equipment is qualified for time periods in excess of that required to provide the equipment's safety function. The operability time requirement listed in the EQSR includes a margin ot at least one hour or 10 percent, whichever is greater, in excess of the time duration required by the accident analyses.
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s SECTION 4
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V DETERMINATION OF QUALIFICATION STATHS 4.1 EQUIPMENT STATUS The qualification status of saf ety-related electrical equipment located in harsh environments is listed in the attached computer listing (EQ Status Report) in Appendix F. Appendix G addresses the equipment with deficient qualification documentation, along with resolution plans and, if needed, justitication for interim operation.
4.2 METHODOLOGY FOR EQUIPMENP QUALIFICATION The environmental qualification documents for the equipment are typically obtained for engineering evaluation from equipment vendors, equipment manufacturers and/or testing racilities.
These documents in the form of qualification procedures, reports, and supplementary information are evaluated in accordance with NUREG-0588, IEEE Std. 323, and the associated daugnter standards included in Section 6. Review of these documents includes assurance that they are technically adequate and contorm to the environmental qualification requirements of the applicable emergency conditions, operability times, and service conditions.
) Each equipment item is assigned an operability code in accordance with the categories discussed in Appendix E of NUREG-0588, and the qualification entails the following:
- a. Equipment assigned an operability code "A" must have acceptable documentation which demonstrates that the equipment performs its required satety function (s) in the environment dictated by the zone in which the equipment is located.
- b. Equipment assigned an operability code "B" does not nave an active safety runction. Essentially, "B" coaed equipment is the equipment identified as connected to Category 1E power systems but not required to operate during the postulated accident condition. Therefore, this equipment is evaluated to ensure that the accident exposure does not result in any equipment tallure which would alter the state of the 1E power system.
- c. Equipment assigned an operability code "C" does not have a safety tunction and does not fail in any manner that would affect the safe shutdown of the plant. Tnis equipment is not included in this report unless determined to be operability code "A" or "b" for a time
. less than the 180 day post accident duration and v
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, operability code "C" for the remaining duration of the accident.
f%]T When this equipment operability code is determined, the length of time (operability time) into an accident during which the equipment must function or must not fail is also ascertained.
The designation of this operability time is based on:
- a. The system operating requirements for accident mitigation.
- b. The tunction of each r equir ed equipment item in tne system during and af ter accident mitigation.
All equipment is designated to be qualified for a maximum of 180 day post-accident duration. Equipment identified as operability code "A" for less than 180 days is designated operability code "b" for the remainder of the accident auration.
However, if, at some time during the accident duration, it is determined that no postulated failure will be detrimental to the sate shutdown of the plant, an operability time of less than 180 days may be designated.
The methods of qualifying equipment are testing and analysis.
Testing is the principal method of qualification used in this program. The evaluation of equipment testing includes the s following considerations:
- a. Acceptance criteria are es tablished prior to the evaluation of test reports.
- b. The environmental profiles for the applicable accident conditions and zones are examined f or comparison to the environment Simulated in the test report.
, c. Continuous or discrete monitoring results are reviewed where relevant.
- d. Margins are verified for the environmental parameters.
- e. Documentation is reviewed to ensure that adequate information with respect to the equipment performing its required safety tunctions during the postulated service conditions is presented in a format that is ver111able in an independent audit.
For cases where test documentation is unavailable or incomplete, the services or reputable independent engineering testing laboratories or engineering consulting 11rms are contracted.
These testing facilities or engineering consultants are selected tased on their cognizance of the applicable standards and their
,_ experience in environmental equipment qualitication.
(J ; Qualification documentation may then be upgraded and reevaluated 4-2
based on additional test information, retesting, or analysis based on adequate data using acceptable engineering models.
4.3 ENVIRONMENTAL QUALIFICATION DOCUMENTS As each qualification document is reviewed and assessed, a " Test Report Number" is assigned. This test report identification is prefixed with the letters "TR " and suffixed with the digits of the equipment's procurement specification identification to tac 111 tate future information retrieval. These c1gits of the specification identification are also used to identity the other forms ot documentation used in the environmental qualification (EQ) review process. When one or more components or groups or components are addressed under one specification, additional digits are added to the identification code.
l The actual review of the equipment qualification reports is j documented on the Environmental Qualitication Report Evaluation Form (EQREF) , described more fully in Appendix A. This document identifies the equipment by system, vendor, manuracturer, and model number, while providing a review format that addresses the applicable zone service conditions as required per NUREG-0588.
Upon completion of the qualification document review, tinal comments are recorded on the EQREF including Justification for EQ acceptance, recommendations to rectify qualification document deficiencies, and limitations or conditions required in order to preserve qualification, as applicable.
The results of the EQREF review are summarized on the Environmental Qualification Summary Sheet (EQSS) , described in more detail in Appendix B. Information including equipment description, IEEE Standards referenced, test sequence, environmental zrnes, and test parameters as described in the qualitication r_ port (s) is entered on this document. The test parameters recorded on the EQSS are compared to the required zone parameters for adequacy. Any discre pancies are noted on the applicable EQREF. A separate EQSS is generated for each specification or group of devices. Documentation packages which include tne qualification reports, EQREF and EQSS are transmitted to LILCO and incorporated into the Shoreham permanent recora tile.
4.4 EQUIPMENT QUALIFICATION ACCEPTANCE CRITERIA Tne information collected on the EQSS and EQSR provides the EQ status of each Class 1E electrical equipment. The equipment is considered qualified if the following requirements are met:
- a. Acceptable documentation to all applicable referenced requirements.
- b. Environmental tests and/or analyses are pertormed and meet all applicable referenced requirements for the
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postulated conditions to which the equipment is Il subjected.
V
- c. Acceptable performance characteristics in an environment as severe as the postulated zone environment is demonstrated.
- d. A qualified life is determined and supported by qualification documents.
Equipment that does not satisfy the above criteria is not considered fully qualified and is addressed in Appendix G. The resolution of EQ deficiencies may include one or more of the alternatives listed in Section 1.1.
4.5 EQUIPMENT LIST UPDATE As additional environmental qualifica tion (EQ) reports and/or procedures are obtained, the appropriate EQ review and evaluation documents are revised to reflect changes in the qualification status of each piece of equipment. Evaluation or these documents is performed as previously described in this text. If changes in the qualification information occur, the appropriate EQSS is revised with a revision number to indicate the revision. Each revised EQSS supersedes, in entirety, all previous EQSSs with the same number. New data is entered into the master list (EQSR) to N indicate changes and additional qualification documentation is
, added to the Shoreham records file as the changes are implemented.
4.6 ENVIRONMENTAL QUALIFICATION STATUS Rt. PORT (EQSR)
The EQSR is a computerized report which summarizes the qualification status of each equipment item. The current issue of the EQSR is included in Appendix F.
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SECTION 5 T
j SURVEILLANCE AND MAINTENANCE The Shoreham surveillance and maintenance programs include documented program plans, procedures, and results to assure that tne safety-related equipment is maintained in a state ot readiness and operability so that it will pertorm its intended adfety function upon demand.
The results of the Equipment Qualification Program are directly input to the Shoreham maintenance and spare parts programs to ensure timely device or parts replacement as needed due to identitied qualified life limitations and to ensure timely performance of any other identified maintenance activities required to preserve the applicability of the qualification.
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SECTION 6 REFERENCES Year of Sponsor Organization, Abbreviation Issue _ Document Title IEEE 308 1971 Institute of Electrical l and Electronics Engineers, Standard Criteria for Class 1E
- Electric Systems for Nuclear 1
Power Generating Stations IEEE 317 1972 Institute of Electrical and Electronics Engineers, Electrical Penetration Assem-blies in Containment Struc-tures for Nuclear Power Generating Stations.
IEEE 323 1971, Institute of Electrical 1974 and Electronics Engineers, General Guide for Quality-ing Class I Electric lyuip-ment for Nuclear Power Generating Stations IEEE 334 1971 Institute of Electrical and Electronics Engineers, Trial-Use Guide for Type Tests of Continuous-duty Class I Motors Installed Inside the Containment of Nuclear Power Generating Stations IEEE 344 1971, Institute of Electrical 1975 and Electronics Engineers, Trial-Use Guide for Seis-mic Qualification of Electronic Equipment for Nuclear Power Generating Stations IEEE 382 1972 Institute of Electrical and Electronic Engineers, Trial-Use Guide for Type Test of Class I Electric Valve Operators for Nuclear Power Generating Stations t
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Year of Sponsor Organization, Abbreviation Issue Document Title IEEE 383 1974 Institute of Electrical and Electronic Engineers, Type Test of Class I Electric Cables, Field Splices, and Connections for Nuclear Power Generating Power Stations NUREG 0588 1979 Nuclear Regulatory Commission, Rev. 1 1981 Interim Staff Position on Environme: tal Qualification of Saf ety-Related Electrical Equipment NUREG 0737 1980 Nuclear Regulatory Commission, Clarification of Tnree Mile Island Action Plan Requirements i
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.. . . _ _ - _ . . . - _ . - _ . - - - . _ ~ . . . - - - - - - - - - - . - . . _ - _ . . - ..-. , - . . . -
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i i APPENDIX A !
' i l EINIRONMENTAL QUALIFICATION REPORT EVALUATION FORM 4
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APPENDIX A ENVIRONMENTAL QUALIFICATION REPORT EVALUATION FORM (EQREF)
This form (a blank copy of which is included after this description) provides a summary of EQ document assessment and consists of four (4) pages. Each EQREF is numbered by specification number preceded by the letters TR. The first page includes data entries entitled EQUIPMENT IDENTIFICATION and OUALIFICATION DOCUMENTATION which are self-explanatory. The entry for "SQRT form I.D.:" is not entered but the seismic qualifications for the equipment are filed separately. The assessment results (whether the EQ document is acceptable or not) are summarized under the REVIEWER *S CONCLUSION section where any exceptions, special conditions or correctable deficiencies are 4
entered.
On Page 2, data entries include TEST FACILITY - name and location of testing firm, and the APPLICABLE ZONE NUMBERS, for the environmental zones in which the tested equipment is installed.
The information that follows is a list of questions that pertain to the equipment. The response to these questions is either "YES", "NO", or "N/A" - not applicable. The technical content of these questions is intended to satisfy the requirements of IEEE Std 323-1971, 1974 and NUREG-0588, and addresses the tollowing:
() 1.
2.
Equipment identification Test Program Description and Procedure
- 3. Qualification and Performance of Tested Equ2pment.
4 Thermal Aging including mechanical wear and radiation exposure.
S. Post test inspection on the final page of this form, the appropriate COMMENTS and RECOMMENDATIONS on all aspects of the qualification reports are entered. Additional pages may be attached to record any additional comments required to summarize the evaluation process.
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J.O. No. 11600.02 Page 1 of 4 O ENVIRONMENTAL QUALIFICATION REPORT EVALUATION FORM FOR SHOREHAM NUCLEAR POWER STATION - UNIT 1 NRC NUREG-0588 Category I* and II Positions TR-(Please type or print)
EQUIPMENT IDENTIFICATION Equipment Types Vendor : ,
Specification No.:
Purchase (P.O. ) No. :
Manufacturer:
Model No.:
Gerial No.:
QUALIFICATION DOCUMEh"TATION
Title:
Author (Organization): _
Identification No.: _
Na Date:
SQRT Form I.D.:
REVIEWER'S CONCLUSION Acceptable? YES NO _.
If YES, any limitatior:, exceptions, special conditions:
If tiO', ~what specific deficiencies corld be corrected in order to achieve acceptability?
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REVIEWED BY:
O Signature Date VFRIFIED BY:
Signature Date
(*) Applicable to NUREG Categorf 1 positions only.
5/1/81
Page 2 of 4
(%
TEST FACILITY Names City:
State:
APPLICABLE ZONE ND 'BERS Rad. Zones:
Temp./ Pres. Zones:
- 1. TEST CONDITIONS See Environmental Qualification Summary Sheet No.:
- 2. Does the model number of the component (s) tested coincide YES NO with the model number of the component (s) being reviewed?
A. If not, is adequate justification provided showing that the component (s) tested adequately represent (s) YES NO N/A component (s) being reviewed?
- 3. Does the Test Program Outline include:
A. Test Objectives YES NO
}
B. Test Sample Description YES NO C. Number of units to be tested YES NO D. Mounting requirements YES NO N/A
- 1. If yes, is mounting justified? YES NO N/A
- 2. If no, has justification been provided showing that equipment performance is not altered by the YES NO N/A manner or position in which it is mounted?
E. Aging Simulation Procedure YES NO F. Parameters to be measured YES NO
- 1. Accuracy YES NO N/A
- 2. Response time YES NO N/A G. The range, sequence, and combination of environments YES E O to simulate DBA conditions?
H. Acceptance Criteria YES NO
- 1. Are the acceptance criterial adequate to verify the ability of the equipment to perform its YES NO N/A required safety function?
- 4. Are the tests methods in accordance with following:
A. Does the test demonstrate that the equipment satisfies YES NO the acceptance criteria?
B. Do the parameters in the qualification documentation YES NO at least meet accident requirements?
- 1. If not, are deviations justified? YES NO N/A
Page 3 of 4 C. Have adeqtate margins been allowed in accordance YES NO with NUREG-0588, Section 3 (Cat. I or II)?
(Circle appropriate Category)
D. If the qualification uses analysis, are the basis' supporting data, and method for analysis included?
YES NO N/A
- E. Is test sequence justified as per IEEE 323-1974 YES NO Section 6.3.2 and NUREG-0588 Category I position?
F. Is the test sequence justified as per IEEE 323-1971 "ES NO and NUREG-0588 Category II position?
G. Were performance characteristic's verified before' YES -NO during, and after testing?
H. Were temperature readings obtained by thermocouple location on, or as near as practical to the surface YES NO of the component?
- 1. If not, is adequate justification proviede showing that the component was exposed to the specified WS NO N/A temperature environment?
- 5. Does the test report address thermal aging? YES NO A. Was a qualified life and/or replacement schedule YES NO established?
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YES NO
- C. Did thermal aging simulate design life at normal YES NO
, conditions (temperature)?
- D. Was test sample operated to simulate expected l mechanical wear over design life? (electromechanical YES NO N/A j equipment only) i l
- E. Was test sample irradiated to the normal service YES NO life dosage before seismic and DBA testing?
- F. Was test sample irradiated to the combined normal service life dosage plus DBA dosage before and during YES NO DBA testing?
- 6. Was equipment inspected after type testing? YES NO A. Are the results of the inspection recorded? YES NO N/A
- 7. Were any failures identified during environmental YES NO qualifications?
A. Are failures justified? YES NO N/A I
! 8. Is the test facility (set-up) described? YES NO N/A p) 5
- 9. Is a description of the instrumentation provided? YES NO
- 10. Are test conclusions consistent with test objectives and YES NO supported by test results?
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i 11. A. Operability time demonstrated B. Accuracy demonstrated C. Response time demonstrated
- 12. Does the report have an approval signature? YES NO N/A
! 13. Is this report acceptable? YES m COMMENTS: 4 i
RECOMMENDATIONS
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APPENDIX B ENVIRONMENTAL QUALIFICATION
SUMMARY
SHEET l
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APPENDIX B ENVIROliMENTAL QUALIFICATION
SUMMARY
SHEET (EQSS)
Tne EQSS is a one page summary (a blank copy ot which is included atter this description) of the qualitication document (s) to record the test or analysis results.
The data entered on the EQSS is, for the most part, self-explanatory. Each tQSS is numbered by specification number, succeeded by a number to sequentially identity each component or group of components. When an EQSS is revised, a revision number is added beginning with "1".
Data entries include procurement document reterences and test report identifications with applicable IEEE standards and the qualified life of the equipment.
The TEST SEQUENCE entry details the specific steps performed during the environmental qualification test in the sequence that they were perf ormed.
Tne TEST ENVIRONMENT data tabulates the temperature, pressure and humidity test parameters, and their duration. In addition, the reviewer must ascertain whether the operability time and the equipment accuracy performance is acceptable.
r0 V Other entries include the APPLICABLE ENVIRola1ENT ZONES in which the equipment must be qualified, and RADIATION AGING, THtkMAL AGING, and mechanical CYCLE AGING data from the test report.
Completed EQSS copies are indexed and included following the i blanx copy for those qualification documents whicn have been evaluated. Each EQSS is referenced in the Equipment Qualitication Status Report (EQSR). The EQSR also gives the qualitication status for the equipment items.
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INDEX ENVIRONMENTAL QUALIFICATION STATUS SUhMARY t
' 'f (EQSS)
DATE EOSS NO. EOUIPMENT TITLE VENDOR REVIEWED 003-01 Limitorque Valve Actuators Gs-NED 12/29/81 SMB2, SMB3 124-01 120VAC Distribution bystems b/29/81 124-01A Ponel Controls b/29/61 124-01B 6/29/81 127-01 SKV Power CaDle Kerite 1/4/82 128-01 000V Power Cable Oxonite 11/20/81 129-01 Instrument Cable RocKbestos 11/27/81 149-02 12/31/81 130-01 Instrument Cable Raychem 10/26/81 134-01 Electrical Penetration Gi 11/30/81 Series 200 Low Voltage 134-02 Electrical Penetration G6 11/06/d1 Series 100 Medium Voltage 159-01 Splicing Tapes Okonite S/19/b1 T35, T95 159-02 Lugs 6 eplices AMP d/4/81 52900 thru 53900 i
159-03 Switchboard Wire GE 12/2/b1 l SIS 157279 i
- 159-04 Switentoard Wire Rocktestos 8/25/u1 Au30 6 159-0$ Raychem hCSF-N Roychen 11/7/61 5 place & Termination 197-01 Motor Operated Valve Henry Fratt 12/11/e1 Actuators, Lim 1 torque ITT Grinnell Contramatics l
214-01 Motor Operated Valve Velan 11/30/81 214-32 Actuators, Limitorque 12/11/81
! -s 232-01 Solenoid Valve Velan 8/16/81 l
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DATE EOSS NO. EQUIPMENT TITLE VENDOR REVIEhhD ASCO WJKX-296-01 Miscellaneous Transformer Magnetics 12/01/u1 233-01 Motor Operated Valve Velan 11/30/81 253-02 Actuators, Limitorque 12/01/u1 253-02 12/08/81 276-01 Fan Motor 143TC2 Buttalo 1/13/ue Westinghouse Forge 289-01 Hydrogen Recombiner Unit Atomics 12/11/01 International 289-02 Limitorque (Rockwell) 12/11/ul 289-03 Hydrogen Recombiner blower 1/6/82 Motor Reliance Electric Co.
310-01 Electric Motor Operated Fisher 1/4/82 Control Valves Controls Harold Beck c, Sons 318-01 Solenoid Valve, Copes Vulcan 8/18/81 ASCO NP-8320 31d-02 Solenoid Valve, Copes Vulcan 8/18/81
}j ASCO HVA-206 313-01 Veltron 800, Centerline MCC 9/21/b1 32046, Dwyer 1647, Powers Powers 331-2792, Raymond HASR-49 319-O e ITT General MCC 4/29/b1 Nil-91 Powers 313-03 Solenoid Valve, MCC 9/1/81 ASCO WJ11KX- Powers j J44-01 Gas Analyzer Comsip 12/3/01
! 3 44 -01 A 12/3/81 l
406-01 Pressure Transmitter, hcsemount 9/09/o1 1153 derles
'406-02 Pressure Transmitter, Rosemount 12/22/81 i 1152 Series E 400-03 k'10 ,88-149 Rosemount 1/5/82 407-01 Level Switen 291- Magnetrol 1/9/62 B-3
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DATE EQSS NO. EQUIPnE!JT TITLE VENDOR REVIEhED fn .
(,* \
\_J 423-01 bolenoid Valve Fisher ASCO WJHKX- Controls 439-01 480V MG Set Louis Allis Panel 439-01A 6/25/81 439-01b 1/6/82 4 39-01C 1/b/82 439-01D 1/6/82 439-01E b/25/81 439-02 1/5/82 455-01 Instrument Cable orand aex 4/5/o1 456-01 Electrical Penetration Conax 9/23/u1 456-02 Electrical Penetrations, Conax 9/29/b1 Adapter Module 15.54-01 Solenoid valve, Valcor 6/17/b1 Valcor V526 88AD-01 Motor Operated Valve Anchor 11/30/81 uBAD-02 Actuator, Lbnitorque Darling 12/11/o1
( 6 8V-01 6 8V-02 Motor Operated Valve Actuator, Limitorque Velan 11/30/o1 12/1/ul obV-03 12/03/81 88V-04 12/21/o1 1
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E NIRO!!!E!.'TAL QUALIFICATION SU:S!A2Y SHEET (IOSS) INDEX DATE O' QS :0. EQUIP:!ENT TITLE VENDOR REVIEWED 3018 Barksdale BlT GE-NED 12/31/81 Pressure Switch 3021 Barksdale D2R GE-NED 12/23/81 Pressure Switch 3025 Barksdale PlH GE-NED 12/31/81 Pressure Switch 3027 ITT Barton 288A GE-NED 1/11/82 and 2898 Differential Pressure Indicating Switches 3032 Static-O-Ring GE-NED 12/31/31 SN and 6N Series Pressure Switches 3037 Yarway 4418C GE-NED 12/30/81 Level Indicator 3040 Fenwal GE-NED 12/30/81 Te=perature Switch 3048 Rosemount 1151 GE-NED 12/31/81 Diff erential Pressure Transmitter i
l 3096 ASCO HTX-8320A20 GE-NED 12/28/81 Solenoid valve 3110 Pyco/ California Alloy / GE-NED 12/31/81 -
NECI Te=perature Element i
3111 General Electric GE-NED 12/23/81 l ECCS Motors O
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EliVIRO!:ME: CAL QUALIFICATION SU:!!"JtRY SHEC (EOSS) INDEI (Continued)
DATE EQUIPMENT TITLE VENDOR REVIEWED EQSS NO.
1 1
3143 Magnetrol GE-NED 12/31/81
- 3. 5-751X-MPG-M14HY Level Switch L
3146 Conax 1832-159-01 GE-tED 1/11/82 Explosive Valve i
3902 General Electric GE-NED 12/31/81 47D518673 Electric Heater 3903 General Electric GE-tED 12/31/81 2CH6-041-lU
+
Blower 3904 Target Rock GE-NED 12/31/81 1 1/2 SMS-A-01 Solenoid Valve 3906 PYCo 102-3171 GE-NED 12/31/81 Temperature Element 3909 AsCO NP8316C37 GE-NED 12/29/81
- Solenoid Valve i
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3915 Rosemount 1152 GE-NED 1/6/82 Differential Pressure
. Transmitter ,
a B - . .-. . ._- .-,- . . . - - . - - . . . . . ,
EINIRONMENTAL QUALIFICATION
SUMMARY
NO.
SHOREHAM NUCLEAR POWER STATION-UNIT 1 lO SPEC. TITLE G' SPEC. NO. P.O. VENDOR TEST ITEM DESC.
MAKE MODEL APPLICABLE STANDARDS TEST REPORT NO.
IEEE TEST METHOD IEEE DOCUMENTATION ACCEPTABILITY IEEE NUREG 0588 CAT. QUALIFIED LIFE TEST SEQUENCE (R: )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
O TEST ENVIRONMENT (R: ) APPLICABLE ENV. ZONES TEMP. *F - - - -
~ ~ ~ ~
PRES. PSIG _ _ _ _
OP. TIME DEMO ACC/PERF DEMO RADIATION AGINC (R: ) THERMAL AGING (R: )
DOSE RATE RAD /HR AGED TO SIMULATED LIFE OF YRS.
DOSE PRIOR TO EtN . TEST RADS BASED ON AMBIENT DOSE DURING EM OF T EtW. TEST RADS AGING TEMP./
TOTAL DOSE " !
RADS CYCLE AGING (R: REL. HUMIDITY %
)
~
CYCLES REQUIRED BY ANALYSIS TO YRS.
(/ CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEWER: DATE:
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. o (19 - 8 /
SHOREHAM NUCLEAR POWER STATION-UNIT 1 f% SPEC. TITLE Nf)(~L EA A l87EAN SUAPI V RVSTEM SPEC. NO. Si}/.t309 P.O. 9100lokunyENDOR . (Q E-NE'D TEST ITEM DESC. /\4n To R 0 PERATEb V AL vf MAKE SMA-A MODEL AC RELI AWE , M -TtJSdt.ATlotJ VENDOR TEST REPORT NO. (n r m f 9 8 T*-/'2232 -O / + ADO I , (COO 37/o A (RAD APPLICABLE STANDARDS TEST REPORT NO. ON IEEE - R 23 - l CJV l _
TEST METHOD t960 UEA/ T//l/_ TEST /A/6 IEEE - bl./ DOCUMENTATION ACCEPTABILITY Aln F IEEE - 3 22- /9 W NUREG 0588 CAT. , T QUALIFIED LIFE /W) T6/ VE A/
TEST SEQUENCE (R: m R . */ (*o On ( C@ )
.O~
- 1. P R c > > M u N RR V H E A T T GS T- '/. HER T AG/NO TEST-/1070f* ,
CN ('n M Do /YE/V'r AARTS Ado Inf O)/ TH A fAXRS' Z,1220 u M int AR V H-E A T rF5~r3 6. S/kYK
- V/ ARA 7/n/V 7737 AF' ArTf]ATd/
n/Y Ar To A7D f G. >9n (VG-E T/;S T
- 3. ./RE. . L t t/E STERN "rES T ON G k67'bktlaENr STEAN+(WEMit*RL
/t'ron 70 A' ENvicR tu G AIT rE;S r O TEST ENVIRONMENT (R: o Ii _,. Aon 1 Tff32 -d/ ) APPLICABLE
'U
k ENV. ZONES TIME () -- lu l-Shr 5013 - 2Yl195 2'lbr-l&tl3' RAD D TUP. *r M29 SA3.5 13'1 2 rov '29'9 f PRES. PSIG 3D 70 IC l 20 46 T/P 2. L R.H. /d c %
OP. TIME DEMO -7 d8 fr ACC/PERF DEMO RADIATION AGING (R: 54 fcOONbk ) THERMAL AGING (R: .oen 5 sco/9R )
Q DOSE RATE l Y kV 4u !
RAD /HR AGED TO SIMULATED LIFE OF YOy YRS.
DOSE PRIOR TO b EtN. TEST . 'AlO 3AoS 3ASco 03 an3Ienr DOSE DURING _
. ST e AGING TEMP./
TOTAL DOSE % i O' RADS o"Io" /W / /oo CYCLE AGING (R: c, (,, 400/N )
I .1 Q
CYCLES REQUIRED 2000 l/se sq2}fx73LE YRS.
x CYCLES PET %)RMED (Electro-Mechanical Equip. only)
/kO
/ ACTVMCA OW W REVIEWER: &d h. , _fL. M/ N fYWTOR f'it.E S DATE: M/8 /
/
R: Test Report Page No. Reference 7/1'81
E!NIRONMENTAL QUALIFICATION
SUMMARY
NO. /24- O /
SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE Misc.elfonc*Ou\ b(. Onch h(s br* viri bd tiOr) Eco rc)s SPEC. NO. l14 P.O. 3/0~IO VENDOR 8 v s /c*/775 (co ho[
TEST ITEM DESC. 8ee /) ffac.l ed EO S ' si i l ce f.s /14 - o / A #/3 MAKE MODEL VENDOR TEST REPORT NO.
APPLICABLE STANDARDS TEST REPORT NO.
IEEE 3 23 - /9 7Y TEST METHOD IEEE 3 W - /4 75 DOCLMENTATION ACCEPTABILITY IEEE NUREG 0588 CAT. QUALIFIED LIFE TEST SEQUENCE (R: )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
TEST E!NIRONMENT (R: } APPLICABLE ENV. ZONES TIME RAD TEMP. *F PRES. PSIG T/P R.H. %
OP. TIME DEMO ACC/PERF DEMO RADIATION AGING (R ) THERMAL AGING (R: )
DOSE RATE RAD /HR AGED TO SIMULATED LIFE OF YRS.
DOSE PRIOR TO ENV. TEST RADS BASED ON AMBIENT DOSE DURING E!N. TEST RADS AGING TEMP./
TOTAL DOSE RADS CYCLE AGING (R: )
^
CYCLES REQUIRED BY ANALYSIS TO YRS.
O v
CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEhTR : (C w 1p b DATE:(o*3"'8/
R: Test de;jrt Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. / 2 'l- O / A SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE $5cellan eou s b 0 anci Dr. Di.s tribu tien Sco<ds SPEC. NO. /N P.O. 3 /0 7 / 3 VENDOR Ovs /cM3 (Coff0f TEST ITEM DESC. NOa d e hic Mc,/ dead bo sc Circui f /3 rea ker$
MAKE We.5 fi dolicu $r- MODEL 8ee A1/ce_ merff /
VENDOR TEST REPORT NO. /b290
~
APPLICABLE STANDARDS TEST REPORT NO. /2L/-C/
IEEE 32 3 'N 7/ TEST METHOD Te $ Y Mno /v f, 5 IEEE 3 W */9 7 I NTATION ACCEPTABILITY da vu e of a b [F -
er Sappor f uh a (fo io o n J' '
IEEE o n 0 g,, s ;, i,,Q u ,g g NUREG 0588 CAT. I QUALIFIED LIFE [L/O ve>ars TEST SEQUENQE_ (R: Ococoder 1 )
- 1. fursc foonb l Yes't 6. Vo brafion HsY
- 2. Ra d ia tior1 Aconaa s
- 7. Co lo bca fron Tes+
- 3. i~unctional Test 8. 1100 IIGS Temr> Aa.nn 150'C 4.12CO liRS Temo Ac;na 150'C
- 9. C.alahra ficn + 07elec te uc Mr
- s. CalibrO Hon Wes5 10. V, bra +;on t Cal; hea nca Tes7 TEST ENVIRONMENT (R: N/r9 Mo OOA tes[ 4cr[wmed '
) APPLICABLE ENV. ZONES TIME RAD N TEMP. *F PRES. PSIG T/P 3. l R.H. bll0 %
OP. TIME DEMO hi[A ACC/PERF DEMO N!d RADIATION AGING (R:8er_4.1 I e Ano F ) THERMAL AGING (R: Sec_L/,l,3 g [pg [ )
DOSE RATE /\/C P hros/ s deCf RAD /HR AGED TO SIMULATED LIFE Or * / 0 YRS .
I DOSE PRIOR TO
( EIN. TEST h/!d RADS DASED ON AMDIENT DOSE DURING EtN. TEST A/!d RADS p
m 9ogg j, j , ,o[ gggg DURATION 302 f /NOO1%
CYCLE AGING (R:&.e 4.f.1J App TT I L' "" $S" I " ^
CYCLES REQUIRED /d 000 BY ANALYSIS TO 8 YRS.
CYCLES PERFORMED 4. 000 (Electro-Mechanical Equi,p. only) v See no te - ca a Huuluren t I g j g 7 /
l REVIEWER: _w -t /f k DATE: b!19!?/
R: Test Report Page No. Feference 7/1/81
A ttachme.n t 1 to EQ.S - 12.'1 - O tt4 Q The. Follow.n3 type,s of circus t brealers are addressecd by EOS -124 - o /4 Th erma I- Mo3 ne ts c. Circus t Brea ker.s G01t OPtf QCtf EB EliB f6 IIFB FO Tri- Pau magnefit Teip Only Ctecait Brea kers FB mcP tlFB lYo feS 1.
(Sec. Therma l a9 s n9 secFoun o f EOS ~l24-c>ts9)
The the<ma I a9i ng tome and temp a >ed .simala ied a t leas t 40 yea <s a t 2r t (87 *d Ar all par 6 of the heca ker e< cept moldeJ, polyesIce 3 /aa3 ba.scs whic.b were oyed to the equivalent of t o y e a r.s. ,Su b.sequen t ana ly.3 i s 69. sed on the. oc ti -
vq hon ener9y of the weak link materrol (9luu tape) showed c9a u vaien t ag,*ny o f 89 year., or HO 'c (Ic'/ *F) i o f EQ S -12'-l <t /9 )
- 1. (See.
The tescycle t reaho.nYr. rect.on UL s t on Jord W 9 I've c ferenwS theur cycle aging regaire ment. The sianJard calls &
6000 load operoFions ,4000 14 ha d opera h cas for a fo to I o f /0, 000 opera ft od3 l
l l
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /14-O/3 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE (d,*sc.e llantonas AC. and DC. D stro bu r o*o n Boo rcl_s SPEC. NO. /24 P .O.3 /0 7/3 VENDOR ,3 v.sf e /0 3 C_cafro/ l TEST ITEM DESC. Ground 0ua Enut $Q for and das $JnDc,rf/[nia l- lbarrICr '
MAxE Penn Cus+orn (Dcidinas MODEL Pienco- All.
VENDOR TEST REPORT NO. Ac80m /b397 APPLICABLE STANDARDS TEST REPORT NO. /3.4-O/
IEEE 323-/9 /Y TEST METHOD Or70 [V.'s / s IEEE 3 @/ - / '3 Y DOCUMENTATION ACCEPTABILITY Un Jue.O to b/c_,
radia tion ona/v ,;s car
$a ffs'c it n t /V d N!a mc*A tc'd NUREG 0588 CAT. . .'L QUALIFIED LIFE 2 40 y ec.r>
TEST SEQUENCE (R: A/[A )
- 1. 6.
- 2. 7.
- 3. s.
- 4. 9.
- 5. 10.
(Oj TEST ENVIRONMENT (R: N//} Mo O O A fe._5P per[orw7ec/
) APPLICABLE ENV. ZONES TIME RAD /y' TEMP. *F PRES. PSIG T/P 1/
R.H. N//i %
OP. TIME DEMO N //9 ACC/PERFDEMO_W[t}
RADIATION AGING (R:8ec h e,1 Ll.1. 2. ) THERMAL AGING (R: Sectron 4.2. )
DOSE RATE N //} by a v10 [v _s . 3 RAD /HR AGED TO SIMULATED LIFE OF /N!N YRS.
DOSE PRIOR TO ENV. TEST A/ !d RADS BASED ON AMBIENT DOSE DURING EtW. TEST N[A RADS p
TOTAL DOSE 1 # /0 RADS CYCLE AGING (R: Nc, r reoverc(I )
" ^
m CYCLES REQUIRED BY ANALYSIS TO -1 M. /u- YRS.
CYCLES PERFORMED (Electro-Mechanical Equip. only) 4 REVIEWER: AL M tb4 DATE: d *) M[
R: Test Report Page No. Reference 7/1/81
l EINIRONMENTAL QUALIFICATION
SUMMARY
NO. / 2 7- O / Rev/
SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE 5 K V Pou./er Ca6/e SPEC. NO. /77 P.O. 3/0861 VENDOR fe r-if e Com oarn 'v !
TEST ITEM DESC. Sinnie Condue /at GAu/G KKV Lxe Cairle MAEE ker;+e ComAw MODEL HTI<(s! 98) insulokon 1p (~yc.gi/ ) ,oc he+
VENDOR TEST REPORT NO. Mone issue daYe Mov /d/ . /98/
APPLICABLE STANDARDS TEST REPdRT NO. /27 Ol IEEE 383-/97'/ TEST METHOD Scou e//o/ Tes/ /b o /vs if IEEE DOCUMENTATION ACCEPTABILITY Ace e elo b/c IEEE NUREG 0588 CAT. T QUALIFIED LIFE 40 vg or<
TEST SEQUENCE (R:$e.} 'Iion/ A coar 'i
- 1. oara 4 e fec Hor 9 0 Booe /3 ento KsG s /
)
"l //
- 1. Th erma l A a in a s. .Tnsulof-ion r esis fance cl> ec le's
- 2. fladiation bes?no s s
- 7. Hiah Vnl+aae A C + e s'f s s
- 3. 3, ~,,la +ed Loc A (6 dad 8.
- 4. Insnee Hon Wi-not tes+ 9.
- 5. Simulofed LOCA (9y dov) 10.
TEST EINIRONMENT (R: See fio.3 O_ooae /V [/ o ure 3 ) APPLICABLE M op. time demo exfended by 4/yle %alysis 17VG4-hSO2.Sec GO ENV. EONES TIME 4 UAb ] NA6 Sb NAj 1304 1103 RAD /)LL TEMP. r 340 32.0 250 200 PRES. PSIG M.f GO efmos Almo; rfp gtf R.H. /OO (forav) %
OP. TIME DEMO } /80 Dayt # ACC/PEFF DEMO 8 RADIATION AGING (R: Sec. O Aoo. A ) THERMAL AGING (R: Sec. A acae / n,,ro . V )
Ii '/ '
'l DOSE RATE / r/O RAD /HR AGED TO SIMULATED LIFE OF 4 0 YRS.
DOSE PRIOR TO g EIN. TEST 2 x /O RADS BASED ON AMBIENT DOSE DURING EIN. TEST AlonC RADS j
TOTAL DOSE 2 V /0 RADS CYCLE AGING (R: )
- " "C#"
CYCLES REQUIRED Mot keovired g g; N[$ YRS.
CYCLES PERFORMED d 5 A 3in3 bo5ed OM /9V *F (70 t ) Conducfor-(Electro-Mechanical Equip, only) temjo g//fh / S/.4 (g3*c.) Sur[occ femp.
I REVIEWER: < tm _ M u/ MM - DATE: /h 82 R: Test Report Page No. Reference 7/1/81
p ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /28*O/ Re.f /J SHOREHAM NUCLEAR POWER STATION-UNIT 1 C)
\
%s SPEC. TITLE 61)O i/v/r buer (O b /c.
SPEC. NO. il? P .O. 3ID.iS 7 VENDOR O k o n a rt* Dm ean s' TEST ITEM DESC. 600 'h r t a/1 U TC, 030 ' 0 6 se . fc f ENs ' n :u 'o - ;
MAKE O t o n , te C om &_s a i MODEL '/ r'r VENDOR TEST REPORT NO. /\/C 4/\/ - /
APPLICABLE STANDARDS TEST REPORT NO. /38-C/
IEEE W. ~ l 0 T 'I TEST METHOD %aven tsai Te J!Ank. , !*;r:J estal IEEE 3 23/' M DOCUMENTATION ACCEPTABILITY 1,
1 an !s r_ Q (. . - c . . . r. . .. .* !,e. 'o .v IEEE ,,g ,y u gj u, g , g,, ,
NUREG 0588 CAT. [ QUALIFIED LIFE Rt.' v .* u r ,
TEST SEQUENCE (R: 8ec fe co /.4. /. F )
- 1. f lec tratu l Terr 6. l/clto s W, b hin : 5;i Gn v'In.!s'c ')
i
- 2. Therina! A a r ro .2 7. <OO b. ., ' c r.13 re.i t
- < g
- 3. Tr,ar]rotoon 8. Vo / to.n V. rn.' fan J F1c T(?c .//n. ' i'. h
- 4. flee t? ,- ,e T'e a t- 9.
~
c'en 'roco! D ;*
- 5. 3 r] Day r Clo) tef
- 10. D, e l.. . , , ,_ !s rc. ;. , +N Q.y TEST EtNIRONMENT (R: S ecte c,.1 / 4 .f. 3 . /2o n .'3 W., c An , -
) APPLICABLE
/ 7 s G d - '# 01 Sec *E s 6 . 'O ENV. ZONES TIME 3 r/C5 2 Itcs 3 !<45 3 /tc 3 4 ila s l ?/ri b h , a c 1.0 c sys RAD nin TEMP. *F 3& foO 345 335 3rr 2cr 1,2 l lil PRES. PSIG llY [rnTro //4 /Oi 7V 29 0 !O 7fp o , .,_
R.H. 100 ! WR!)v ) %
OP. TIME DEMO /90 O/P/ fe ACC/PERF DEMO __ f\/
/^
RADIATION AGING (R: Acc n j.< 1 ) THERMAL AGING (R: Sem *,c a 7"l1 # /100 '). )
DOSE RATE 67rc 75 RAD /HR AGED TO SIMULATED LIFE OF l' ) YRS.
DOSE PRIOR TO ENV. TEST 2. C/ 8 /O RADS DASED ON AMBIENT DOSE DURING EIN. TEST /On e RADS AGING TEMP./
TOTAL DOSE 3. 01 //O /
RADS DURATION l 0 ^' 'r~ / [C Y st/h CYCLE AGING (R: )
CYCLES REQUIRED b'.. f kedu.rtd " ^ ~
BY ANALYSIS TO YRS.
\ CYCLES PERFORMED
( g Af3sf, ,, , . / s,.*, ,,,a- o c, o ,' .5 v,, e i (Elc,:tro-Mechanical Equip. only) ,, . ., y 3, y,_ g., , , . . ,. , , , a r ' J' t .
i i REVIEWER: /' *' /' C ' ' 'P L '
DATE: L
R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO.139 -O /
SHOREHAM NUCLEAR POWER STATION-UNIT 1 hvj g j (D
i SPEC. TITLE 3CCVW foco v" hDsL+ Contro I d becom,a , hee C4 6Ie SPEC. NO. I% P.O.3i0553 VENDOR be7Mc'S Cerv,NL4 TEST ITEM DESC. Nr/ Qf try-he.ner n-t- 1 MAKE h MOC hr nct VM i MODEL Se<z m++me s-m m+ i VENDOR TEST REPORT NO.T,*ra; an_1 f .IITChenco.11u Cwss 'mit.a.A ~1 ""I-T1 Md.v IA-9-TO APPLICABLE STANDARDS TEST REP' ORT NO. MQ-Oi IEEE 3R 3 - lCi 1 L4 TEST MET 9D bni V7A-t t ("1 I N5Y v
IEEE DOCUMENTATION ACCEPTABILITY betrofoP3 f/7.
N t 3 fZF G% M 9 9 Crt+fnm ts M
%% ! 4 t m% "# #
NUREG 0588 CAT.~~[1 QUALIFIED LIFE HA LA , > n f-N
,.)
TEST SEQUENCE (R: De o._9 R Ybr , 3 ~~7 )
J 1.% a.,-mm0 %,e 6. \/'m 1 -b-m n hN +h%M 'TUrt-2.VnH Q ttmm Mcs L c 7. w6 d , , h+ LOCA Tvat 3.Y) \ +ces (11hknk'Ye st8.YO He vo, b t-hSh tr'Y"3 TctM a
4.Te-d$d i o n A o /mo. 9.
- 5. *o Enu l- Om TO-+ ) 10.
J TEST ENVIRONMENT (R: M ev7. I1 A n d han & '7 ) APPLICABLE
__) ) ENV. ZONES TIME 3M5 .~h Hqs ~6 HRS l~$taes 4Nc $ Hes %D-15 144 aAD K) f ;
TExP. F 34 to Iyo 3% 5S5 315 ass ala ; etc PRES. PSIG I(3 E r* I13 ra' "
T/P NQ l I R.H. 10 0 M prct Q s OP. TIME DEMO N 9 M 'i.,S ACC/PERF DEMO k(( N g ,
RADIATION AGING (R:bf Tir m,,E,S e V'o, c,y G THERMAL AGING (R: Sc_c H "l")c T )
a DOSE RATE ( \c l O RAD /HR AGED TO SIMULATED LIFE OF M C YRS.
DOSE PRIOR TO E?N. TEST >C lO 7 RADS BASED ON AMBIENT DOSE DURING EIN . TEST nnC RADS AGING TEMP./ o TOTAL DOSE Ax iO E RADS CYCLE AGING (R: ._ )
- "" O CYCLES REQUIRED h[0-t- bot %,-et el "
y/g ygg, CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEWER: W k DATE: //!27 N R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO.1 Ac) - OI kd.v". I j SHOREHAM NUCLEAR POWER STATION-UNIT 1 g q SPEC. TITLE 3cov as race v E M histw+ Co ,+ ,.o f am l e6 - m m N m In hto SPEC. NO. Ia et P.O.3 s o553 VENDOR Wer W f w A4-m S (mmm no TEST ITEM DESC. $n n _ h -f-+me-_ M rrm t 1 MAKE Non h ha r-d- Q 1 MODEL bner. A+J-ne- hw n-I- C)
VENDOR TEST REPORT NO.E-at m! 1 ar 3rd ct om Cfmer.-Lniore 1 m % s tr &i en 9a v. IA-9-9C APPLICABLE STANDARDS TEST REPORT NO. Ic%-OI IEEE 3*R 3 - f Q 1 t.4 TEST METHOD b u e n tio J T a 6"f-IEEE DOCUMENTATION ACCEPTABILITY hDin ble,l IEEE worrFn oc59 9 rnwe ect_ni mg, ,4, , c sn a ;
NUREG 0588 CAT. i 1 QUALIFIED LIFE 4 -4C) t fr a r-- %
TEST SEQUENCE (R: m eno A 1(n -ib , y -
l9 )
6 .)
- 1. T'humal A ,- , ," n a 6. Yn l -f-clarf, ( , %M-Aty ind T2 <rf-
- 2. TsiA in 4i e Ab 7.3L F; D t.s nm d- Lom Tv Ab a
a l-t n e in .( i h-+ M ra'T2'Gt. 8. src t-+ndre 'e Aih 7 cts 4 3.
- 4. 9 est h n n n Reg in o 9.
5.05 ) T)n , , LOCm O_,*:>h 10.
J TEST EINIRONMENT (R: hri m 2 a a m C) m e,n. Ib ) APPLICABLE k J L
) ENV. ZONES TIME 3ff85. ca. H R 3 MR5b hrs. 4 sRs Er HR5 aoCNs 1 9 r? RAD FSI k TEMP. r 3 w <o isc sq (,, n=5 3s et65 c'ai c L aoo PRES. PSIG l13 EiNw I,3 93 69. M. O e~,, J~ rf, si g R.H. g oo (S P e n.Q %
OP. TIME DEMO 3Cl5 b o _S ACC/PERF DEMO V/A J /
RADIATION AGING (R:b a IIrn,,,. . %,n W . ! 7) s a THERMAL AGING (R: 3 017 3 'n.1fr a
)
DOSE RATE lxInb RAD /HR AGED TO SIMULATED LIFE OF 40 YRS.
DOSE PRIOR TO ENV. TEST c1 x C RADS DASED M M N TEMP OF / 7 (p *F DOSE DURING EtN. TEST h[o a #- RADS AGING TEMP./ ,
T(yrAL DOSE 2 _ X- l C RADS DURATION ooc 0 > /! ON CYCLE AGING (R: )
CYCLES REQUIRED M o t M G Q_C): r-dX-i C\ CYCLES PERFORMED A. Y M /S YRS.
h (Electro-Mechanical Equip. only)
REVIEWER: A b DATE: I/!27!8/
R: Test Report Page No. Reference 7/1/el
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. /'2.9 - 01 MW O SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE 3 Coves cecov T:,, n_ T2a wh4 6trel a, d'I~_n%e.-.,c,,+a f .~ /1@
SPEC. NO. l G C) P.O.3tO5S S VENDOR Mer MbdM4M CC)rm mmm TEST ITEM DESC. Rei v-na- S 1 _ $ny- ic/L oc 1 v_ t'n I fn H #
MAKE kod her W S fo -var nrst4 MODEL 99 % 6- IOR > ce d T4SS f >-IIS VENDOR TEST REPORT NO O 4 G,e +, % k f- N d I ~d I C o m ea i Ce n 3 t ,, 3e + e ens APPLICABLE STANDARDS TEST REPORT NO. \aci - O Q_>
IEEE 373 - I9 ""7 4 TEST METHODSc.coermi .E2 J Te:"5 4-IEEE DOCUMENTATION ACCEPTABILITYtQeeyed ei hla r4 u rR 2 6 O*55'c R /n+e.2J'>n_ e -TT IEEE .Thair+-rm ,m s NUREG 0588 CAT. __LL. QUALIFIED LIFE L.-In r,2 n c s TEST SEQUENCE (R: MaaOA I,A,7 )
J l@wa i % ,- e 6'JnsoJay ,onbina C hy e !C -
a
- 2. Tach + , c,m r% j, ,, c, 7 3ss Ik h +- Leew s un4 io n 3.3 0 D e m L.ocN hh+ 8. I nsolado6 Rs.s+a,,<1 C hect-4.l rm=> o lei 4-s e dd-s rsicM Mmer d 9. Dr m ld_C"-4 r- f e- Tc7 S b
- 5. bi aJ er cA r- i c "Tez.3 10.
TEST E!NIRONMENT (R: Mnna_ '"~} } APPLICABLE v J ENV. ZONES TIME 3 HIEb 3H G- 3 3 N R.5 4 f9 r23 IO5 HRS 3Al O95 pao Qgi TEMP. F 390 340 3ao 3 00 a50 c700 PRES. PSIG I09 loH 75 Sc2., 15 O TfP n,i R.H. @ [$Dr%) %
OP. TIME DEMb bC f Cl Nt4 s ACC/PERF DEMO rs/ / A J
RADIATION AGING (R: boa,A+F ) THERMAL AGING (R: h/lc,c7_ & Mr H )
J J DOSE RATE 5x IC O RAD /HR AGED TO SIMULATED LIFE OF '/(; YRS.
DOSE PRIOR TO EIN. TEST dX lA b RADS BASED ON AMBIENT DOSE DURING EIN. TEST (\[o nrL RADE
,j TOTAL DOSE d_, x. I /Y RADS CYCLE AGING (R: )
CYCLES REQUIRED inh + Mr_qo r e r4 A
[S S N/R YRS.
CYCLES PERFORMED
\ (Electro-Mechanical Equip. only) n REVIEWER: A NL DATE: /2 /
R: .ast Report Page No. Reference 7/1/81 1
o n
/
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /30 - 0 / Rev M SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE To 3 7 rusY)e a 0 t bQ b /c SPEC. NO. /3 0 P.O. 3 /0 8c? / VENDOR /2Ovc e 77)
TEST ITEM DESC. $<e*_ _ OTfoc./3rY1eOff MAKE /2o W_ b c tri MODEL E/or>v fr"O /
VENDOR TEST REPORT NO. 5058 F - C 40 33 - / , E UI /13 7 r EM i4O 1 APPLICABLE STANDARDS TEST REPORT NO. /30 - O /
IEEE 383-/97'/ TEST METHOD .h._, .> f,, / Te r7 //?o o Iv 3, s IEEE 323-/97'/ DOCUMENTATIONAbCEPTABILITY A a e fac h/c IEEE NUREG 0588 CAT. f (hof I ;n 40.S \ QUALIFIED LIFE 4C ytoe3 TEST' SEQUENCE (R: 4no ~fT oo 6. R e coe f E/71 /4 0 7 op i+l '
)
ll /J '
IJ
- 1. (_.cmb,m.d Rodnotro 3 + The<mol & na 6. Voltaae LU, It n taacl Tes,
- 2. Inw lahon Pes,11once Cliec s 7.
- 3. 30 i)av i.o c t) expos ar e. 8.
- 4. Ben d a ll, = 1, Pn u t,al re s t 9.
- 5. i.CC A hn fr na a tr oo) 10.
O TEST ENVIRONMENT(R: A00 W na 6 Arvo I/// Meoc ef f /T) 1401 )
APPLICABLE ENV. ZONES TIME 10 NRS 91 /fRS 16 DVS t il DY5 i&5~ D/S RAD t1u. dec _ f c.-
TEMP. F 357 175 lil 200 /N NA PRES. PSIG 70 3/ /C /O T/P rW R or M-R.H. /00 % o'iJa OP. TIME DEMO .3'36 /)Y) ACC/PERF DEMO /V/d RADIATION AGING (R: i ;1 ') THERMAL AGING (R: ($
77- h7e I? r ,7Vig-)
tr o s.
DOSE RATE /\/c r 5' r o t e ci RAD /HR AGED TO SIMULATED LIFE OF I><" < .i /2/.7 5 ) 3i YRS.
DOSE PRIOR TO ENV. TEST O /0 RADS DASED ON AMBIENT DOSE DURING ,, y ENV. TEST /3 #/C RADS AGING TEMP./ ,
A N TOTAL DOSE 2.0 / /C RADS
/ Oy<
CYCLE AGING (R )
CYCLES REQUIRED /Ve t /2eo u rc e ,1 NOT AGED-JUSTIFIED BY ANALYSIS TO N YRS.
CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEWER: A M 6v' DATE: /O*26*J'/
R: Test Report Page No. Reference 7/1/81
ts O
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /34-C/ rie g' I SHOREHAM NUCLEAR POWER STATION-UNIT 1 0 SPEC. TITLE ide:> r for 05, fo r nm en t ?lel f f * ' u ' he'M T% f
- OH ? -
SPEC. NO. I3d P.O.3lO5 78 VENDOR 0errer O l 5'ec f f at TEST ITEM DESC. 6,'cc fr , < 3 / (c.at,:,..+,.iT [e,if d.',,',.
MAKE Ih.,s e ra l /5!< c f e ,r. MODEL 5'erre : 1Q0 '
..,.., ' - I r ca VENDOR TEST REPORT NO. 9 '/'/ -% O//
APPLICABLE STANDARDS TEST REPORT NO. / 3 '-/ - 0 /
5 IEEE '2/ 7 - / -f 7 2 TEST METHOD $e;_s ,/o., ' 9:7 IEEE DOCUMENTATION ACCEPTABILITY / '/ .'
A : : .- e bs e'. 'c NUREG 0588 CAT. T[ QUALIFIED LIFE r.' - -
TEST SEQUENCE (R: n 0 <_m ? )
- 1. & ci ,m ! (.,c /e 6. l cn 2 T~e, m k . < . L-x r3
/ ='
- 2. 0 _a,-n m :s !?n z .a rc e 1.
- 3. n ue r_ ,i rr e. ,$ 8.
- 4. _ jic of TT. , ,+ 9.
- 5. _2 e , . . ,3 . c E. ? 10.
O TEST EfNIRONMENT (R: caae 32 ) APPLICABLE
< ENV. ZONES r
TIME UT- 'f D 3 E !/M5 / ' I /< d5 i / 2 CAV; 'e . J D RAD f)
TEMP. 'F 3 6/d ' 32.I O7~~ ! ' '
PRES. PSIG /O3 3 ' 2*> I
> 2b T/P ')
R.H. /00 %
OP. TIME DEMO 'T 't r' \' ) ACC/PERF DEMO \' 2 .
RADIATION AGING (R: D ag ,. Y ) THERMAL AGING (R: /V + /' i d e . :, . / )
DOSE RATE r/.? 8 c. ie d RAD /HR AGED TO SIMULATED LIFE OF YRS.
DOSE PRIOR TO ,
EtN. TEST !/ - RADS DASED ON AMBIENT DOSE DURING EtN. TEST N J" O RADS AGING TEMP./
DURATION /
TOTAL DOSE /3 RADS q REL. HUMIDITY %
CYCLE AGING (R: /" ? A e aa,rc f )
NOT AGED-JUSTIFIED CYCLES REQUIRED BY ANALYSIS TO YRS.
O CYCLES PERFORMED (Electro-Mechanical Equip. only)
,s 3,.
REVIEWER: /t a ' ' r ^"f -
DATE: -
i R: Test Report Page No. Reference 7/1/81
8 ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /34-02.
SHOREHAM NUCLEAR POWER STATION-UNIT 1 O
SPEC. TITLE SCOC$Or Con +o r n in ent Electe r w l Pene +<c. w n ,
SPEC. NO. /34 P.O. 3 /0878 VENDOR bencro/ f/cc/ ret _.
TEST ITEM DESC. E/eefroc_al {c.,forniner1t hcne $ro f!CO MAKE &c.neral Elec +r re MODEL 100 See,e, s 1< v /s)e< >.a,n V: / +oac-VENDOR TEST REPORT NO. '7'/ 6 02-1 APPLICABLE STANDARDS TEST REPORT NO. /34-O1 IEEE 3/7-/472 TEST METHOD Seoven tr ol Te~ s- T-
- IEEE NT Nm r Annic / /e,
% nerATION tu r t ACCEPTABILITYtesT ,3 rcuJw&J or anulv NUREG 0588 CAT. I QUALIFIED LIFE Ne h de / rr m e.)e _/
TEST SEQUENCE (R: May 3 3 )
- 1. Gamin o e rna s u r<- 6. (Therovsa l Cvele\-r oe,forrvsed f ir,rb.>,end-
- 2. Eintrico l tes tina 7. $#lY
- 3. LocA e.
- 4. _ fo_ + L oc t} t e n- 9.
- 5. 10.
TEST ENVIRONMENT (R: [co e 2-3 ) APPLICABLE ENV. ZONES TIME 4//OS G ///25 1 240 //6 i RAD D TEMP. *F 340 '
320 l 20 l PRES. PSIG /C3 ! h/ 10 T/P 33_
R.H. bM/?Y) /CO %
OP. TIME DEMO /0 Ouv3 ACC/PERP DEMO /V/d RADIATION AGING (R: A0o /3 ) THERMAL AGING (R: Ne 7- Oddre_s se J )
DOSE RATE 3 7 Y/O ' RAD /HR AGED TO SIMULATED LIFE OF YRS.
DOSE PRIOR TO P ENV. TEST /#/E RADS BASED ON AMBIENT DOSE DURING ENV. TEST N J n C. RADS AGING TEMP./
'IOTAL DOSE /'/O DNION /
RADS CYCLE AGING (R: App A Serretal Cyr[c. )
- CYCLES REQUIRED /OO #
- BY ANALYSIS TO YRS.
O' CYCLES PERFORMED /20 (Electro-Mechanical Equip. only)
,, n : 4. ,
REVIEWER: / M- O // i ^j) 7 k DATE: II'b R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /b9-O/
SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE ELECTRICAL 'DJSTAU.AT/00 v
SPEC. NO. $M/-/N P.O. M\d VENDOR VA8/CUS TEST ITEM DESC. di'0/hd44'8 f//.5fXMED d6/E5 W/f-4id T-M TArY5 1
MaxE OkOM ITE. MODEL T-355 T-95 6PLicE TAFES VENDOR TEST REPORT NO. NG RM- 3 APPLICABLE STANDARDS TEST REPORT NO. TR - IZ E$-OI IEEE M3 - f 3 TEST METHOD 6EGMEtJTI A L IEEE 32.b-f17b DOCUMENTATION ACCEPTABILITY - NOT IEEE APPucA BLf: TO Geov CAfN_E5 U683 6D SHCREH A(V\
NUREG 0588 CAT. "
QUALIFIED LIFE -
TEST SEQUENCE (R: ht_ D )
- 1. Svmpie. seledien+ peerbest 6. Lo c o- Wodi'Ie 2.'Preow %tices + dhe.c_w. 7. %d Loc.n Wi& slo.d
- 3. TheAvnc[I l\ 4 ime,
- 8. Adrl 10 0 DA'I Ensivtnmwr*
- 4. 3'r md. i di2n 9. Fi nct \ c h e.c k
- s. Tre -Lo cm ch eCx lo.
V TEST EtWIRONMENT (R: b D i~~)
I '
h ) APPLICABLE ENV. ZONES TIME wpRs sms MRS 4 HRS 21 HRS 2Ws Kcoq a3D ALL TEMP. *F =345' 34G 335 53iG Zlo5 2l2.
PRES. PSIG Il4 Ile- 101 74 3 0-2 O m u t= s TfP R.n. Ico s OP. TIME DEMO O O D b ACC/PERF DEMO RADIATION AGING (R: App 3 > TaERMAL AGING (R: R, 3 )
DOSE RxTE O,7 A IO b q
RAD /nR AGED TO SIMUtATED LIFE OF
[ YRS.
V DOSE EtN. TESTPRIOR TO 201 x'l0 RADS DASED ON AMBIENr sq 7 DOSE DURING E!N . TEST RADS j
OgO 3 DEES TOTAt. DOSE f0/CO b RADS "I"
l CYCLE AGING (R: .[k )
^ ~
CYCLES REQUIRED BY ANALYSIS TO YRS.
CYCLES PERFORMED
\ (Electro-Mechanical Equip. on1 ,
-Q'/
REVIEWER: / [/1d4 'U DATE: [
R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. l59-OZ SHOREHAM NUCLEAR POWER STATION-UNIT 1
[] SPEC. TITLE GLEC TRIC At_ IGsTALL ate otJ SPEC. NO. 614 I -169 P.O. v A%Cv'.) VENDOR V art 005 TEST ITEM DESC. l.O C15 3 6 P Lt C.F_ $
MAKE AMP MODEL 634
, 6 39 - - . 5 M - -
VENDOR TEST REPORT NO. 1i0 -Il51 to APPLICABLE STANDARDS TEST REPORT NO. I 59 -o 2.
IEEE 223 - I 9 7h TEST METHOD 6EGCEMTi AL REST / AMALYSIS IEEE :23 g g . [C] 74- DOCUMENTATION ACCEPTABILITY EPTASLE IEEE Ps72 / DG A NUREG 0588 CAT. l QUALIFIED LIFE M D TEST SEQUENCE (R: Mc\v_ /4 oF N )
- 1. ExArnieJE hococt 6. 6 PRAY
- 2. TtthP MISE 7. 1,= w% c c- 6 RetJGTH
- 3. dEAT kbE 8.
- 4. D@t2 L TRi c. (OL THST Adh 9.
- 5. Mt\D - 6 POSJ tRhE -
10.
TEST ENVIRONMENT (R:
Pc3 5 or M ) APPLICABLE
( ,e ENV. ZONES TIME 'vi-l 73% l %lf IIr.37Sm $Uk I#$N -[INc MD b TEMP. 'F $ 37o 3 70 h350 35o i 3o2 2co 8 FAc PRES. PSIG 160 tD o (30 (oo 55 2Jo i 3 - Vr 7fp gg R.H. }DD70 %
OP. TIME DEMO Ilo CRIS ACC/PERF DEMO N/A RADIATION AGING (R: 3 P 5 or i+ ) THERMAL AGING (R: 3 5 .< i.4 )
DOSE RATE O. 76 MF6A RAD /HR AGED TO SIMULATED LIFE OF _.
AC YRS.
DOSE PRIOR TO ENV. TEST 2.0 6 A to RADS BASED ON AMBIENT DOSE DURING E!N. TEST No NE RADS AGING TEMP./ 4 TOTAL DOSE 2.0 6 M O #
RAPS D M ION SI / 7 W CYCLE AGING (R: Nor TCQD )
N/A " ^
CYCLES REQUIRED N /A BY ANALYSIS TO YRS.
CYCLES PERFOR"ED N /6 (Electro-Mechanical Equip. only) DD'T' " D '" M E # 0 REVIEWER: & O -s k DATE : 6 4 -8 i R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. kb-O3 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE ELF _- C.TR) C_Pd._ T.bJSTR\_ ATIW SPEC. NO. 6H1-159 P.O. VARIOVS VENDOR V AfMOV6 TEST ITEM DESC. 6 ENERAL. ELECTRIC VolkENE 6UPREPtEL 67 cs72 7*)
MAKE D E.ME.R AL ELEc_TRIc_ MODEL 6I 57299 so TcMEoARD wtRE-VENDOR TEST REPORT NO. FRR4K1JM TusT TuTE # -C.4497-2 d 6E_.*PD-80 F
APPLICABLE STANDARDS TEST REPORT NO. TR- \ M -O 3 IEEE 6TD 3Q- lC)N TEST METHOD 6EQUEMTIAL 'TE.sT lEEE dFD 323- I)74- DOCUMENTATION ACCEPTABILITY mot ACfEPTAt3tE' FO RTHER ANM Y5t6 REQ'D .
IEEE NUREG 0588 CAT. T QUALIFIED LIFE F43T WDIC.A"TED TEST SEQUENCE (R: 3-I,2,~$
- 4-I of re_ pot't F-C44">7-2 )
- 1. "THERinAL A6tM6 NOTE: IN60L ATtod RESISTAMCE
- 2. 4MmmA RAo: ATi c+J Ex.FbsoRE mEM-OREmEMTs. mAbE #D EAc 9
- 3. $TEAin / CHEP1tcAL edHAY ExA050RE TEST STAGE _.
4.NW4DREL EEND "TW.ST
- 5. HMH RTEMD AL TE.%T C TEST ENVIRONMENT (R: R c.-5 of t eport #F-C_449 7- P_ ) APPLICABLE V ENV. ZONES y
o to 35 % o +o 4. MR 65 MTo 9 5 d ve ll.5 dro n5W TIME .AGHR M cays 3RR To(. 5HA 9.S ua 12.5 M iks u Td4tM ' TAD kN TEMP. *F 348 krtMC -34(o MO 345 'ns 3is 2(,s-PRES. PSIG,. 12.4- 12 4 O 17.2. % H 2 _ 7fp pi R.H. I00To OP. TIME DEMO llo DRM ACC/PERF DEMO b
- FRetn StA45 H.S HR Tb (10 tA95,2124 @ 5 P516 RADIATION AGING (R: Pa.ne 3-l ) THERMAL AGING (R: hG 4Oh N~b)
DOSE RATE O.54 ME6A RAD /!1R AGED TO SIMULATED LIFE OF 350,coOHRS DOSE PRIOR TO (40 YRS)
ENV. TEST 2 20 mA RADS DASED ON AMBIENT o DOSE DURING TEMP OF 90 C_ (IM r)
AGING TEMP./ O TOTAL DOSE 22_O ME6A RADS ATION / i b CYCLE AGING (R: h/ [ A )
- "" O CYCLES REQUIRED A -
BY ANALYSIS TO D
/A
/ /7 YRS.
CYCLES PERFORMED
( ,) (Electro-Mechanical Equip only) n REVIEWER: DATE: f2-02il R: Test Report Page No. Reference 7/1/81
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. /59-#
SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TINE Etscre/ cat IerAuAriOa SPEC. NO. El59 P.O. YARIOUS VENDOR VEN DOR TEST ITEM DESC. $lAll?l4RoAen Wil2r WM A B 30 - 6 MAxt: ROCKSESTt15 MODEL klR @__N bll E VENDOR TEST REPORT NO.
APPLICABLE STANDARDS TEST REPORT NO. W -(29-Of IEEE 38s-MM TEST MErHOD 6 eau EkJTl AL. M T~
IEEE DOCUMENTATION ACCEPTABILITY bCCEPT PGLE IEEE NUREG 0588 CAT. 1 QUALIFIED LIFE M VEM TEST SEQUENCE (R: ATICdS T. 4 3 )
- 1. TM@Mk(, k(d h 6- OLTA46- tTH5 TAU D
- 7. 365 OAY FbsT Loc.A (JAMPL E1)5
- 2. MIATlOM MtM6(6%lO9
- 3. Mot.T. WtTH5TA*JD . 8.
- 4. MADIAT(Oed Olu6 (1.5 M09 '
9.
- 5. 30 DM LOC.A lo.
TEST EINIRONMENT (R: El2t )F~ll.E. Oh! 74 8 U
, Y ohJ P4 h) APPLICABLE v G EIN. ZONES TIME 3% M bM bE bM bMS M RAD /\t t TEMP. r 3% MO 346 355 ats 2GB 2 12. 2co N PRES. PSIG 11 3 -
(13 is G) 26 o -
T/P wwas R.H. 10 0 %
OP. TIME DEMO .3b b ACC/PERF DEMO NA RADIATION AGING (R: M C.T E 3 ) THERMAL AGING (R: b 2 . NCT Y
)
9
/ %.)
DOSE RATE \ %to RAD /HR AGED TO SIMULATED LIFE OF g 0 YRS.
- 6. T- t O $
DOSE PRIOR TO O EtN . TEST RAuS aASED ON AMBIENT igg DOSE DURING E!N. TEST RADS j
rO m DOSE 2. A t 08 RADS WRATION F / \';bOORRS CYCLE AGING (R: )
CYCLES REQUIRED /h D NOT AGED-JUSTIFIED BY ANALYSIS TO YES*
CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEWER:
R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 163-CS SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE EL66/r'/C/2/ c[/7Sl/1//c?[/On SPEC. NO. Sff -/6 9 P.O.YMict? VENDOR VC< i 0 UT TEST ITEM DESC. WA-f Sh re n Yo h/A Inn e ilC[/V' 3)FFaf FJ [8r/ (o r [
MAKE kuO Fro MODEL \/CS -M VENDOR TEST REPORT NO.
APPLICABLE STANDARDS TEST REPORT NO7_ D C(3 IEEE - M 3 -l 9'7 N TEST METHOD .Sen ( 'enEta/ I6"?YS IEEE - 3 9 % - 1 C~f'l DOCUMENTATION AC PTABILITY NO- -
IEEE 6e e. ce m m e- a+n on _
gg, g g g g , . /5' 9-os NUREG 0588 CAT. T QUALIFIED LIFE 'r4O j e_o TEST SEQUENCE (R: )
- 1. To#d m nn ]
Tst s. MeliWo rm 1 A n a ,n t -n ?+ c, +
- 2. Acti nrT Stme M4 to n 7.
u u
- 3. (\h)( JPa r. FadM} ton 8.
- 4. LOCA Rim olq+ie.A 9.
- 5. krd- L 6/T,M b4 i E . net e rt .0.
hj TEST ENVIRONMENT (R: Det&
S ) APPLICABLE V O ENV. ZONES TIME 3hr 6 h e l 6hr 5s), %erl 1 i se isna artis i so& ano AQ TEMP. 'F S 40 M.>l40 r40 -gqof N O l 'qC !'50 0 '1s[ !200' PRES. PSIG iO3 -- - i 103 f 'l$ [ 01 i5 lC T/P MZMS R.H. t007 s OP. TIME DEMO $Od qs ACC/PERF DEMG N /r1 RADIATION AGING (R: noe ? /4 ) THERMAL AGING (R: NN 9 )
i tj ,
6(j DOSE RATEi .3 9 l Ne.fi RAD /HR AGED TO SIMULATED.-
LIFE OF ll 6/6 YRS.
DOSE PRIOR TO /
ENV. TEST \(o 9.3 M&- RADS DASED ON AMBIENT V
MSE Q TEMP OF I *F ENY. TEST 50 Mege RADS g j
^
TOTAL DOSE f_. / 9 3 Ah ed RADS CYCLE AGING (R )
/Y/A " ^ ~
CYCLES REQUIRED BY ANALYSIS TO YRS.
v CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEWER: dr n/ [i ! n/ / TIl DATE: //[7 2, R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. l97-OI SHOREHAM NUCLEAR POWER STATION-UNIT 1 h SPEC. TITLE NJ TGA y hLVE /NA H NC- I Vb n -+ WM N SPEC. NO.l97//A9/f5ilP.O.hr 53 VENDOR hv#rd th// TTGA/NEL L/Cen fed mal /CS TEST ITEM DESC. r"h i -t I
e MOV MAKE L.l m l 4 0 FO U e. MODEL MOTORt AC,TUATC6 SMB 0"I5 VENDOR TEST REPORT [JO.80058+ Acab- 8/3n03 MOTO8S(AlcNEl Relidnee.ACefs2.54 40 f /b stdet tD 8 TAttMorogT]
APPLICABLE STANDARDS TEST REPORT NO '
IEEE - % 2 - 1972 TEST METHOD & n,,entiA1Testi W IEEE - 08.3 - l N 1 DOCUMENTATION ACCEPTABILITY Acren+/IEle _
IEEE
%=e cn m m e n 4R ~ cener i A s ' -
mnet i+t a n s - EG R EF - MV-M NUREG 0588 CAT. 1T. QUALIFIED LIFE 40 Vr5 i
TEST SEQUENCE (R: oa '+-Io (BOO 03) )
- 1. Th ermM AairyT s.
v v .
- 2. M e c_hA ni cM Asina 7.
a v
- 3. AAciiation Aaina 8.
- 4. 9 1 F M rYu r A n'r"n o " 9.
v o
- 5. F_ noi r on rne nia l Te34 10.
TEST ENVIRONMENT (R: ca i n CBoCON ) APPLICABLE I O ENV. ZONES TIME O .5hr .5- the Z-/.Llkr 2.4-Z5hr 23hr - 16das RAD n, e TEMP. *F 2.50 2.4w120 7.5 0 2_am-foo 2.00 PRES. PSIG Z.5 75 -
l0 T/p f f9 R.H. in0 s OP. TIME DEMO l G el A S ACC/PERF DEMO RADIATION AGING (R: An R [MOOh ) THERMAL AGING (R: ret"7.(ROCOM[ M 8-nllb '
I Q Fd DOSE RATE I ( lO b RAD /HR AGED TO SIMULATED LIFE OF 131 day DOSE PRIOR TO ENV. TEST 2 X lO 7 RADS DASED ON AMBIENT DOSE DURING
^ " '
TOTAL DOSE 2 E {O~Y RADS D TI 165 F / 20d fl99.dne CYCLE AGING (R: rw 4 -% (6000_3 ) ) REL. M ID M fM %
5O CYCLES REQUIRED MO O B O nS .
~
CYCLES PERFORMED /393 I.y 12- 15 60055]
(Electro-Mechanical Equip only) Eq .
%e ett LO40C o brained by O r> sorf Tancr16 ho-f herma! lite +Murs REVIEWER:_ /M [Il 1A- DATE: /2 // lb/
R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. fI4-Ol SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE M Ant ja llv OOct-ated Stai n less 3-feeI \/alVd5 SPEC. NO. SH l-714 P.O. A1bR12 VENDOR \/ela n TEST ITEM DESC. Li mMord oe MoV MAFI Li mMn en U F MODE @CMM fS- O-M Ae_liance C Ws PiH VENDORTESTREPORYNO. SAA 69 4 $ Do 8' *' (n o n 37(a A APPLICABLE STANDARDS '/E'ST REPORT NO.
IEEE - 923 ".T. l TEST METHOD Mne fantiM Tr a sti na r o IEEE - M 2 - 72., DOCUMENTATION ACCEPTABILITY Ac eetaoe See comroents -+ sner ta c_h net i ttens IEEE g g gg g, qgy,g i NUREG 0588 CAT. IT. QUALIFIED LIFE > MOurS TEST SEQUENCE (R: On 3-5 ((oOO37(o4) )
- 1. Thermal Adinn 6.
- 2. MechanicYl A$ina - U V 7.
- 3. bArliPLHnn Acai v na 8.
v
- 4. [toi 9 m'i e $U&\*i f t ( AY1 Or) 9.
- 5. A cc'i ole n+ Si mt il A+1 on lo.
TEST EtNIRONMENT (R:T~ranKli A~1nal-MU4e r Aenort Fc3441 ) APPLICABLE 9% 3-5 ENV. ZONES TIME O Chr 'S-lohr Io.cJhr 3-11hr 11-13hr iSh r '2d etan' RAD D TEMP. 'F S t.10 Con, 340 h A2M252, 25i PRES. PSIG 105 %5) tc6 77 t9 15 T/P rz R.H. 100 %
OP. TIME DEMO SO da M ACC/PERF DEMO RADIATION AGING (R: nn 4 [M(13*][,M THERMAL AGING I. R : n A 3 1 (RAASS-M fn . f il)
Id only the motb8Wdtor g' DOSE RATE l Y lO b RAD /HR AGED .O SIMULATED LIFE OF N3 YRS.
DOSE PRIOR TO E!N. TEST EO4 x.10 4 RADS BASED ON AMBIENT DOSE DURING TEMP OF ]$R *F ENv. TEST -
RADS AGING TEMP./
TOTAL DOSE Eo4xIOb RADS DURATION 130 C / IO O e CYCLE AGING (R: n %4 (GOO 3'MAI) REL. HUMIDITY Not - Oi \1e O %
ggg v NOT ?.SQ-JUSTIFIED CVCLES REQUIRED 50 0 BY ANALYSIS TO >Q O YRS.
p CYCLES PERFORMED ROO QUtv. aqe a.+ 153"F is de.termiocd
\ (Electro-Mechanical Equip, only) b pn to P.3, to bCr &l lifc RFVIEWERw / W [/ )- 724 DATE: if OM/
R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 2 / 41 -CE.
SHOREHAM NUCLFAR POWER STATION-UNIT 1 SPEC. TITLC _M a n U4 l } y Oor rel'rFd 8YS i n $PSS 8 YFCl VdlV6S SPEC. NO.BH I- 2.14 P.O. 31 5 I 2. VENDOR Vela A TEST ITEM DESC. l.Am i Yn rt7, ie. M OV r
MODEL MOTORtAC.TUATCti EMB-OJ5 MAKE L.1 m 1 Y O F Q U e. MOTORS [ALONEl 2.54 40 f[-/b start toa VENDOR TEST REPORT riO.80058+ Acob- BmO3 8elidnee.Acefm 8 lAu_Marantr]
APPLICABLE STANDARDS TEST REPORT NO.
IEEE - @ 2 - l972 TEST METHOD c90r pFntI ell TeMtM IEEE - Ob - l@ l DOCUMENTATION ACCF TABILITY Accr-ota$__lc _
IEEE CP f" com MF AYA - Mot e idl ' ~
chnef i+i o n s - EG R EF - 5f2 V-3 NUREG 0588 CAT. E QUALIFIED LIFE 4 d V r,5 i
TEST SEQUENCE (R: oa T-Io (BOO 03) )
- 1. 'Th er mal Aai ner 6.
- 2. MechAnieb binG a v 7.
- 3. AAciiation Anina 8.
- U y
- 4. 9 t e s m t e_ Aai n G 9.
- 5. Pnvicn_nrneotA TF54 10.
TEST ENVIRONMENT (R: ca i n CB00033 APPLICABLE O
)
I O ENV. ZONES TIME O .5hr .5- the 2-LLlhe ZM-25hr 2.Sh e -l(odap RAD s,L TEMP. 'F 250 2m+l20 750 M '2co 200 PRES. PSIG _ ?.5 75 -
io T/P i , 2. /2 R.H. in0 s OP. TIME DEMO l G el 3 S ACC/PERF D?.MO RADIATION AGING (R: n(1 % [@AOOb ) THERMAL AGING (R: ry? i- ('faccogYptrygg.rsl2))
i U Fd DOSE RATE I ( lO b RAD /HR AGED TO SIMULATED LIFE OF fl3 2. dap DOSE PRIOR TO ENV. TEST 2 X l0 7 RADS BASED ON AMBIENT DOSE DuRING
"" 'ON T Ew. EST RADS AGING TEMP./
TOTAL DOSE 2. x 1 # RADS ATION 1fo5 F / 20o ll99 8ks CYCLE AGING (R: en 4 -% (60003 ) ) REIo HUMIDIU iM %
5O
- IED CYCLES REQUIRED 55 0 O CYCLES PERFORMED [393 [ % 12-15 000553 d (Electro-Mechanical Equip. only) Equiv. %e d.f lO40C o brdined by _
C ro oOrfYon a nd ho-f hermal life tiGurs REVIEWER: Mrd [_/ l. b/A DATE: /2 /Hk/
R: Test Report Page No. Reference 7/1/81
ENVIRONMElfrAL QUALIFICATION
SUMMARY
NO. ? 3 2 -O /
SHOREHAM NUCLEAR POWER STATION-UNIT 1 (7 SPEC. TITLE S <w , o / Di e c 4 Vo /,> e s SPEC. NO. 1 3 P.O. 3/0697 VENDOR Ye/Og TESr IrEM DESC. Sciencid Va Qe.
MAxE A SC.O MODEL NP 9 3 3.0 A 18'1 E VENDOR TEST REPORT NO. AOS - 216 78/TA Reti A . uMe rescer 17'/ s't - / 2 ca.
~
APPLICABLE STANDARDS TEST REPORT NO. .731-O/
IEEE 323-/97'/ TEST METHCD dcg,@,1 fro [ Ie57!Anc/ys i s IEEE DOCUMENTATION ACCEPTABILITY Mct.cof o((e IEEE NUREG 0588 CAT. T QUALIFIED LIFE 1/0 yea s - c o s/ # e/osto,ner c.h O' n c e everY '1 veor)
TEST SEQUENCE (R: [ooe( 1-/ 3- 2 )
- 1.o$e l, n t. ffuncitan o l 6. h1, hen 1 h bioYocd
- 2. Thermal Aa rno 7. LOC /1 Si.n alo t r on
- 3. Ao dr a ho*1 8.
- 4. _ LUeor A o s a a 9.
a 10 4 S. Seism De+c<c asdc 11!te, S,mu/afron echh TvselVbratron re ,, End. c lrarc.
] TEST ENVIRONMENT (R: [ocj e. s '/4 '/ f and Eo #
2 noe.e
'f - 2 / ) APPLICABLE ENV. ZONES TIME 3 ##$ 3 e/M 3 av) 85 //C5 ' 2 6 D Y3 RAD 13 D (- H TEMP. *F 34G S W., 320 250 2. C0 PRES. PSIG //O // O 7f /5 /0 r/p i ,f 11_
R.H. l00 % OP. TIME DEMO /80 D VS Y ACC/PERF DEMO N/f9 - K Analy>. , (v 140 onY op 71rnt w .st it 6 R st'cr'r 17 f s, sf - / 2 cl. RADIATION AGING (R: D,,/,b ) THERMAL AGING (R: 83 + l , 9 - 3 9 't ) DOSE RATE .5/h0\nd . 8NC RAD /HR AGED TO SIMULATED l LIFE OF % dO_ YRS. DOSE PRIOR TO E!N. TEST 2.0 /3 / /0 f RADS DASED ON AMBIENT u, ne. U u@ fgG DOSE DURING TEMP OF 'T /04 'F EtN. TEST NonC. RADS
,f TOTAL DOSE 2.0/ 3 / /C 8
RADS DURATION )b8 [ / /2 00v5 CYCLE AGING (R: So c.c '/ - 3 ) NOT AGED-JUSTIFIED CYCLES REQUIRED 40000 BY ANALYSIS TO N!d YRS. CYCLES PERFORMED 'f d, 0 0 0 W See f.4/ fe/ /- o b . T/f er ma/ dj .n ce l (Electro-Mechanical Equip. only) f/,ia/y,,, ;c y /e flep; y /7 gf./R1jnp 2. REVIEWER:, 44 Tjfb DATE: N!/ J/ R: Test Report Page No. Reference 7/1/81 l 1 . .
l EINIRONMENTAL QUALIFICATION
SUMMARY
NO. 246-Ol l SHOREHAM NUCLEAR POWER STATION-UNIT 1 i SPEC. TITLE MtSCELLANG6l3 1*MNS70KmEAS ! SPEC. NO. 6M/-24hP.O. 3/673 7 VENDOR NMhMdOb TEST ITEM DESC. 480- /24/840V "73'AN5/DernEL MAKE //7A4M/677C.6 MODEL L-/26/Y VENDOR TEST REPORT NO. - No A/ F -- APPLICABLE STANDARDS TEST REPORT NO. -- NO A/6 - IEEE 32 R - / 97/ TEST METHOD IEEE DOCUMENTATION ACCEPTABILITY h/ IEEE NUREG 0588 CAT. IT. QUALIFIED LIFE AEE WVL6 4A/ALY5/5 /74f4-/27. TEST SEQUENCE (R: )
- 1. 6.
- 2. 7
+
3. 4. 5. O TEST ENV. Z JES PLICA i TIME D TEMP. 'F l / PRES. PSIG T/P / 2./ R.H. .
/
! OP. TIME DEMO F PERF DEMO .
, A - k RADIATION AGING (f ; ) THE ' Ab. R: d 4l.f. NA/4/ N b )
l (?q.fo4 /302-I DOSE RATE /HR AGED TO LATE" YRS. DOSE PR' R TO ENV. TF I RADS '3 ON AMB';NT
~ ,.. /o4 F fDOSED ENV. " ; RAD ~ ,
g ,7 U ! TOTA DOSE _ 9 nS CYCLE AGING (R: )
" ~
CYCLES REQUIRED BY ;.ALYSIS TO M YRS. O CYCLES PERFORMED (Electro-Mechanical Equip. orl, REVIEWER: M DATE:/2-/"8! R: Test Report Page No. Reference 7/1/81
l 1 ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 253-oI l SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE Motnc- Ocec/1+ed Carbo n Stee i Vellves C r~a+.C O' SPEC. NO. S H I - 253 P .O. 3 I 0512. VENDOR Yr*la A TEST ITEM DESC. Li mitora " oe MoV MAKE U rnNn r( 0 F MODE VENDOR TEST REPORd NO. b A O f5 3 4 bDo B(4CISM ' (n o n 3 7(n A6-O-M Aeliance Cl APPLICABLE STANDARDS N T REPORT NO. IEEE 9Z3-7l TEST METHOD MAi f e.nti a \ T<asti no r o IEEE -332- 73 DOCUMENTATION ACCEPTABILITY Ace <-otable.. See comments 4 A ner t a l e h net i +mris IEEE g g g g p , ,j y,g i NUREG 0588 CAT. 3I. __ QUALIFIED LIFE '> M O u r s TEST SEQUENCE (R: On 3-6 ((o oO37(o A )
- 1. ThFrmAlAdinA 6.
- 2. Mechanic [I A%na . U U 7.
- 3. bAdi2L+ inn Asi v nsv 8.
- 4. 8 Fi 9 m 'i P b u aI'l hic!l YI O n 9.
- 5. A CC 't Ole n-t- 8i mt Il A4 i on 10.
, TEST ENVIRONMENT (R:T~rAnKlin~1not4 NU49 beenett Fc3W / ) APPLICABLE b 9% 3-5 ENV. ZONES TIME o-% %-Ghr 6-Sb 9-12hr i 2.-13hr 13hr -Mew' RAD ft m , c -
TEMP. r sLt 0 % 340 %7A '42 N 2s2. E5i PRES. PSIG 105 %s los 77 19 15 TfP er. o _ <z z R.H. 100 % _ OP. TIME DEMO SO daVS ACC/PERF DEMO RADIATION AGING (R: nA 4 [ M A37[,M THERMAL AGING (R: nrtL S s fRnn59-oesin. fil) I d only tne motbestitor ocdf DOSE RATE l Y \O b RAD /HR AGED *.'O SIMULATED V LIFE OF N3 YRS. DOSE PRIOR TO ENV. TEST OH X. ) O b RADS BASED ON AMBIENT DOSE DURING TEMP OF l$R *F ENV. TEST - RADS AGING TEMP./
^ " i C! '
TOTAL DOSE B4 x I O'8 RADS CYCLE AGING (R: no %,4 (rooO3%AI) i o Ac.t e r NOT '.S"D-JUSTIFIED CYCLES REQUIRED 50 O BY ANALYSIS TO >4 A YRS. CYCLES PERFORfIED RO QUtv. age a+ 15'8"F is de.h cmioed (Electro-Mechanical Equip. only)
'Og pn so ct- rn 1 1[Q, p
REVIEWER- (W [/ ). M - DATE If R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 2@d '"Ob SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE lilUTOR OPERATEr> ( ARPDtd 6 TEEL sl0UJES SPEC. NO. M I-29 P.O. StO 61?- VENDOR N/ Es p.d TEST ITEM DESC. LirniYo ro o e M O\/ MAKE LimiYnrcUP MODEL SMB-O-25 Aeliance DCm class M ' VENDORTESTREPORT$0. 80o58 + Ano E - (6 moo 9 APPLICABLE STANDARDS ' TEST REPORT NO. IEEE - A 3 2_ '7 2. TEST METHOD % r iP f\-tIclk TCSYi06 IEEE - 323 ~4l DOCUMENTATION ACCEPTABILITY hraa" See Co m me r +s Anri sor c'Ot2 sa IEEE - pg n gg ; 9, g g3 3 g g g g g g y . g, NUREG 0588 CAT. T QUALIFIED LIFE > 4 O u r3 I TEST SEQUENCE (R:D._(n - 9 (60009) )
- 1. Ther rnAl Aa i ne; 6.
U
- 2. Merhan'iral Adl'na 7.
- 3. M (ilR'I*Lon Aa b " 8.
- 4. M $rnte Td hinS 9.
- s. Envi con rvie n t al Yest lo.
TEST EtNIRONMENT (R: nn,io [6ln o n b ) APPLICABLE IO ENV. ZONES TIME O-Ihr 1 'l h r E-4hr Li'.'4hr 'l -E5hr5 RAD L lC TEMP. *F 110M O 340 S36 'A i o E.i2 PRES. PSIG 0 ->(o2 (o8%n4 iOMo 9(oM o T/p s,e R.H. /OO % OP. TIME DEMO 26 h r3 ACC/PERF DEMO RADIATION AGING (R: on7 (&OOO _) THERMAL AGING (R: rvi. In + Ann'III. (800d) I C> DOSE RATE - RAD /HR MotoTOr SIMULATED AGED St@or Ont(0 LIFE OF i15 YRS. DOSE PRIOR TO EIN. TEST l V. l O RADS BASED ON AMBIENT DOSE DURING ENV. TEST - RADS AGING TEMP./ I TOTAL DOSE 1 EIM 4 RADS CYCLE AGING ih: m "J. ( R O O O 3) ) ra Actudier TB005% CYCLES REQ!iIRED 5OO Qg %]13-Ifg, CYCLES PERFORMED 200Y (Electro-Mechanical Equip only) Eque v. ge Cterived bu preportiO [ 0-g REVIEWER: ,
/ (/ l. , E DATE:l R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 289-OZ SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE W DROCaEM Re SPEC. NO. P.O. VENDOR TEST ITEM DESC.13m l' YA (Tit je. M OV r MAKE L.1miYOCOUc MODEL MOTO8+ ACTUATo6- SMB-0-45 MOTO85[ALONEl 2.M 40 h-/b S/det tg VENDOR TEST REPORT NO. BOO 58+ Apob- fMn03 ReIidnee.AC efm f3 lAr.LMorogr] APPLICABLE STANDARDS TEST REPORT NO. IEEE - % 2 - 1972 TEST METHOD 8 tant # F nt 1 A I T65TlYVT IEEE - Od3 - 197 l DOCUMENTATION ACCEPTABILITY Ace,-O+71Elv- ~ IEEE Me cnm rn e n+R .v snec t an ' ~ Mneli+1 Q n S - E G R E F - 532 V-3 NUREG 0588 CAT. 'E. QUALIFIED LIFE 2./f]Vr,5 i TEST SEQUENCE (R: OG 7-1O ( BOO 09 )
- 1. Therrat Aairva 6.
v v .
- 2. MechA nical Asina 7.
v v
- 3. AAriiation Ani -u _.
8. U ()
- 4. 9 i F M ryit ("_ An't nes 9.
- 5. I~ nvi r nn rne ntA Tr54 10.
"'EST ENVIRONMENT (R: on i n ( BOOO33 ) APPLICABLE I O ENV. ZONES TIME O .5hr .5- thr E-44hr ZN-25hr 15hr-l6dae RAD J l
TEMP. 'F 2.50 2.m+lzo 15 0 28;o 200 Zoo PRES. PSIG ?.5 75 - io T/P fs R.H. 1oO s OP. TIME DEMO l G el a S ACC/PEPE DEMO RADIATION AGING (R: n(1 R [MOOh ) THERMAL AGING (R: ryt '4 CRoco@fFfa58 rtl2l) / I U Fd DOSE RATE I i lO b RAD /HR AGED TO SIMULATED DOSE PRIOR TO LIFE OF fl31 _ ddp ENV. TEST 2. E I O I RADS DASED ON AMBIENT DOSE DURING RADS AGING TEMP./ 2,. E \ O * " #
- TOTAL DOSE RADS
" I" "U"IU
- I '
CYCLE AGING (R: m 4 -% (60003 ) ) 50 CYCLES REQUIRED MO O 4O
- 0. CYCLES PERFORMED .7993 (Electro-Mechanical Equip, only)
B S Lq i2-is ocess3 Equi v. %e at IO40R o bf-dined by. YRS. p ro perf T6nma Eo-f hermal life +'lGurs REVIEWER: /M [lI b>A DATE:
/2 ${k/
R: Test Report Page No. Reference __ 7 /1/_81__ __,
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 2 %-03 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE M nt nt- Onererted CM-bon SYect ValvCS SPEC. NO.SH i -253 P.O. 3105 t 2_ VENDOR Veliln EST ITEM DESC. l.drh i Yn rt'ir Je. M OV r MODEL MOTc6tPCTUATC6 SMS-0-45 MAKE L.1 m i 4 O F Q U e. MOT,085 [Al.ONEl 2.M 40 #-/b stdet tg VENDOR TEST REPORT NO.80058+ Apob- BMO3 8eItdnce.AC cfm 8 TALLMoN3J APPLICABLE STANDARDS TEST REPORT NO. IEEE - @ 2 - l972 TEST METHOD cf*OrrFnt1A1 76 Mi/VT IEEE - 323 - t 971 DOCUMENTATION ACCEPTABILITY Acreot/ idle _ cse enm me nk - moec iat ' ~ IEEE (9 net i+t a n s - EG R ET:- M V-3 NUPEG 0588 CAT. E QUALIFIED LIFE 40 Vr-3 i TEST SEQUENCE (R: oa T -I o (60009 )
- 1. Th erma1 AairYT '
6.
- 2. M e ch A ni cNI Asina v v 7.
- 3. AActiahon Asina 8.
o y
- 4. S I P s m'n c An't n G 9.
- 5. P nvi r nn rne ntA TFS4 10.
TEST EINIRONMENT (R: OG ) n (6O003) ) APPLICABLE O io ENv. ZONES TIME O .5hr .5- the 2-44hr ZN-25hr E5hr - l(odavs RAD a. t, r i TEMP. *F 250 2m+120 760 N -foo 200 PRES. PSIG 25 -
'25 -
iO T/P L /m '8 R.H. In0 s OP. TIME DEMO l A el A S ACC/PERF DEMO ,, RADIATION AGING (R: nri R [MOOh ) THERMAL ?.uING (R: yr_( cccMF#68-nl2l) DOSE RATE I ( l C)IO RAD /HR AGED TO SIMULATED LIFE OF dl3 2. ddp DOSE PRIOR TO EIN. TEST 2 X lO I RADS BASED ON AMBIENT DOSE DURING l ENV. TEST RADS _j TOTAL DOSE 2.X\O~Y RADS A N 1fo5 F / 20o fI99.835s CYCLE AGING (R: fv? 4 -% (60003 ) ) REL. M M iM % f nO l CYCLES REQUIRED 50 O B 4O YRS. CYCLES PERFORMED _/393 _ I.q 12-l'5 ecC5iis] (,/ (Electro-Mechanical Equip. only) Equi v. qe M IO40P o bfAW D. O rO O Orf To n fr16 ho-f hccm81 lite tlGur6 REVIEWER: Ed [d /A DATE:
/2%[/
R: Test Report Page No. Reference 7/1/81
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. 2%-O1 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE OMd Dl M SPEC. NO.Ml-[bP.O. BIO 556vENwR BURLO W.CaE. C_o . TEST ITEM DESC. N\ \ t- + MOTOR M T I M Cs MAxz WESTI UG RooSE. MODEL $%E %ET VENDOR TEST REPORT NO. DO- 1% F APPLICABLE STANDARDS TEST REPORT NO. TIk - 2.7(o -O i IEEE bhb ~~ k TEST METHOD MbMIl bk IEEE Mh' DOCUMENTATION ACCEPTABILITY k1CC.@AU IEEE 334 ~ k 7h-NUREG 0588 CAT. TFFF QUALIFIED LIFE M VEARS ul/
\\7 - 19 '7 4 BE.MR ud6 +LN BE mMM_
TEST SEQUENCE (R: hb %)
)
- 1. StStf\t.C. (C_ALC ). 6. DDE '\t ST"
- 2. F Ac_TnRv h5T5 7. ELEc_.. nusot. ATiou TEST-
- 3. THE.Rn\it A6i k)G 8. FNAL rkisFEcrioLJ
- 4. TRR Apt Am ohJ 9.
- 5. M kit e. A \ Mi% 10.
p' TEST EINIRONMENT (R: kpb hCA h ) APPLICABLE v
' O ENV. ZONES TIME M Dbbb RAD L.
TEMP. 'F 2 ' PRES. PSIG 3.3 TfP o g_ R.H. LOO s OP.T[MEDEMO AO DAY.5 ACC/PERF DEMO RADIATION AGING (R: k% G 3 ) THERMAL AGING (R: Pe 5 ) G' DOSE RATE RAD /HR AGED TO SIMULATED LIFE OF YRS. DOSE PRIOR TO EIN . TEST RADS BASED ON AMBIENT DOSE DURING ENV. TEST - RADS
^"
TOTAL DOSE \%1O e RADS
= " " " ' 4to% iMogas CYCLE AGING (R: ) " ^ ~
CYCLES REQUIRED . p . BY ANALYSIS TO _ YRS. Q CYCLES PERFORMED (Electro-Mechanical Equip. .
/ O ' .I ,
RE?IEWER: 1 DATE: R: Test Report Page No. Reference 7/1/81
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. 2.89-o1 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE Hyrirnne n Aerom b ine r Un'i +s f]
./ SPEC. NO.SH1- 29P.Olaio/cz4 VENDOR 6 oc.M w II TEST ITEM DESC. Li mitora oe M OV MAKE Li mH-n rn U F MODEd4CNM fh- O-f 6 bel }&nCE (SOS Sh VENDORTESTREPORYNO. A A n E5 9 4 4oo 8' 6On376 A APPLICABLE STANDARDS '/E'ST REPORT NO.
IEEE - 9Z3- 7.l TEST METHOD Noni fe_ntiell ToSti ()G r o IEEE - SS 2 - 73 DOCUMENTATION ACCEPTABILITY Areeatable See comments -+ sner ta l c hnetittens IEEE p g gg g, ggy,g i NUREG 0588 CAT. IT. QUALIFIED LIFE '> 4 O u r S TEST SEQUENCE (R: On 3-5 ((noo3 IcosAl ) ,
- 1. Thermal 4(iinn 6.
- 2. Mec'r,a n i cYl A9sina 7.
. U V
- 3. Aaelia+ inn Acai v na v 8.
- 4. Sei9 mic (cualieea+ ion 9.
- s. A ccJi ole n+ Si mo ta-h on 10.
h TEST EtNIRONMENT (R: Franklin InA-M4ufe 'AeoncttFc3441 ) APPLICABLE V 9% 3-5 ENV. ZONES TIME o-% 'A- Ghr G-Skr 9-lZhr t 1-IShe 13hr -30ek' RAD 4 TEMP. r SLt 0 Coo, 340 '62A A2tW252, Z51 PRES. PSIG 105 % tos 77 19 s5 TfP is R.H. 100 t OP. TIME DEMO SO da ACC/PERF DEMO l RADIATION AGING (R: ng 4 [f4/\3MM THERMAL AGING (R: nn 3 1 IRonSS-on In . I13) DOSE RATE l Y \O b I d Ont the mothr%tIitor AGED i SIMULATED l RAD /HR l LIFE OF N3 YRS. DOSE PRIOR TO EtN . TEST 104 x. ) O' RADS BASED ON AMBIENT DOSE DURING EIN. TEST RADS AGING TEMP./ TOTAL DOSE EOM K lOb RADS CYCLE AGING (R: no 14 (fooO3%AT) i o Ac.tuo. tor + ' h" ' NOT '.S:J-JUSTIFIED CYCLES REQUIRED 50 0 BY ANALYSIS TO >N O YRS. I CYCLES PERFORMED ROO QUtv. age aF 158 F is de.termined j (Electro-Mechanical Equip. only) Ct On to C rnd\ life REVIEWER- (gf [/ ). ML DATE: f 5' I / R: Test Report Page No. Reference 7/1/81 l
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 289.OZ SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE WDROGEO Rcoryse>lNN ON1T5 V SPEC. NO.MI-2f$c) P .O.31 O(o 2 4- VENDOR ATOrniC6 T6JTERtdCoso@L ( RocicNEE.LL') TEST ITEM DESC. Idrn l' YA rdt je. M OV r MAKE L). m I Y O rQ (J e. MODEL MOTO6tACTUATC6 SMB 0-[75 VENDOR TEST REPORT NO.80058+ Apob- RonO3 MOTORS Rett dnee WONET
.AC erm M4 % fMoruJJ G tau -/b #M %
APPLICABLE STANDARDS TEST REPORT NO. ' IEEE - __g9 2 - 1972 TEST METHOD evn,,enti a 1 Te.svi vvr IEEE - bd3 - IOY ! DOCUMENTATION ACCF TABILITY A< et otadre _
%=e c n m m e A fs -.- 90ee i a t
- IEEE '
O net i+i o n s - EG H E.F - SR V-3 NUREG 0588 CAT. E QUALIFIED LIFE 4/d Vr3 i TEST SEQUENCE (R: oa 1-1 O (BOO 03) )
- 1. ~Th e r ma_l Aairvt '
s.
- 2. MechA niceD Asina v si 7.
- 3. AAciiatton Anina 8.
U (J
- 4. 9 i F_ s m 'n c A n 't n a 9.
- 5. F_ n v i e n n m e n i a Te54 10.
! vf) TEST EINIRONMENT (R: ca i n C BO0033 ) APPLICABLE io ENv. ZONES l TIME O .5hr .5- the 2-Othe 2N-E5hc E5he-l(odap RAD sf TEMP. *F MO EM+f20 7.50 28;A-foO 200 PRES. PSIG E5 - 75 - 10 T/P fs R.H. InO _ OP. TIME DEMO l A el a S ACC/PERF DEMO i RADIATION AGING (R: AAE [@AOOh ) THERMAL AGING (R: rvt*4 (BOOOM[F&68 M2l) i y Ed ' DOSE RATE ! t lO b RAD /HR AGED TO SIMUIATED LIFE OF 131 ddp DOSE PRIOR TO EIN . TEST 2 X 10 ? RADS BASED ON AMBIENT DOSE DURING EW. TEST RADS AGING TEMP./ TOTAL DOSE 1X\O RADS
** ""IU " I '
CYCLE AGING (R: m ~.I. ~% (60003 ) ) i 0 CYCLES REQUIRED 50 O B S O YRS. CYCLES PERFORMED _/393 12.- 15 6005f5] (Electro-Mechanical Equip. only) Equi v. qe M 104 C o bfMoed b,y O ro p orf Ton fr16 60-f hccm81 lifc tlGUrs REVIEWER: fM [_lI 1A DATE: /2 // / R: Test Report Page No. Reference 7/1/81
EINIRONMENTAL QUALIFICATION
SUMMARY
NO.888- 03 SHOREHAM NUCLEAR POWER STATION-UNIT 1
~ SPEC. TITLE Huc/rogen Recom8/ner*
SPEC.NO.h$ P O.blOSEN VENDOR Refia.nce Efectric. Compants TEST ITEM DESC. 86Cdm 8/ne/~ 080LVe/~ /72ddo/~S MANE Reeia.nce Electn'c. ComwssODEL 324 Y VENDOR TEST REPORT No.StS50.nce 'Electnc. compant/ Report Af JVM -J? APPLICABLE STANDARDS TEST REPORT 'NO.//777/L* dred./d. AO/edt F84%7M3 500 #l0l /f IEEE TEST METHOD $ta.nc/Afd %Q ihCQfl0M Ie3b IEEE 3 3 k " /.8 7k DOCUMENTATION ACCEPTABILITY /77ust 8e u5ed in conia.nction with Regia nce 3 y _ ,g g recort No. Nuc-3 NUREG 0588 CAT. QU5LIFIED LIFE //d (/Bd,f3 TEST SEQUENCE (R: [, P(1.Q8 3 "// )
- 1. Therma 8 Aging s. LOCA Te.st
- 2. Mecha.nica.$ Nein9 7. L/isua.8 /nspe.chion
- 3. Ra.dia, tion A$ini 8. Post Locs load c<ictine Test
- a. Se isenic 'Tes" tin 9 9. Fina.l. Inspection "
- 5. 2Q.OllQ blon Ex'toos"ett e. 10.
TEST E?NIRONMENT (R: / . /SQ.48 /O, /k O ' "
) APPLICABLE ENV. ZONES TIME 3d(175n. 2l//77th $2HQUr3 (6 DQ.ys pgg -f' TEMP. *F 295 3/o BSO 200 PRES. PSIG 70 7O O [N T/P /6 R.H. /dC \ SCBAns/Chemica.8 3)OrG.y OP. TIME DEMO 3d 04.L,6 ACC/PERF DEMO M/A RADIATION AGING (R: [ Da,Q8, [ ) THERMAL AGING (R: [ , pa.ee 5. Ep.3 )
g u / DOSE RATE ///d RAD /HR AGED TO SIMULATED LIFE OF 6eca. der dhdM YRS. DOSE EIN. TEST PRIOR'20 [.O Y / / g RADS DASED ON AMBIENT DOSE DURINC E?N. TEST RADS , p TOTAL DOSE 8. Ok / /O RADS CYCLE AGING (R: , MG.,l/6 /[ ) NTA TIFIED CYCLES REQUIRED _~ BY ANALYSIS TO M/d YRS.
/O08 O CYCLES PERFORMED (Electro-Mechanical Equip. only)
REVIEWER: /N' h f/tY DATE:/- 6 Y 2. R: Test Report Page No. Reference 7/1/81
)
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 310-01 SHOREHAM NUCLEAR POWER STATION-UNIT 1 Q SPEC. TITLE Elec.+ rie. (Co-for Opero+eci Con trol Valves O SPEC. NO. 3/O P.O. 3/073(o VENDOR FO 4 er Confro/s TEST ITEM DESC. El et-f r ic_ YY)n+0r Doerafed llalve A e /va $Or* MAEz l-loco ld Bec.k a n d Sons MODEL I4 - / O I - 0 2 3 C 45 VENDOR TEST REPORT NO. Mof 455foned APPLICABLE STANDARDS TEST REPORT NO. 3/O O/ IEEE 982-/9'79 TEST METHOD 8eauenfio/ [cr/ IEEE 32S-/97'/ DOCUMENTATION ACCEPTABILITY Not Acceofod/c, IEEE NUREG 0588 CAT. N/A QUALIFIED LIFE Nc. P fs-f o d /64ed TEST SEQUENCE (R: [o n e- /2 ~7 )
- 1. & ec anicaf kaina v s 6.
- 2. JQadio ffon A n in a 7.
- 3. fune /fon o / fett 8.
- 4. $e. is es ir_ Ta= < f- 9.
- 5. 10.
TEST EINIRONMENT (R: No f- ker[vw?ed APPLICABLE O
)
5 ENV. ZONES TIME RAD G. N. R. N TEMP. *F PRES. PSIG T/P / . 3 ff / b _ R.H. Net /) aM<e_s , e d3 19.6o OP. TIME DEMO Mone ACC/PERP DEMO N!A RADIATION AGING (R: Affac/1 / ' /o Wy/c ) THERMAL AGING (R: (dv/e. Mecoef /7V('/ /8/03 Refort 12V4M-ll/02 Sec.f oon '3. 0 DOSE RATE / Y/O RAD /HR AGED TO SIMULATED LIFE OF /Y h YRS. DOSE PRIOR TO EtW. TEST / A RADS DASED ON AMBIENT DOSE DURING E!N. TEST N!d PADS _j
% / no ' hr UR 0"'d DURATION O/O TOTAL DOSE 2,2 wo# [or remqgp1 RADS jCYCLEAGING (R: Page /2 -7 ) " HM TY Not /9ddresJed %
CYCLES Pa, QUIRED 500 """"" BY ANALYSIS O )4o YRS. CYCLES VERFORMED /G,588 (Electro-Mechanical Equip. on1y) $ Therma l f)9i en o[/ mayerio/S n9 daio nof 000ilo blc REVIEWER: Uw__ __ .d MW DATE: 1 !'/ 2.-- E: Test Report Page No. Reference 7/1/01
ENVIRONMENTAL QUALIFICATION SUI 94ARY NO. 3/8- O / SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE _ Ase 0Dera-+ed Cmhcl Value s SPEC. NO. 3/8 P.O.3/07 lf VENDOR Ccoes Ya/ro.o TEST ITEM DESC. 80/e n OiM Yu [L/ C. MAKE ASCO MODEL NP &320 A134 E VENDOR TEST REPORT NO. AOS- 21678/TR Rev A . UMe reporv /71164-12 o 2 APPLICABLE STANDARDS TEST REP' ORT'NO. 2 3 2.- O / IEEE S 2 3 - /9 7'/ TEST METHOD .Secuenfio/ Test /Ano/vsis IEEE DOCUMENTATION ACCEPTABILITY Acceofohe IEEE NUREG 0588 CAT. T QUALIFIED LIFE 40 vents - co j/ + elo.shner c.h 'on a e e ver Y '1f year) TEST SEQUENCE (R: 000e< 3-/ 3- 2 ) 1? Base line /func+ ion a I s._6giden1 RadicHon
- 2. Thermol A Q in a ?. LOCR Sirnulotion
- 3. Aodia fiort 8.
- 4. _ U/ ear A o in o 9.
- 5. Setsmic S;$ulaiton/v,L<ation Enc]. 10.
Y Oehre and Affer ecch T#c Tes1 D 10!c TEST ENVIRONMENT (R: 8on,< t/ '/ _ L1 f and so 2 ooor 4-21 APPLICABLE O ' s ' '
)
ENv. ZONES TIMc S //#5 l 3 /MS 3 NPS 85 NPS ' 2 (, D K5 RAn 6 N K ' TEMP. *F 3'/G 3 6/(, 12O ISO 200 PRES. PSIG //O //O 73- /6 10 T/P / . 3 7 /f /f R.H. /OO s OP. TIME DEMO /B0 D W W ACC/PERP DEMO N/A
% Analy. sis for /so ony OR T!rnE IN WKG" QEPoA'T (74 6 4-/ 2OL RADIATION AGING (R: /0, ,7#,,d b ) THERMAL AGING (R:kovs '1-l,9-39'1/
f ) DOSE RATE .5///OL and .8X/O , RAD /HR C AGED TO SIMULATED LIFE OF M 8[ YRS. DOSE PRIOR TO p ENV. TEST 2.0/3 / /O SC3 BASED ON AMBIENT DOSE DURING ENV. TEST h/oaC RADS
,j TOTAL DOSE 2.0/ 3 e /o # RADS D"IN 2M F / /2 % s CYCLE AGING (R: [ooe 44 - 3 ) . c ok %
NOT AGED-JUSTIFIED CYCLES REQUIRED L fd 000 i BY ANALYSIS TO M/d
/
YRS. CYCLES PERFORMED 40,000 $ See U/y/c Lo b. Thermo/ Ag in g Q (Electro-Mechanical Equip. only) f],1o/y3 S , thy /e gcfort /7%y. /jolgoce 2. REVIEWER: A DATE: 8!/8
i ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 3 /33 - 0 2. SHOREHAM NUCLEAR POWER STATICN-UNIT 1 SPEC. TITLE Aor Opero $c=d (on trol ValJe S SPEC. NO. S/.i P.O. 3/O 737 VENDOR C_coc- s //a/ coa TEST ITEM DESC. 8c/cna id Yo f(/c"_ MAKE bb MODEL M //f )db-3OO 'OM b __ VENDOR TEST REPORT NO. /)CS 2/l>78/TM /de.r 4 Wy/c Meoor15 / 7Yl='/* Ob d /7Yb'/' obc'2 APPLICABLE STANDARDS TEST ' REPORT NO. ,13 2 - O/ IEEE 32 P / 974' TEST METHOD Scoden t/o / Iesf //2na//Sr i + IEEE DOCUMENTATION ACCEPTABILITY /2C/ceto /r* IEEE NUREG 0588 CAT. J QUALIFIED LIFE 40 gean .cc ,/ #e /us /c m er ch'ance everv 4 veOn
)
, TEST SEQUENCE (R: Foges } * / . 3- 2. 1.* Ba se. I,n e /Func.fion a l 6. Acc.nlen f- Aado a f oo*1
- 2. Therma i Aa"una" 7. LOC A S.ma lo tion
- 3. kodr o foon 8.
- 4. Wea r- Aoina s a 9.
- 5. Sen,nac $,mulabo*r/L! ,bration End- O.
4 Behre and of ter ecc), Tvne. Test . o se.
/ TEST EINIRONMENT (R: [coes L/ l/ Y-f and Eso 2'nocc_ l-/-2 / ) APPLICABLE ' " ' ENV. ZONES TIME 3Ne5 3//PS 3 // # S SJ /IPs 2 6 D y3 RAD G TEMP. 'F 3'//, 34G 320 25D 200 PRES. PSIG // O //O 78' /8 /0 T/P 1,6./1 R.H. /00 s OP. TIME DEMO /dD OY.$ % ACC/PERF DEMO N!//
' % /)naly m (ce /!c Dov Oc yo.ne on Ulvle Aescer 1744:4-LLC) RADIATION AGING (R: oN nd *[ ) THERMAL AGING (R: Osce 3 4-k i'3 i'Y ) DOSE RATE ,.7/ 7/c a,n/ , 8 7/ O ' RAD /HR AGED TO SIMULATED LIFE OF i 88 YRS. DOSE PRIOR TO ENV. TEST 2,C/Ie/D # RADS DASED ON AMBIENT M OF U /O *F DOSE DURING EIN . TEST Morica RADS AGING TEMP./ TOTAL DOSE 2,vr D e/0 RADS DURATION kbdi"~/ /1 Ouvs REL. HUMID M Unc M fm h([ g CYCLE AGING (R: [ogc 4/-3 ) CYCLES REQUIRED '/ O. 0 0 0 ((U S F 8ce. W /c /Q6 Therma l /]g n a
/\l//f YRS. [
O CYCLES PERFORME9 NO C00
/}ncly >Q (U /
V (Electro-Mechanical Equip. only) 7 /e regcf /~7'/I)/-0(ovIgoge 1 REVIEWER: <^ l- 4d DATE: 2!/// / R: Test Report Page No. Reference 7/1/81 N -, - - , - - .
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 3$ -C/{ SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE AUTomA ric. TEMPERATURE (_OMTROL 6YbTEMS FDR WAC. SPEC. NO. Ml ~3\9 P.O. 310738 VENDOR M C.C. PONMERS TEST ITEM DESC. 6EE ATTACH MEL3T
- l MAxz 6EE ATTACMME:k3T #l MODEL 6E6 bub (MN VENDOR TEST REPORT NO. WYLE
- 44540-1 APPLICABLE STANDARDS TEST REPORT NO. TR - 5W -OI f
IEEE 38- NU! i !kN TEST METHOD DE MY f IEEE DOCUMENTATION ACCEPTABILITY 6 6 E. ATTAC.H M E MT- dl IEEE NUREG 0588 CAT. 6EE tGTA/PMEUT*l QUALIFIED LIFE 6 EI=_ AT. TACHMEhJT
- l TEST SEQUENCE (R: ECNo.bd, ,
V, V ( ) o '
- l. IMTITAL FUMCT100 WST 6. %smic TEST
- 2. 6ERVICE CONDITICM 6f motATiodt Adl$ 7. %T6Eistnic CPERATraJAL G MECM
- 3. OST A6Ius, OveRAT,ce,At CME'ck 8. 6 MOLATED '%r AccitfUT Cc*JbPCOS
- 4. NAnt ATied Ey Pbso seE 9. NO AL FUf0CT700 AL " TEST ~
- 5. %r RAcipou CPERATicOAL Cpecg 10.
TEST ENVIRONMENT (R: MTIOM M ll( - I ) APPLICABLE ENV. ZONES TIME N I DAT 9DATS IM 7Ob M RAD TEMP. *F V70 127. 12 2 200 12.?- PRES. PSIG 1 O o l O 7jp R.H. % 10 0 90 60 l00 60 OP. TIME DEMO '722. 14 R $ ACC/PERF DEMO 6EE ATTAt.HMENT S t RADIATION AGING (R: 6EC.T IM -l ) THERMAL AGING (R: bE fTlOM U-l ) DOSE RATE 1000 RAD /HR AGED TO SIMULATED LIFE OF 59Rs 'IHERmRL,'5TR5 OPER.-TwtcE DOSE PRIOR TO 7 to @RS WA ENV. TEST I K 10 RADS DASED ON AMBIENT DOSE DURING _,,,,, AGING TEMP./ TOTAL DOSE 1 'AIO RADS uRATION @oF/ GM % CYCLE AGING (R: 6ECTl0M ll- I(o ,ll ) S IE CYCLES REQUIRED N OT kDORESf5ED '[ p CYCLES PERFORMED NE kTTACHMEUT#l ( (Electro-Mechanical Equip, only) REVIEWER: # DATE: R: Test Report Page No. Reference 7/1/81
3 (V ATTACHinEMT #l To EGS5 .31">-01 '//E//#/ A TEsr rrEm : DWiER IMSTRUrnEGE IMC / # //o 87-l Nor GUAuf1ED/ MInH OtFFERENT/AL PRESSURE EXCEEDED A LLNJ A8LE Lim iT- AFTER ComPLE.TicM oF TESTA M5 QUAL. LIFE
- 4. Acc.ogpc_Y PER FoRrnAuc.E Nor McMSTRATEC)/ dTdLED 7400 Times / ouAtlFlED UFE AT 104. F NoT VETERmlAJEb
- 3. TEST _L. t t:M: AIR m0NITOR. GORP [VAllDYME)/VELTROAJ 809 NOT QOALIFIED / DOR. A]G, DBA TEST u3l Re l AJ50LAT70A3 FALLEb[ QOAL LIFE $ Acc.OR.Act PERFOR.MAMcE.
(V~) Mar tremousreATen/ c.7cten 7400 TIMES / QUAL U FE. AT 104 F NOT DETERtotMED
- c. rest rTEm : RAYmOMD CCMTROL_ 6/ stems / M ASR - %4-)
rot QontiaED/ FAtLED AFTER. THERMAL A(aiOG AMD comu4 cYc.tE AGiuG / QUAL LtFE_ 4 Accuracy PERFORmA9ce. mot DEmoOSTRATED/ GYcutJC7 (MComPLETEf QORL. LIFE AT lof F MOT DET. ERmiUED D. TEST LTEM ' c_.s.MTERUME. / 32.0% -G Q UALIFIED / To tdOREG C_AT T [ QO ALI FIED LIFE O e seaas vex ni ncsen tovte asecar 17464 -tcoz/ A C C. PERC NOT APPucAELE/cYct.so 79eo umes/ T9ERmat Acmuc, ANAt3ss Peg uyYLE. REPORT 174/o4-I oot.
ATTAcHmeur # l1D Eass = sic)-o I E_ . TE.sT ITEM: Mc.c. Pou)ER.s / .3 61 - 2 % 2. QOhttFtED / NUREdr CAT I [ QU Alt FIED (5 YEARS FER. Wyte REPORT 174(o4 -0402. /' A C CPERF: NoT REa'D / c.vc.tto 7400 we.s/ nu=emmt. AcaiM6 AMM.YSIS FER LOYLE REPORT Fl4(of-0402. F. TE6T rrem : AscD / W TRK'X 832.08 )E 6EE EQss 3\9 - O ~6 (.QUALIFIEB) O 4. xssr rrsm: wsmco/ es,so MOT QU ALtFlED , .6 E E EQ% 319 O
e E NIRO!!MEliTAL CUALIFICATIGli SUlt*1J.Y !!O. Ol /-Od SHOPIHAM NUCLEAR POWER STATIT*J-U:!IT I 4/1/81 l SPEC. TITLE0 [4 Yn T%n fe ndrol 9 2 dem C e e Pf\l M I SPEC. 110. $M/-?/9 P.O. V/077h VENDOR MC 9e t v e (*S TEST ITEM DESC. O n vn 0 Rf- /k e ')'r in to v-MArz T T T a> na co ) ('e n+ cc k MCDEL NH9i APPLICABIE STANDARDS TEST PIPO2T NO. 7 7 7-$d, O/O- A IEEE s]J 3 - 7/ TEST METHOD IEEE 3W-76 DOCUMENTA~ICN ACCEPTA3ILI*Y IEEE UUREG 0568 CAT. T. QUALIFIED I.IFE 10 vrq TEST SEQUENCE (R: 04. rte. J 8T ) 4
- 1. % kJ %n a nd Rwevex1 Tc c1 6. %n I n- o . +-Lch c..ses t To. -r
- 2. Rar u.c e ce NA . % m u k%s n %,,,o 7.
- 3
- 3. T, end m t,cn % .- + 8. ( Fi m e t , e m i Tut m < cc e b vret(
- 4. % , e m i c_ V, brn+ie n Te 8 9. <t 4 Mc .),- eh 't r 3 Y ')
- 5. S , ut, A tv l LccA cnid. Tc4T 10.
TEST E!NIRONME!!T (R: A ne. T I APPLICABLE E:n. zcNES fi Ac2[ 2cyte-gc, g ;q3_w, - Tus 30c6vs /C0 detv3 TEMP. *F /c22 8 _ /f0 #F -
~ ~ ~ ~
PRES. PSIG //C I C'CtdfC S S CJ , , ,
/c. R.H M3 75' % - - - -
CP. TIME DEMO , ACC/PERP DE210 RADIATION AGING (R: A Mc 3 ) THEPMAL A~-ING (R: Os e t C- 'i ) DCSE RATE /. [f X/O RAD /HR AGED TC 3DIULATED LIFE CF / (' YRS. DOSE PRICR TO EIN. TEST / X /0 RADS BASED CN A'IBIENT DOSE DURING E!N. TEST C RADS AGING TE'9./ DURATION /86Y/ /dCcb d TOTAL DOSE V x /O RADS L' ' '~'
- CYCLE AG!NG (R: 04 nc '3 )
^
CYC*IS REQUIRED BY ANALYSI3 TO YRS. 07 ".E5 PERFORMED [ 7 JIIed
' Electro-Mechanical Equip. or.ly)
SIVIEWER: Ch . 4 DATE: '/V74 i R Test Report Page No. Reference
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. 319-03 t SHOREHAM trJCLEAR PC'4ER STATION-UNIT 1 SPEC. TITLE AUTO TEMPERATURE C00 TROL 6YGM6 FOR RVAC G SPEC. NO. 6Ml ~319 P.O. 310738 VENDOR Me.c. RWE.6 TEST ITEM DESC. M LENOID V ALY E MAxE Asc.O MODEt vdTKW 8320 A 89 E VENDOR TEST REPORT NO. AGS -21(o78/TR REV A. , \MVLE. RFORT G464-1202. APPLICABLE STANDARDS TEST REPORT NO. 2 '3 2 - O I IEEE 323- 19 % TEST METHOD MGUE.WlAL TEST /AMALV5:5 IEEE DOCUMENTATION ACCEPTABILITY AcfflTAE IEEE NUREG 0588 CAT. 1 QUALIFIED LIFE 40 VEARS - 4.uALX5E. cot t 4- t:LLASTornE.R @ 4 NE A R t NTERVAl TEST SEQUENCE (R: C#\ C.S 3-l , 3-2 )
- 1. IBASEllNE / FWJCTIOMAL 6. ACaDEur RADIATico
- 2. ~ THERMAL A6i06 1. 1AcA 61 mULAT10tJ
- 3. R ADI ATiou 8.
- 4. WEAR A6106 9.
- 5. 6 E6mtG G mul AT100/VIBRAT10Mo.
4 EbEFORE -t- ANR E ACR TYPE ' TEST PHASE TEST E!NIRONMENT (R: M 4-h 4-5, FIG.2 Pm . 4 - 21 ) APeLICAst.E G V G EIN . ZONES TIME 3HR5 3H6 3HE ME &WS ago g, K TEMP. *F 3% 34(2 320 2.5 0 200 PRES. PSIG il 0 110 75 15 10 TfP s, e R.u. \oo s OP. TIME DEMO 70 MW ACC/PERF DEMO M/A RADIATION AGING (R: A d-2M , Mf D ) THERMAL AGING (R: ~! , b , 'k ) E DOSE RATE . 5 1 % 10 d S XIO RAD /HR AGEDTOSIMuLATEDh LIFE OF YRS. DOSE PRIOR TO h EtN. TEST .06 % to RADS oASED ON AMsIE"' 4 150 DOSE DURING EtN. TEST NjWE O mDS sczsc,s,., 260 1 2. DAYS TO'I AL DOSE '2.015 J0 8 uDS DuRArION / CYCLE AGING (R: N~5 ) CYCLES REQUIRED 40,000 NOT AGED-JUSTIFIED BY ANALYSIS TO
/ /[ YRS.
CYCI.ES PERFOPJtED 4 0,000 y see ma us Tscema Asoc, O (Electro-Mechanical Equip. only) y REVIEWER: N DATE:
~
R: Test Report Page No. Reference 7/1/81
EHVIRONMENTALQUALIFICATION
SUMMARY
NO.344-O/ Rev / SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE Primorv Con +ain m en+ Gas Ana /v z er SPEC. NO. 3 N P.O. 3/0737 VENDOR Comf /c [nc,.. TEST ITEM DESC. Nydrooen , Ana /v 2 er" N. fem MAKE C. oms /s O /td/ MODEL k -lE" 8ev. / .Se of /98/ VENDOR TEST REPORT NO. 8roveed
~ /015~- /
APPLICABLE STANDARDS TEST REPORT NO. 344-01 _ IEEE 32,3-/978/ TEST METHOD 8eQuen'/io/ IE.sY And/y3/f IEEE DOCUMENTATION ACCEPTABILITY Necrofa $/e , orovided deficleneles li.,+ o n haac- 1
'of 80REF 3W-01 are_ msidied '
NUREG 0588 CAT. l' QUALIFIED LIFE 8ee A~1f ac$menf / TEST SEQUENCE (R: Page 1 sec.fion 4./. / )
- 1. Insoecfion and anerafional Tett s. simulai ed Pad Accident Cond;+ ion
- 2. Th e/rma/ Aoina _
- 7. Final In_s,nor + ion and Goerationa/ Test
- 3. Metbanical Cyc/ina 8.
- 4. Irrodia tion 9. 'Elfuneltonal Te.rt were performed
- 5. Seismic. Vibration 10. after eacb fes-1)
. TEST Et4VIRONMENT (R: To((* F"- I Fo o e. Io9.Afler 2 Sec '/ ) APPLICABLE LOCr1 EN V. SaNp/e has En v.
- TIME 10 0 0>'S 915 f6 10 6 # #5 96 Of5 RAD J TEMP. 'F /50 300 2/O /67 PRES. PSIG O 70 8/O E 7/p ff. f g, R.H. 9 0 .T S' \
CP. TIME DEMO /eO DK5 # ACC/PERF DEMO / b // dco/c ._
$ Analysis l'o r Iso cey Op. time provided h %stp leder ,/u tv 20,19si~
RADIATION AGING (R: Ta &/e D 71T on 37 ) THEFMAL AGING (R: To8/e 0-1 co 19 ,
)
DOSE RATE <///O (49 h RAD /hR AGED TO SIMULATED LIFE OF .8e e OfYach I YRS. DOSE PRIOR TO ENV. TEST ///0 b f< ADS DASED ON AMBIENT DOSE DUPING ENV. TEST None RADS p TOTAL DOSE / Y/0 RADS L. H M cddre55ed %
- CYCLE AGING (R
- Tome DY pp 33 )
ST FIED CYCLES REQUIRED l/nde Yermin ed "LAE CYCLES PERFORMED 8ee A f/c;b 2_ C4 (Electro-Mechanical Equip. only) REVIEWER: L4- M/ DATE: /2 8/ R: Test Report Page No Reference 7/1/81
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. 3 A/k
- O/O SHOREHAM NUCLEAR POWER STATION-UNIT 1 C) SPEC. TITLE himary bo0Yoidrneof bof Noo/VZPf SPEC. NO. S W-0 / P.O. 3/0 73 7 VENDOR (om3 /o 1 _
TEST ITEM DESC. No forc f/(* MAKE he fia n r_ e_ MODEL Abl onel (Ell in sufo /io!) VENDOR TEST REPORT NO. A/L/C 9 APPLICABLE STANDARDS TEST REPORT NO. 3 W-O/A IEEE 323-/97Y TEST METHOD 7~voe Te.sf//Yno/vf/s I IEEE 134- /979 DOCUMENTATION ACCEPTABILITY [/re eo/a[h IEEE NUREG 0588 CAT. I QUALIFIED LIFE L/O vpart EST SEQUENCE (R: 8cc f fen f oones f e l, )
- 1. Ternperafure Goasure s.
- 2. [Dehnical t/ibr$ lion 7.
- 3. /Y)oic}ure Evoosure_ 8.
- a. v'oltoae dclks 9.
- 5. 10.
TEST EtNIRONMENT (R: 1.0C A Te,5 f /7o f r e o v ir e d O '
) APPLICABLE ENV. ZONES TIME RAD d TEMP. *F PRES. PSIG T/P If /(3 R.H. N /$ %
OP. TIME DEMO /AO Drey s ACC/PERF DEMO N!A RADIATION AGING (R: fec]fon I on ft/ ) THERMAL AGING (R: 8ec //On 2 ) DOSE RATE / //O RAD /HR AGED TO SIMULATED LIFE OF M YRS. DOSE PRIOR TO EIN. TEST M[d RADS BASED ON AMBIENT DOSE DURING TEMP OF __] N *F EIN. TEST A/ d pAv; AGING TEMP./ TOTAL DOSE 2 . Oy y/O RADS
- DURATION A/!/7 / A/!//
CYCLE AGING (R: Mof cer[or,eed )
~
CYCLES REQUIRED BY ANALYSIS TO N YRS. (] (j CYCLES PERFORMED (Electro-Mechanical Equip. only) REVIEWER: 4"[ t'k DATE: 1 3 [ R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 40[4 -O I SHOREHAM NUCLEAR POWER STATION-UNIT 1 b SPEC. TITLE Ei.ecTaoaic ranusmiTreas a RTb' . SPEC. NO. M1-406 P.O. 310113 VENDOR Roseenoe ur TEST ITEM DESC. 'T}A E > s > A E A W AiTTE R, MAKE 3c'4Ahm F MODEL 1683 3 de A,iE.5 ~6 VENDOR TEST REPORT NO. 10802.6 lo 8 0 2 (o ( 2 volumes 4 APPfbJDiCEES) APPLICABLE STANDARDS TEST REPORT NO. %b -OI IEEE 3N- k TEST METHOD 6EOLX~.NTf AL TEST IEEE sN- OY DOCUMENTATION ACCEPTABILITY b c EFrtwE IEEE NUREG 0588 CAT. ~I- QUALIFIED LIFE 3.')yGbs @ 104 F TEST SEQUENCE (R: Agpena;v T of 10802. (,, (%e,ot ?we aure # iso 2 )
- 1. Acc. ..dotnc <> TM Ven Ucabo<s 6. R a.<Aon Aum "
+ Anor mal
- 2. h.3, \/e r. b ea 4. h I c . A. 7. S e> ; s .m . t- K <0 ,w
- 3. A cc e l e rc. t e d kei No Th e> r ma l 8. bc'i6m't kh n 011 I e
- 4. kr.de mied A 1s S
~ Fu,3c4,'ona t 9. fle a,n / TEmpe r.;4cce T.a.
- 5. 2a se l, n c 6hetk 10. 709 k cri d i ett (he, . 44 J.1 h fytse d heu O TEST ENVIRONMENT (R: Vntemn T oh IOQO'2 (n ) APPLICABLE kj ENV. ZONES TIME 25 .5 m;n 8 Rc, \'7.5 sa 5 7 Hrs RAD (; .T TEMP. *F 318 Si8 295 PRES. PSIG '72 73 2.4 rfp i z_ 7 R.H. 10090 % iO' i6 OP. TIME DEMO ACC/PERF DEMO RADIATION AGING (R: PAS bmE8 ) THERMAL AGING (R: 9 33, SCPar1 10B04 DOSE RATE MnO b i x 10 RAD /HR AGED TO SIMULATED LIFE OF b YRS.
DOSE PRIOR TO r r ENV. TEST 2 610 r 4 2&o RADS DASED ON AMBIENT DOSE DURING TEMP OF I20 F EIN. TEST C RADS AGING TEMP./ . 7 Zhz sto %, 2 sBxto' RADS uRATION 203,,7 1;llo hrs TOTAL DOSE CYCLE AGING (R: 83 3 Z , bPistada_If ) " "" Y
- Mr r a w>a c.e
^
CYCLES REQUIRED - BY ANALYSIS TO YRS.
] CYCLES PERFORMED VO30 (Electro-Mechanical Equip. only) ~
REVIEWER: / Ml DATE: R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. h- Oh SilOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE ELEdTRo4iC TRAuc.1Y\iTrERS A4D RESiSTAucE Tuenperartoes n:rsre teR.5 SPEC. NO. 6HI-@lp P.O. 310 W 3 VENDOR NO6E.MOUul' TEST ITEM DESC. TREMURF NAW6m iTTER_ MAKE 'b4T MODEL ll62 , OUTPUT cnC[E VENDOR TEST REPORT NO. APPLICABLE STANDARDS TEST REPORT NO. 38019. 57020, ll7415 Rev3 IEEE Q2S -89l TEST METHOD bMhRMW TEST 5 [MLYSL6 IEEE 344 -ITIS DOCUMENTATION ACCEPTABILITY YG_6 - M ID 6EGh3EMT1 AL -REST m PPORT W6 IEEE _ gg NUREG 05M CAT. T QUALIFIED LIFE I NENR. 4.D MOS. TEST SEQUENCE (R: IEPARATE TEST *5 k(* mP E%iO oh lMlI3 (Adi Akio n on )
' RMT 6f605N %ar24
- 1. 3rtRff@l TF'5T- (Ae c r CEur) 6.
- 2. Lo'.M LENEL RADI ATtoO rE_6T 7.
- 3. 6)FPLEmEktTARY 'RACvAT10L1 TESTr a.
- 4. 9.
- 5. , 10.
TEST EINIRONMENT (R: R oi . 117 415 ) APPLICABLE O' 'G ' EIN. ZONES TIMEA .a Swan to m k lihoor_'?wuas 42.HcufJ MD TEMP. r & 35CfF 350VI 316% 3OFF 2So*F PRES. PSIG _t 60 GO j 70 %.+ 6 7/p R.H. 100 9o s OP. TIME DEMO ACC/PERP DEMO O.r75% Acc Anse.
%tTt V6 RADIATION AGING (R: R 9,% 22.d ) THERMAL AGING (R: INCLtJOED 10 PEAT / ) ~
c Accican m.sr DOSE RATE O.2 ho1.0 %)o RAD /HR AGED TO SIMUt.ATED.. s _ LIFE OF YRS. DOSE PRIOR TO EtN. TEST (p.) IIO Q RADS BASED ON AMBIENT o TEMP OF DOSE DURING _ AGING TEMP./
"I" '
TOTAL DOSE 6 .7 %10 RADS CYCLE AGING (R: Nh ) NOT AGED-JUSTIFIED -M-CYCLES REQUIRED BY ANALYSIS TO j g j CYCLES PERFORMED (Electro-Mechanical Equip only) M gg g g g p Eg-fl7Q-0902, REVIEWER: DATE:/ N R: Test Report Page No. Reference 7/1/81 j
EINIRONMENTAL QUALIFICATION
SUMMARY
NO. l./06 - 03 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE R TO ASsern88/6S J SPEC. NO. 406 P.O.3/0 773 VENDOR Rosernot <.nt /nc. TEST ITEM DESC. $6S/S$A.MCO 8mA87Q$Uf8 OB t&CZOf~ mar.E Rosemou.nr /nc. MODEL #8 --5/-5o VENDOR TEST REPORT NO. ROSemount teS t rmort A/o. 276 7 Rev.B APPLICABLE STANDARDS TEST REPORT NO. [7[ 7 Ped. d. IEEE bS3 ***lS?l TEST METHOD bGQuent/ 2 test Analysis. IEEE 383 ~~/O7'f DOCUMENTATION CCEI'TABILITY /72uSb [( USfo/ n nu t n With Wyft ftforl$ IEEE 3 W ~ lh ?j _. Afc /7%!T2/-/S0/ /S~C2. NUREG 0588 CAT. ~
// QUALIFIED LIFE 'l/ 78 v.[ 8 F/W T 3 )
G TEST SEQUENCE (R: / Bd.4e 8"/3) ) 1.Inidt>8 Inspection anol ca.fi&ta.tiary s.
- 2. hea n t m c2 /"22.0//t2.t/on 7.
- 3. $5Sn'?iC. Vi$/~tL.t/CM 8.
a.Stearn chemical exposure 9. 5.ftha8 Ihspt.ction And co.fi$nt&fo. TEST EtNIRONMENT (R: / Pd.48 8 -// ) APPLICABLE ENV. ZONES TIME 7 min. / 7rn/n 8 Hours Soyou/s Styourz ,,o _g . , , . y reMP. F 3!/0 34/0 30S 228 4m8/ent E: P PRES. PSIQ $$$ l$5 ?0 S$ WSlen$ T/P / 8 /5 /6 R.H. $0 % WO'*/U W' * " SYW IS'WOiA$ OP. TIME DEMO 80 #o4.4./'5 ACC/PERF DEMO I . d'/ O RADIATION AGING (R /,.00.08 8,. Appen/O) ,, THERMAL AGING (R: b _ Q. h
)
DOSE RATE /X/O RAD /HR AGED TO SIMULATED LIFE OF A YRS. DOSE PRIOR TO g EIN. TEST [X/o RADS BASED ON AMBIENT DOSE DURING EtN. TEST A RADS j J DURATION / TOTAL DOSE 8//O RADS CYCLE AGING (R: ) NOT AGED-JUSTIFIED CYCLES REQUIRED A//A BY ANALYSIS TO [$fonokuY Sit [6 - YRS. CYCLES PERFORMED /V/A gj gjg g jWg* hi (Electro-Mechanical Equip. only) G
, REVIEWER: -
M3SI DATE:[~8~80 R Test Report Page No. Reference 7/1/81
DNIDONMENTAL QUALIFICATION
SUMMARY
NO. [/O 7 -O/ SHOREHAM NUCLEAR POWER STATION-UNIT 1
/ SPEC. TITLE [6Ve 8 $ Witch SPEC. NO. ll0 7 P.O. /0 04'2 VENDOR Ma.aneti 0- 8 /n terna tiona &
TELT ITEM DESC. /ct/e8 $ WifC// MAKE Met.an e ti-ce /n terntti MODEt Est-Mpc -x-Mitt o c VENDOR TEST" REPORT No.Typs Test Ovqnun on fjaviaf htArt controfS/5/ift la&-) APPLICABLE STANDARDS TEST REPbRT NO./3838-/
/
IEEE .303 ~ /Sl&! TEST METHOD $2QUCMtlkl 7e~st Anttfysis IEEE 3 l'/V "/8[ DOCUMENTATION ACCEPTABILITY /7A/St [e FM in conjuncitbn with wute renortc, IEEE g 774 q,,,c,g, g, g g s i NUREG 0588 CAT. [ QUALIFIED LIFE 7 8 t/ca.r5 [ft/ 3) TEST SEQUENCE (R: /.8 O ) 1.Nuclea.r thdiation Oa.ma tye s. 7.S~)/z Mant /ntlu cr.cl lliA/2ttiev> Test.
=<
rest. 7. S es.sms c, Outt$s}/ cation.
- 2. Reare <rureshoed;s ion A na.fu.s e G 3.Basdhre fitnetional af Hva'itsdabi,8. Functienot Teht fotfowing
- 4. M u c fe.a.e $$$dn Aging. 9.
5.Ebstete of Tempern tur.a//fu Nicli&rl 10.
~
Cuete Atih9 [ TEST ENVIRONMENT (R: } APPLICABLE (,, ENV. ZONES TIME JVC lLCc.iden$ YC.S$~ tAla.$ )Cer/0/~h~ red- RAD G : H, TEMP. *F PRES. PSIG T/P C3.* /d '_* // R.H. % OP. TIME DEMO ACC/PERP DEMO i RADIATION AGING (R: / /O. /kO ) THERMAL AGING (R:_I , P. /4's
- 3. A 3 DOSE RATE [8//d RAD /HR AGED TO SIMULATED LIFE OF 4 YRS.
I DOSE PRIOR TO /,y l ENV. TEST kk //O RADS DASED ON AMBIENT DOSE DURING l ENV. TEST /V/A RADS AGING TEMP./ f/hout:5 MacciMd l ' DURATION BOO /~ / OUM TOTAL DOSE kI///O RADS l CYCLE AGING (R:.[; M. /k7 ) L. HUMIDITY 8d~ O /Od % l N AGED-RSMED CYCLES PEQUIRED 4 BY ANALYSIS TO 70 YRS. CYCLES PERFORMED l0, 0 40 t
#T}se hurrait/ity wa.s l>erforenea,/,g# for i s (Electro-Mechanical Equip. only) (b. ddC4k8. C/ V/dhoc<.r5 Q d 85-/co andido*f attes- therinal a9/ny taS&.
\ l v v REVIEWER: M MbA+ - DATE:[.O Y 8 l R: Test Report Page No. Reference 7/1/81
ENVII:GNMENTAL QUALIFICATION
SUMMARY
NO. t/ 2 3 -O/ SHOREHAM NUCLEAR POWER STATION-UNIT'l (^; SPEC. T1TtE .A,e Ooerafed Butter /% Values SPEC. NO. '/ 2 3 P.O.3/O 771 VENDOR E# c r bnfrc/.1 TEST ITEM DESC. 8o/e reo id Va[v c. MAKE. ASCO MODEL NP & 320 A /3'I E VENDOR TEST REPORT NO. AO$- 2 /6 78/7/2 8ev A , Wv/e reporf /746'/-/20 1 APPLICABLE STANDA.'tDS TEST REP' ORT NO. 2.3 2.- O / IEEE S 2 3 - /9 7'/ TEST METHOD Seaireo fio/ Te3-/Ano/vsis IEEE DCCUMENTATION ACCEPTABILITY Accep'/ob c IEEE NUREG 0588 CAT. 2' QUALIFIED LIFE tr'O ,rors - coil s. elespomer c.h 'on q e e ver y 4 years TEST SEQUENCE (R: kooc( 3-/ 3- 2 } 1 Bas e lin e_ /func+ ion a I s. Ace; den-/ RadioHon
- 2. Thermal Aoina 7. L OCA ,Sim ulo t ion 3.__0abiofio*1 8.
- a. ulear A o in a 9.
- 5. Senmic Si$ulafion/V,tra+ ion 10 W 0 e [or e a n d A O e r echh Twe Te <1 End.Yq:.
, TEST ENVIRONMENT (R: 8o n e. < L/ '/ _ 4 J" an d $a 2' 'Ooor '/ - 2 / ) APPLICABLE ,/ ENV. ZONES TIME S ##$ 3 #/25 l7 ##5 85 #25 ' 2 G D)'.5 RAD (;
TEMP. *r 34/6 36/6, 320 250 200 PRES. PSIG //O //D 7f /6 /O T/p / R.H. /OO s OP. TIME DEMO /BO DVS T ACC/PERF DEMO M/A
$ Ann /vsis for /40 ORY OO 7,AC W Q YL G' AEPoCT' ('7'/ (oU~/2ok RADIATION AGING (R: U#,4 b ) THERMAL AGING (R: [oy s '/- l 9- 3 9 '/
j ) L L DOSE RATE 8///O ond .8X/O RAD /HR AGED TO SIMULATED
~
LIFE OF M 8b YRS. DOSE PRIOR TO p ENV. TEST 2.Of 3 / /0 RADS DASED ON AMBIENT TEMP OF DOSE DURING , . . . . ENV. TEST /Yo M C RADS AGING TEP g DURATIO [ / ! O,V I MTAL DOSE 2. O/ 2, / /C RADS *, REL. HUM 1uITY I.) n t e d r0 e % CYCLE AGING (R: kooc 4*3 I NOT AGED-JUSTIFIED CYCLES REQUIRED _4d,000 / BY ANALYSIS TO M/A YRS. (j~3 CYCLES PERrORMED 40,000 w see wy/c Lc 6. TAermal S9,ng \ (Electro-Mechanical Equip. only) An o /y,5 0, cuy /c ,Megorf /7Y(,y. f.idpogc 2. s l . n p REVIEWER: JL !/h M 'lyf DATE: 8!/88[
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 1/39-O/ SHOREHAM NUCLEAR POWER STATION-UNIT 1 l SPEC. TITLE M80 V Mo+or Generofor- Set SPEC. NO. '/39 P .O. J /095D VENDOR 1o u /3 A///3 TEST ITEM DESC. Se e A t+ ael) ed GOS nas. 43 9 - 01 A G_ C.. D an d E~ MAKE MODEL VENDOR TEST REPORT NO. lou /< A ///S 9 /2 95"7 b _, APPLICABLE STANDARDS TEST REPORT NO. 3/ 3 9 - Of IEEE TEST METHOD IEEE DOgUMENTATION ACCEPTABJLITY A cc eo"/a(( when sunnle menfed bv tuale ' La 6 ~
*EEE rennr+ 'i7 t/Gt/- 3902 '
NUREG 0588 CAT. QUALIFIED LIFE TEST SEQUENCE (R: )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
TEST EINIRONMENT (R: } APPLICABLE \ / ENV. ZONES TIME RAD /\/ TEMP. 'F PRES. PSIG T/P 21 R.H. % OP. TIME DEMO ACC/PERF DEMO RADIATION AGING (R: ) THERMAL AGING (R: ) DOSE RATE RAD /HR AGED TO SIMULATED LIFE OF 1RS. DOSE PRIOR TO ENV. TEST RADS BASED ON AMBIENT DOSE DURING EIN . TEST RADS j
~
TOTAL DOSE RADS CYCLE AGIE (R: )
" ~
CYCLES REQUIRED BY ANALYSIS TO YRS. CYCLES PERFORMED g (Electro-Mechanical Equip. only) REVIEWER: NN d DATE: / !(, !&1 R: Test Report Page No. Reference 7/1/81
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N24 A *G1 REPORT tc. PIS-500 JC3 1160002 12/10/81 EtNIR0!4t:NTAL CUALIFICATICN STATUS RIPCRT RP O:.T to. FES-800 STOt;E AND N!BSTER E!!GINEERIt43 CORTORATICt! J03 t?r*.,E9 1160002 FROJECT E O'JIF S!!.T SYSTEM - IIS-129) REPCRT DATE 12/18/S1 PAOI 66 JC3 L*.!!E SH03E:!t.!t - U'4IT 1 EttVIR0!ctEffTAL Cts.'.LIFICATIC;l STATUS REPO2T RESET t43. 003 JOB CLIE!1T LILCJ SCRTED SY - EQ3 / / RESET DATE G7/El/31 ECUIP:tEtti ID ECWPitEtiT CESCRIFTICM APFLIC C643 I!AME / !!At?JFACTUR:P EQ SHEET CP TIME ACC / PE9F NU-cat VEtCC2 ID VEtCO2 flAlfE CAC ZOriE I:00EL / CATALCG t:0 Q'J '.L STAT OCTG ITE!! OSTG ITEtt EttG Cic PO t.Ut'BER PC PESP SPEC ELOS ELEV SAFETY FUtiCTICr4S SUB!fG CP CD u*m.e4*venesene ** <s,* ave..**,=,,.,<,m .. 4s*. 44 awe.*u e=, te m nu*.se.*ws..es mas 4**,me ***emede emm*.***** **** REPO?T CPCUP EOS = 05-439-01 1
.1P 2ht t3111 <480V It0TCR GEriERATO'3 (RED) LCUIS ALLIS *QS-439-01 100 DYS f:A LOUIS ALLIS IE d-21 COGSF eEQ ALL 310950 439 R33 150 A .1R2ht:3112 450V ilOTCR GE!ERATC9 (CLUE) LOUIS ALLIS
- QS -439-01 180 CYS NA LCUIS ALLIS 1E N-21 CO3SF .EQ ALL 310950 439 R3S 150 A
.1R24 t;G113A 480V ltOTC9 GEri;RATCa (CRAr;GE) LOUIS ALLIS =05-439-01 100 DYS NA LOUIS ALLIS IE ti-21 CCGSF *EQ ALL 310950 479 KS3 150 A .192rin':3113D 480V It0TCR G!t;EnATC7 (OnAt:GE ) LCUIS ALLIS *CS-439-01 ISO DYS MA LCUIS ALLIS 1E N-21 COCSF *Q ALL 310950 t' 3 9 R15 150 A a
D x 3 Q 'rn mc (A ~I A~1 (F C a i O
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EINIRONMENTAL QUALIFICATION
SUMMARY
NO. 439--o/M SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE 4SO V Mofor Ger) e< a for- Se.fs SPEC. NO. N.3 h P.O. 3/09f0 VENDOR / ou is A//,5 TEST ITEM DESC. Wi ndin a [nsal4ftOA bv$f e rnS MAKE 8ee A f focM m - f / MODEL ed A f f o ck m esq / / VENDOR TEST REPORT NO. L o u a _J / ///3 9 - /2 9 8 7 [., APPLICABLE STANDARDS TEST REPORT NO. 434-O/ IEEE 3 23-/9 7Y TEST METHOD 7'd 5 N /d n o /y 5, r IEEE // 7 -/ ON DOCUMENTATION ACCEPTABILITY /)ccen t a / /e-IEEE W -- / G W NUREG 0588 CAT. J' QUALIFIED LIFE A/d veoes TEST SEQUENCE (R: /V/A f)ll /~er f ujerc cer [o em ec/ indenen alen f fv ) i i i
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
) TEST ENVIRONMENT (R: //[/) /)/3 /? fc5 f n e T r co t/ /rc d ) APPLICABLE j '
ENV. ZONES TIME RAD f/ TEMP. *F PRES. PSIG T/P 1/ R.H. fi//] % OP. T ME DEMO / 8 0 E o v.S ACC/PERP DEMO N!/1 1ADIATION AGING (R Jec_ f ; aq ff ) THERMAL AGING (R: d'ec ts e n /1 ) DOSE RATE 4. 9 i /O RAD /PR AGED TO SIMULATED LIFE OF N!N YRS. DOSE PRIOR TO EIN . TEST N!// RADS BASED ON AMBIEfr~ DOSE UURING EtN . TEST N!/3 RADS j
^
TOTAL DOSE /./ / /O RADS CYCLE AGING (Rr Y
/ c t- Meq.; f re d ) " ^ -
CYCLES REQUIRED BY ANALYSIS TO YO YRS. CYCLES PERFORMED 4 g gpfe f p,) j g,.g 4 g v 5. Electro-Mechanical Equip. only) REVIEWER: N - W/Mk __ DATE: b' M- 8/ R: Test Report Page No. Peference 7/1/81
ENGINEERING REPORT A f foc.hmen t I for ros- 439-o//t i gage I of 7 DATE OF TEST
-~~
f ("% MANUFACTURERS l: 9-129576 (j . ORDER NO. PURC H ASE R'S , PURCHASER Long Is1 nd Lihhting Co. ORDER NO. 310950 P4-9061 INSCLATION SYSTEM ALTERNATOR ARMATURE Magnet Wire - - Single Glasa Heavy Polyimide Film { Slot Cell - Silicone, G3 ass-Mica-<> lass Top Wedge , Aramid U-Wedge Silicone Resin Gla.is Laminate Flat Wedge Center Wedge - Sil,icone Resin Gla ss Laminate End Coil Insulation - Silicone , Glass-Mica-Gla ss Sleeving - Polyimide Coated Glass Connection Insulation - Gla ss Polyimide Coated Glass Sleeving i i Lacing - Woven Gla ss Tape - Woven Gla ss i Varnish - Silicone ; Lead Cable - Aramid Polyimide Coated Glass I. Re fer to i fcm 15, par n,p3 l'i.df tes y repor f- for Ja lq
.show.ng ham o ( .' 109 9 (43 "c. ) am bi e n t temp ;
Eritten By P.
~p}p g g uyy Sheet 1 of 7 [._J L()UIS ALLIS s ,u utton .. .... e,- " ' ' ' " " '""'""""E" b 4rnOvto av N/~ N- Nd _
DATE_ 5-15-81 f/ _ SECTION G-1
ENGINEERING REPORT F Se lof 7 --- I I~ DATE OF TEST ps M ANU FACTUR E R'S 9-129576 (g! - ORDER NO. PURCHASERS i . - L ng . Island Lighting Co. ORDER NO. 310950 ; PURCHASER P4-9135 INSULATION SYSTEM ALTERNATOR ROTATING FIELD Magnet Wire - Heavy Polyimide Film (H220F)
. Pole - Silicone , Gla ss-Mica-Gla ss Pole End Radius Block -
Silicone Resin Glass Laminate Pole Washers - Silicone Resin Glass Laminate Washer Tape . Woven Glass < Bonding Resin - Epoxy Resin eg S le eving. - Polyimide Coated Glass
/ ) \'~/ Tie Tape - Woven Glass Crossover Insulation - Silicone , Glass-Mica -Glass Connection Tape - Silicone , Gla ss-Mica-Gla s s Woven Glass Banding Tape - Epoxy Resin Glass Filament Reinforced Varnish -
Silicone < Lead Cable - Aramid Polyimide Coated Glass l j No P F 4 :
- l. Refer to i rem W, pqr4 B , pg JS of res 1 repo.' t fcr da fq
, $l1cwo ng boso s o f /b-) ~s: ( Y 3 %.) c.nf a as t- fem /3 O,
y, v r:.tten av 1 Sheet 2 of 7 1 LOU;S ALLIS
/.(L/'j7r-e'-
R _ ,, Litton g - - 4 -. . . :. APPROVED BY A> '/"R
*"- - { /#4 # CoDEIDENT.NO.
DOCUMENT NUMBER f.fm /q e.,7-SECTION G-1 '
" 5-15-01 4 7 DATE -
ENGINEERING REPORT F"" 3 # 7 DATE OF TEST
. M A N U FAC TUR E R'S 1 ORDER NO. 9-129576-O)
(_ = -
- Lona Island Lichtina co.
. PUR CH ASE R'S 310950 I'
PURCHASER ORDER NO. P4-9144 INSULATION SYSTEM ALTERNATOR EXCITER ROTATING ARMATURE f i
. ARMATURE l Magnet Wire -
Heavy Polyimide Film (H220F) ! I Slot Cell - Silicone , Glass-Mica-Gla ss' ' Top Wedge - Silicone Resin Filled Glass i Laminate , I Center Wedge - Silicsh Resin Filled Glass Lamins te ',
' End Coil Insulation -
Silicone, G la s s -Mica -G la s s I O.' Sleeving - Polyimide Coated Glass 1 Connection Tape - Silicone , Glass-Mica-Gla ss I
. i Woven Glass Lacing - Woven Glass Banding Tape -
Epoxy Resin Glass Filament Reinforced Resin - Epoxy Varnish - Silicone Lead Cable - Aramid b go g . - Polyimide Caoted Gla ue I.i2efer to item 15, para . C, pg y, o ( les7 repor i l'or dofq
. .sh c w o ng b o.s i s o f f o9 'f* (4.3 *c ] am b, en t temp.
Written .9y m-(N y/ {
\
pp ,7 j [ , Sheet 3 of 7 _ _ _ . . LOU!S Al.i_lS o 1.ttic n ' sn // n ' CODEIDENT.NO. DOCUMENT N U /A B E R CO APPROVED BY AN 'V/[" N4 DATE 5-15 !81 SECTION G-1
ENGINEERING REPORT F 9" Y # 7 DATE OF TEST --- M AN U FAC TUR E R'S h * - ORDER NO. 9-129576
. PURCH A SE R'S .
PURCHASER Lono - T o la nel Llahtina Co. ORDER NO. 3100GO P4-9144 INSULATION SYSTEM i ALTERNATOR EXCITER STATIONARY FIELD g i
. ETELDS , l i
Magnet Wire - Heavy Polyimide Film (H220F) ! Ground Insulation - Silicone , Gla ss-Mica-Gla ss Conductor Splice - Polyimide Coated Glass I s Coil Leads - Aramid Polyimide Coated Glass - O
- Connection Insulation -
Woven Glass ( Polyimide Coated Glass Start & Finish Leade - Polyimide Coated Glass Buf fer Insulation - Polyimide Coated Glass Coil Insulation Tape - Silicone , Gla ss-Mica-Gla ss
- Woven Glass Varnish -
silicone No t es : .
- l. i?e fee to a f em 20~ para .D, py 2 I o( iesi reparf for da ta s hows ng ba,s,3 o f to; y (y3 c.) c.rrbien t txmp,
- s rm written ey --
l O 6 v n g J g m. 0 Sheet 4 of 7 unon 2 LOUIS ALLIS Arraoveo av b [u d N N. " " " " """"'"""" DATE 5-15-G1 I f SECTION G-1
F 9* # / 7 ENGINEERING REPORT ---
.DAT E OF TEST ~
M ANU FACTUR E R'S 9-129576 Os . ORDER NO. k' = - Long Island Lie;hting Co. PU R C H A SE R'S 310950 PURCHASER ORDER NO. P4-9128 INSULATION SYSTEM
, A.C. MMOR STATOR AND PERMANENT MAGNET PILM EXCITER STATOR 1
Magnet Wire - Heavy Polyimide Film Slot Ce11
- Silicone , Glass-Mica-Glass Top Wedge - Aramid I?-Wedge Silicone Glass Laminate Flat Wedge Center Wedge' -
Sil'icone Glass Laminate
' End Coils - Silicone , Gla ss-Mica-Glass Sleeving - Polyimide Coated Glass Connection Insulation -
Woven Glass Polyimide Coated Glass Lacing - Woven Glass Lead Cable . Aramid
- Polyimide Coated Glass Varnish -
Silicone lVo res -
- i. Refer to ifem 1Qpura. E,pg% ) om b, temp.
en t2 2 o f te.d r cpa showing bon.s of 104 4 (4 3 p \-lritten y
~,
ne JSplLIS D7'18 .ke, ~ u_. 3 e ;,h jl -e L CODE IDLf4T. NO. D O C U .M E N T NUMBER c) APP.10V ED BY DATE 5-15-81 gj f , SECTION G-1
~
ENGINEERING REPORT F9e '#7 --- DATE OF TEST .
~
M AN U FAC T UR E R'S n . ORDER NO. 9-129576 j , ,
- PURCH ASER5 Long -Island Lionting Co.
ORDER NO. 310950 PURCHASER _. t
. i 09P00057 .0000 {
i INSULATICN SYSTEM FEEDBACK CURRENT TRANSFORMER j i I l i
- s Magnet Wire -
Heavy Polyimide Film ; Te rmina ls - Tin Plated Brass Terminal and Bracket Insulation - Flexible Plate Mica Tape Woven Glass Varnish Sil'icone O %./ l i VARNISH TREATMENT Preheat followed by multiple dips and bakes in silicone i varnish. i t 1 No t es : -
.13, o f te s t repor f & ,
I. daRefer to i rembas Wnpura o f w F+ ,*;py(13 c.) cim bra, t terrip. to .shcwing I i
. i
- t v:rizzer. ?
> R Sheet 6 of 7 LOUIS ALLIS M'o >/+/e- ~
g utton . . . . . . . -
~
coot ioten. no. ! cocuutsi suu. eta A rr o tn [D B Y - M g d, p(C M
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c 5-15-81 SECTION ,G-1 Det
I com e
~
7of 7 ENGINEERING REPORT
~ ~
DATE OF TEST
' ~
M ANU FAC TUR E R'S
/N) 9-129576 ORDER NO.
(v' ' PURCH ASERS Lona Isla nd Liahtina Co. ORDER NO. 310950 PURCHASER VARNISH TREATMENTS P4-400-ll5 A.C. STATORS
~
Preheat followed by multiple dips and bakes in silicone varnish. P4-400-125 ALTERNATOR RCTATING FIELD COILS
' varnish treatment for coils , wet wound with epoxy' resin and baked.
Varnish' treatment for coil assembly, p.rcheat followed by multiple dips and bakes in a silicone varnish. ye) - - - _ P4-400-126 BRUSHLESS EXCITER ARMATUPI Preliminary varnish treatment is a preheat followed by one VPI and bake in epoxy resin before installing leads. Final varnish treatment a fter leads are installed is multiple dips and bakes in silicone varnish'. P4-400-127 EXCITER FIELDS Preliminary va rnish treatment is a preheat followed by one dip and bake in silicone varnish before forming and taping operating.
, Final varnish treatment is a preheat followed by multiple dips and bakes in silicone varnish a fter forming and taping operation.
n) r:
>, . : s t. .:
of 7 g L_ '*s LOUIS ALLIS R S y7 ., b"/j^ ' " " 4 Sheet 7 Litton . . . . .
~ ,o f eoNfjjA'-u /j:1.s 7. . ccet etNT. No. coc stNT NUMSER APPROvtD ey c.: -- .
DMt 5-15 dG1 7;' , SECTION,G-1
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 439-O/M Rev 1 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE L/ BO V M o tor Gene ra tor Se.ts 3 /0 9fD VENDOR /,ou /S A///J h SPEC. NO. I/ 3 9 P .O. TEST ITEM DESC. Ocorino Me/o fed E/emenf 5 MAKE See- A ++a ch m en"+ MODEL See A tt ach m en + 1 VENDOR TEST REPORT NO. l.ou is A /[IS 9 - /2 98 7b APPLICABLE STANDARDS TEST REPORT NO. 1/39-O/ IEEE 3 2 3 - / 9 7'/ TEST METHOD T~es-f /Ana /yJ U IEEE DOCUMENTATION ACCEPTABILITY Aer eoYo[/c= IEEE i NUREG 0588 CAT. T QUALIFIED LIFE L/d ear $ TEST SEQUENCE (R: hllA All fest ulere Berl'ctmeN in ofef en dt.n 4 ly )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
TEST ENVIRONMENT (R 7)R A f emf noY /*c o u/r e d APPLICABLE EIN. ZONES TIME RAD A/ TEMP. *F PRES. PSIG T/P 2I R.H. A///) % OP. TIME DEMO /SO Dayr ACC/PERF DEMO A/!4 RADIATION AGING (R: 8c. c_-f fon d ) THERMAL AGING (R: 8 ec_f in n el ) WSee note I on ottachment DOSE RATE Not Giv e n RAD /hR AGED TO SIMULATED LIFE CF /\/[/9 YRS. DOSE PRIOR TO EtN. TEST N !r} RADS DASED ON AMBIENT DOSE DURING EtN. TEST /\/!A RADS j TOTAL DOSE / < /o 7 RADS uRATION d / NA CYCLE AGING (R: S e c_f[o n tl- / )
. Of $ reneh %
STIFIED CYCLES REQUIlED /00.o00 N#S #[g$t L)Q yp , CYCLES PERFORMED > L/O vears V de 3 m o%MM n v (Electro-Mechanical Equip. pnly)
% Se ,- note 1 on oHochment-WS REVIEWER: '[ m - V DATE: 1!b!82 R: Test Report Page No. Reference 7/1/81
ENGINEERING REPORT A ffochrn ent / for EGS 439-0/6
~ . D AT E OF TEST __., ---
M ANUFAC TUR E R'S O ' ORDER NO. 9-129576 V PURCHASERS PURCHASER Lona Island Lichtina co. ORDER NO. 310950 BEARING RELATED ELEMENTS A. . BEARING SIZE AND TYPE:
- 1. Motor
- Drive End - 218 SF Deep Groove Conrad Ball (1 Shield)
Non Drive End '- 216 SF Deep Groove Conrad Ball (1 Shield)
- 2. A lt e rna t or ,
i Drive End - 318SF Deep Groove Conrad Ball (1 Shield) Non Drive End - 318 - SF Deep Groove Conrad Ball (1 Shield) B. BEARING INSUIATION:
- 1. Motor
- Insulating Washers - Canvas Base Phenolic l p)
Insulating Tape - Epoxy Resin Glass Filament Reinforced l
- 2. A lterna t or I,nsula ting wa shers - Polyester Gla ss I,aminate Insulating Tape - Epoxy Resin Glass Filament Reinforced-C. BEARING LUBRICATION: Dow Corning @
FS-3451 Grea se NGLI #2 NO + es - I. Limiting Component is bearing ul>re'eant f
- 2. The heering life c{ > 40 y e, : e s f a L li.sbed by a n o ly.s is ,
- 3. Refer to p ag e. 25 of tesi r*cfort for dato abowing i ba.sh of IO9 'f (43 *C} am bien t temp
- . j I
=
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- CoDEIDENT.NO. DOCUMENT NOMEER APPROVED BY # A'W m 4 jf % :=
= DATC G-15-91 ,
f t,.M
, _ SECTION G-2 i
81NIRONMENTAL QUALIFICATION
SUMMARY
NO. 439- O /C Revi SHOREIUud NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE 480 V Mofor Geoeraf or Sef V SPEC. NO. 8/39 P.O. 3/0 980 VENDOR l.O ta is A/[/a TEST ITEM DESC. Mof a fina Meefi[ier A SSem b /V MAKE See A f+oc hav1enh MODEL St=rm A }fac k mc /1f VENDOR TEST REPORT NO. [ou is A///3 9 - 12 987 b APPLICABLE STANDARDS TEST REPORT NO. L/ 3 9 -O/ IEEE ,12 3 -/97'[ TEST METHOD Tegf /Ano /vg/3 IEEE GSO - / 979 ' DOCUMENTATION ACCEPTABILITY A cc e e po/[r= ' rah e_ n Succlemenfed by Wyle 'Lu b IEEE ,e ,o,f ' , ygy_3 goj NUREG 0588 CAT. I QUALIFIED LIFE t/D veor3 TEST SEQUENCE (R: /\//A A// +est were Derformed independen/fy )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
TEST EtNIRONMENT (R: DOO fes-f" nof recurred '
) APPLICABLE ENV. ZONES TIME RAD /\/
TEMP. *F PRES. PSIG T/P 2i R.H. N/d s OP. TIME DEMO /80 dovS ACC/PERF DEMO /V!/7 RADIATION AGING (R: Sec f fon 1( d Wy/e ) THERMAL AGING (R: 8ec fio n M ) Repe t I1'fL V- 3 90 2. DOSE RATE Mo /- b ive #7 RIO /HR AGEl> TO SIMULATED LIFE OF N[4 YRS. DOSE PRIOR TO EtN. TEST /\/!d RADS DASED ON AMBIENT DOSE DURING EtN. TEST N/A RADS TOTE DOSE / X/0 7 W S uRATION p,j N/M / A//4 CYCLF AGING (R: Mof Meovired )
" ^
CYCLES REQUIRED BY ANALYSIS TO 40 YRS. CYCLES PERFORMED / (Electro-Mechanical Equip. only) W 8cc, AOIC 1 o n o // UC'ir9 ed f REVIEWER: M- W ///*\ DATE: I!6 !<P1 R: Test Report Page No. Reference 7/1/81 l l
ENGINEERING REPO'RT A trac. Amen t / for E(PS - L/3 9 - o / C, ~~~ DATE OF TEST M AN U FAC TUR E R'S
- ORDER NO. 9-129576 (c)
. PUR CH ASE R'S Long Island Lightina Co. ORDER NO. 310950 PURCH ASE R RUPATING RECTIFTER ASSEMBLY A. Diodes: " General Electric" Part No. 1N1190 (Forward) and 1N1190R (Reverse) ,
B Diode Support: Canvas Base Phenolic C. Sha ft Insulation: Gla s s-Mica pa pe r-G la s s Laminate Silicon Bonded D. Cable: Aramid Notes:
- 1. I.rio ' Ri3DS bascJ on I,mihng c car,pc ren t (Dicde.s) e vu _.u- #
se
/
2.. Re fer to i tem 15, para. 11 , pg 2G of tesi repor t C)
%j for- da ta Jciv w J basis for 109 7 (43 2 ) om bien t f~c m j0.
3 The effecb al' ro d. o t:cn on d.cde : w a.> do ci k' m J by L _
;p f wyle L a b report / W G 'l - 3 9 0 2-Written =']
Sheet 1
}
CL R ~ m7'73,f 4 _/ [ , , i_ _. of 1 i LOUIS ALLIS L,tton ' .... . S . . . w Arraovc0 av b.N+< L[*S -
.CTION G-3 f.
DATE 5-]S-R1 _ 1 -- _. -
EtWIROMMENTAL QUALIFICATION
SUMMARY
NO. 43 9 -o/D Re. I SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE $O V Motor 0enero h0r $cf SDEC. NO. V39 P.O. 3]Q9fO VENDOR l. ou s*5 A///3 TEST ITEM DESC. Sf 0fic-. kecfiNer Con +rol BOacd Cire.uir MAYE See A ffocb menf MODEL Sec A ttac_hrn e n+ VENDOR TEST REPORT NO. l O U [S A///5 9-/2987b APPLICABLE STANDARDS TEST REPORT NO. '/3 CT- O/ IEEE 323-/979/ TEST METHOD Tesf/Ano/v5/_5 IEEE foSO '/0[79 DOGUMENTATION ACCEPTABILITY Acceofo((e. when suoo/emen+ed bv wvie ' L a b. IEEE ,e co,p jygg y,399, NUREG 0588 CAT. [ QUA'LIFIED LIFE L/ O v e o r ; TEST SEQUENCE (R: M[A A// feff u/ere cer[orened indedeoderdke )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
TEST EtWIRONMENT (R: T)d A tea / /5 no/ reous* red ) APPLICABLE O ' EIN. ZONES TIME RAD /\/ TEMP. *F i PRES. PSIG T/P '1 l R.H. N /o s OP. TIME DEMO _/ 30 Days ACC/PERF DEMO A/!A RADIATION AGING (R:S ec.fio n Le W y /c ) THERMAL At ING (R: 8ec-/ /o n [ ) (cport n'fGV-3901 DOSE RATE Not- Given RAD /HR AGED TO SIMULATED LIFE OF A/!d YRS. DOSE PRIOR TO EIN. TEST N[d RADS BASED ON AMBIEt1T DOSE DURING EIN. TEST N /A RADS _j
- DURATION / A TOTAL DOSE L/. / 7 Y/O ' DS CYCLE AGING (R: Not Recu rred )
"E "U"***'* N* A dd""'N ' ^ ~
CYCLES REQUIRED BY ANALYSIS TO 40 YRS. CYCLES PERFORMED O (Electro-Mechanical Equip, only) I ICC. M O f e 1 0 0 o / /~a c b ol c o f REVIEWER: m I T M DATE: I!(e [87 R: Test Report Page No. Reference 7/1/81
- ' ENGINEERING REPORT A ffacA ment I for EOS- 439 - O/ 0
~~~
DATE OF TEST
. 1 MANUFAC1URERS ORDE R NO. 9-129576 l f] \. ) .. PURCHASERS PURCHASER Lono Island Lichtino co. ORDER NO. - 310950 STATIC R"CTIFIER CONTROL BOARD CIRCUIT A. D,iode s : " Genera l Electric" Part No. lN1190 (Forward) and IN1190R (Reverse) i B. Insulated Diode Support: Canvas Base Phenolic C. Cable: Aramid D. Pesistors:
- 1. 10 OHM "OHMITE" Type 210
- 2. 21 OHM (hpf"ht) _ ..Milwa ukee Resistor Corp."
E. Termina l Board : General Purpose Black Phenolic F. Poly Crystaline Varistor: "Ge neral Electric" Part No. V320LA40B Notes : 1. 4.17/ to' R A D,5 based on limiHng componen t (Poly Crys talin e. Varis for)
- 2. Re f'er to i fem 15', para t) pg 2? c>f test reporf for clota 9Wong bas lS for ,/09 'i' ( 4] 'C.) am bi en F temp.
3 The elTect., of rad.o +oca cn r'0c cla c cl e s r e ,_, o rs o rsd Pc>l y Gys to lu ne Vo <i s f or u .s o ddrc s.,cd b ,< A y " '*' Wyle. La bora tories repor t n y c,4 - 3 9 0/ 4 p ' .'.-: u : . : - l
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l ogg 5-15-81 f/f SECTION ,G-4 l
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 4,3 P 0 / E SHOREHAM NUCLEAR POWER STATION-UNIT 1 (3 SPEC. TITLE L/20 V motor G er, er o +ce Se+ SPEC. NO. L/39 P.O. 3 / 0950 VENDOR l_od [5 A/// s TEST ITEM DESC. /2Olof/oo E / em /cl ([o,tto,nQ v i a MAKE Se_ e_ A + +ac.h m e n t i MODEt see A ttac hmen t I VENDOR TEST REPORT NO. /-ou i-5 A // d 9- / 2 987la APPLICABLE STANDARDS TEST REPORT NO. 439-O/ IEEE 333-/979 TEST METHOD T'e s-f Mn c, /v_s i.s IEEE DOCUMENTATION ACCEPTABILITY Ae_c e,n to b /e, IEEE NUREG 0588 CAT. [ QUALIFIED LIFE L/O v eo / s TEST SEQUENCE (R: N/A All Tesf were ,nerformed undecendently )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
TEST EtNIRONMENT (R: M[/) Ol3A f e d 7 O O /~ ("C O y /rc h ) APPM CABI.E ENV. ZONES TIME __ RAD N TEMP. 'F _ PRES. PSIG T/P 1/ R.H. N/d ik OP. TIME DEMO N/A ACC/PERF DEMO N[A t RADIATION AGING (R: Sta c_ [ f o n /T} } THERMAL AGING (R: _3ec.bO*! /N ) 4 See note I on a t tac.hment i DOSE RATE NcF 6,ven RAD /HR AGED TO SIMULATED LIFE OF /V!/} YRS. DOSE PRIOR TO EtN. TEST N[/} RADS BASED ON AMBIENT DOSE DURING ENV. TEST /V !/f RADS j TOTAL DOSE 27/0 RADS CYCLE AGING (R: NOr Meot//rc d )
" ^ ~
CYCLES REQUIRED BY ANALYSIS TO kb YRS. CYCLES PERFORMED (Electro-Mechanical Equip. only) j( 8e e D C fc /10/~e 1 On C7 7IO 'Md I / REVIEWER: ut gi DATE: _b~1E*M R: Test Report Page No. Reference 7/1/81
f i ENGINEERING REPORT Attach ment. / for Eo3-439-o/r ~~- DATE OF TEST M ANU FAC TUR E R'S
. ORDER NO. 9-129576 d . . -
L ng .Isla nd Lichting Co.
. PURC H ASE R'S 310950 PURCHASER ORDER NO. . 1 I
ROTATING - FIELD CLAMPTNG ! I A. Coil Claraps : Canvas Base Phenolic .
~
B. Bolt Insula tion: Polyimide Resin Coated Glass . I l\i o t e s - I. 1xto' RADS ba. sed on lim din 9 component (Cbol Clamps)
- 2. Refer to i tem for cla fq 9avin915,bas parq i.s .for K 109
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Sheet 1 of 1 _] LOUIS ALLIS g '- Litton "s...- 4 Le N//dW g* CCDEIDENT.NO. DOCUMENT NUM6ER oo APPROVED BY - DA1E 5-1 ~81 I _ SECTION G-5
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 439-02 Rnv i SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE &80 Volf 00for 0tne 70for Sti3 Q SPEC. NO. Ll3 9 P.O. 310950 VENDOR _ Louis Allis Inc. TEST ITEM DESC. Motor ConYrol Pone! for 4 tov Mc. ser MAKE bou /Of MODEL 56OO Ser/es VENDOR TEST REPORT NO. CC - 3 3 3.7 4 - @3 /2eV O APPLICABLE STANDARDS TEST REPORT NO. 439-02. IEEE S23-/97V TEST MEruOD Somrnaev #eoorf IEEE DOCUMEN*ATION ACCEPTABILITY AcceofO b/c - IEEE nrovided the informoHon re u Q.> - * - ted n n ggggy y39.gy g, g,g,;ggg NURSG 0588 CAT. _T ouALIrIED LIFE S,,' Af roc 4 men t TEST SEQUENCE (R: A/[A )
- 1. 6.
- 2. 7.
- 3. 8.
- 4. 9. _
- 5. 10.
TEST ENVIRONMENT (R: g[A _ _DOd tef f nOf reOu ired ) APPLICABLE O ' ' ENV. ZONES TIME RAD A[ TEMP. r PRES. PSIG T/P 2/ R.H. /s///) % OP. TIME DEMO A//4 ACC/PERF DEMO M!d RADIATION AGING (R: Page 7 ) THERMAL AGING (R: kog e 7 ) DOSE RATE 8ee A1/ocbroenf RAD /HR AGED TO SIMULATED LIFE OF 8ee A ffoc rr7eni" YRS. DOSE PRIOR TO j ENV. TEST /Y/d RADS DASED ON AMBIENT DOSE DURING #" ENV. TEST /Y O RADS j TOTAL DOSE Jee A ffac ment RADS CYCLE AGING (R: Mage 7 )
" "" ## H## #" ##* '
CYCLES REQUIRED
" ^ ~
BY ANALYSIS TO Iee A ffac[*f en f YRS . CYCLES PERFORMED 8ee_ AfYac 07en[ (Electro-Mechanical Equip. only) \,.s _ REVIEWER: Mo w d _ DATE: / [ R: Test Report Page No. Reference 7/1/81
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ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. W 5-Of SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE low Cocou+anc- F,, %, ra n - To . / < v .m . , - C a b le _ SPEC. NO. 4 53~ P.O. Jto 96 K VENDOR /3raoj kex (, O - TEST ITEM DESC. C r Or xrO l {R5 ff Umer, r Ca 6:e <M av u !a on MAKE 0 fond kdA D C. MODEL R G - 12 A 'a ; R C- -59 & la VENDOR TEST REPORT NO. F - C,5 / 20 -1 IBroo d & v Ca. /fea < ' , b t , Cre.) / APPLICABLE STANDARDS TEST REPORT NO. 457-O/ IEEE ?)1-/9N TEST METHOD 8e Ou e n "iu / 5*!Anu/. ,s IEEE 3S I~/9 W DOCUMENTATION ACCEPTABILITY N - c /o 6 /e IEEE NUREG 0588 CAT. I QUALIFIED LIFE 4 0 y ars TEST SEQUENCE (R: deCf,on T 000e5 4 -I TA g a.u )
- 1. [J nL h ona l Test s. 5,n a l Tn . ,,ec r,u n
- 2. 7~h e rma / /lo,r1Q 7. lf f ob Mo *en ho / 4' rS , forii/ 'Tidf s J <
- 3. [n s a la Tson Aes', < tonce Ch:ck 8.
- 4. G o an rn a [< r a al . o
- i o n 9.
- 5. :, rea.n lCheun. cal 5fa v Evo m u m 10.
TEST ENVIRONMENT (R: M3cc 9-3 (Eoi?EF yn-o/ C2Mt 3 ) APPLICABLE ENV. ZONES TIME /4b a d l2. . 2. l2 8 l 4Y / 1 Y 7Y pap /)/1 , TEMP. *F 365 3% 385 l3'6 l 3, ' 190 230 PRES. PSIG b6 //3 bb ! // 3 70 38 /O T/P ed _
/ r_
R.H. ( SPA'IlY ) /CO % OP. TIME DEMO / 90 ,.90 v s ACC/PERF DEMO /Y b RADIATION AGING (R:, duce 4 / c /W /3 ) THERMAL AGING (R: %e 3 4 - / E- ! A%n / ) DOSE RATE b3d /0 RAD /HR AGED TO SIMULATED L' n LIFE OF s YRS. DOSE PRIOR TO y E?N. TEST 1" /C RADS DASED ON AMBIENT DOSE DURING OF /O T EIN. TEST /YOH d. RADS AGING TEMP./ v TOTAL DOSE 2/ /C RADS ATION / / b 8 e'/b CYCLE AGING (R: /VG
- k dOd *, dC/ * """
)
CYCLES REQUIRED N /,1 NOT AGED-JUSTIFIED BY ANALYSIS TO /V /7 YRS. CYCLES PERFORMED '\ 8 (Electro-Mechanical Equip. only) REVIEWER: 'ob- 1 v'/ b DATE: 8! /, R: Test Report Page No. Reference 7/1/81
b ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. L/56 - O/ SHOREHAM NUCLEAR POWER STATION-UNIT 1 O SPEC. TITLE Seacfar (On'to .., mc n r- Ele 2c.tr ,ca l Pene reo rio.n > SPEC. NO. 45fo P.O. 3iO% 7 VENDOR Canar Co.ooraticn TEST ITEM DESC. In S tru n) e n t PCne tra tion A s5e m bly Muz Conai MODet Tn s f<a nen i R:ne. tra V:en !?ss en, bly VENDOR TEST REPORT NO. IPS-533 APPLICABLE STANDARDS TEST REPORT NO. #56-OI IEEE 3/ 7-/37b TEST METHOD M.oan ho / Ie d /)no I.n U IEEE 33 3- /9 7Y ,,, DOCUMENTATION ACCEPTABILITY Il e a / . // - IEEE NUREG 0588 CAT. [ QUALIFIED LIFE 4 0 ,v~ e O ri TEST SEQUENCE (R: T.alle 4. 2. . ovu e. 8~ f. o a re %f pace S~/h )
- 1. Des,an Va l.da t,0., Tes1~ 6. Val,Jo to en Tei h,
- 2. S tor % q e S.in a lo tion 7. Seism,c__ Tes ts
- 3. Therino/ (-v /u 8. (/S /, do f, c., Tesis
- 4. Therrn a l /k i ., a 9. De s . o ., /3a s ; > s'w n r T~e ., r-
- 5. I?a d, a ts on N~a oN s a r e_ 10. t/a t, Ya t r.pn re . n jq TEST EtNIRONMENT (R: 8ec t. w? 8. 9,s'o c N 6.V o i. 3 / #-oc /JM t _) APP'. CABLE
( ENV. ZONES TIME Ml/'.!e., t /0 AV /. 8 //MO IE //MS '/ //M3 3@ Ib RAD .D Cy N TEMP. *F k rc,.io 320' 3 cri 340' 320' 100' PRES. PSIG 30 ~ 7Y 70 Y 35 T/P /0 // 2. 3-R.H. /OO s OP. TIME DEMO / vear ACC/PERF DEMO h/h RADIATION AGING (R S ev, T. b. s oora i~ ) THERMAL AGING (R: Sev er;.3 h. 2. J osu e /0 ) fy 1 DOSE RATE 7. '7 e /0 *' RAD /HR AGED TO SIMULATED LIFE OF 4 ') YRS. DOSE PRIOR TO y E?N. TEST /. 9 e /O RADS DASED ON AMBIENT TEMP OF ,2, f y op DOSE DURING l EtW. TEST /\/[] RADS AGING TEMP./ # URATION SO2 F / /00 ,f/?S TOTAL DOSE /. 3" /O RADS CYCLE AGING (R:m $e 56, / euro 3 g. / )
" ~
l CYCLES REQUIRED / 3. O BY ANALYSIS TO /Vf/Y YRS. CYCLES PERFORMED /20 (E!*tetro-Mechanical Equip. only)
\ f % rs .1 Lu le tes* re va.v] Is ifE0 3) 7 REVIEWER: L6 f- / -. .. M L DATE: d/ 2 J/
l R: Test Report Page No. Reference 7/1/81 l
)
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 4 Wo-0 3_ SHOREHAM NUCLEAR POWER STATION-UNIT 1 p SPEC. TITLE Reo< +ce Car, fo ann-4 Glee h,< a i 1%. + ro h w s SPEC. NO. 41 T/3 P.O. 3/D V6 7 VENDOR C -<3 o y Ca e tw a f , 9 + 1 TEST ITEM DESC. P, ne t < a 1. .~ . Il_ loo le, (1).: ,1,1le MAKE 0, ;) a v' MODEL l/> f 01 " l " 9 - {},n n Sea !s VENDOR TEST REPORT NO. 103 - Q [ ~ APPLICABLE STANDARDS TEST REPORT NO. 43 G 03 IEEE 3/ 7 -/ 9 7 L TEST METnOD Sem, e ., 4, a / Te
- IEEE 7 2 ' ' / 9 %' DOCUMENTATION ACCEPTABILITY /)c, _3
/ , / .!c IEEE NUREG 0588 CAT. [ QUALIFIED LIFE Wi' eeor-TEST SEQUENCE (R: 8 e a ,< e 3. 3 ourw 3 ) / / J
- 1. Gas icah kate T5st 6. [rr ae),a f i n!) -d
- 2. Therm a l C v , I, n a 7. Se , , m , e x
- 3. Sro,aoe j .r,, la)f, c n 8. Onc En' ,. , , c, < , i n <> . . a ! Ti _~ r K
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- 5. .Sh . o n > n . > 10. olier *!'a .' nN) e N te *on.d J J
TEST ENVIRONMENT (R: be,
- 6. /J 2 #
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//A ) APPLICABLE g ENV. ZONES v
TIME 210.4 ' I /Dlo 7 /".O b //M3 42i 4D RAD '?i . /_3
/j ~
15C'
~
TEMP. *F 30.f 350' 3 (- O 2 6 (. PRES. PSIG 5f SO 6f ST 2 0' T/P .<? // T)_ R.u. JCO \ , OP. TIME DEMO 18U Oov5 ACC/PERF DEMO A/ 4 l RADIATION AGING (R: $cc f,en & 6 on 7 ) THERMAL AGING (R: h .'r " .4 .'s -i on L. anl ) _ g ijtkltnar ]' DOSE RATE / . 5 / ' RAD /HR AGED TO SIMULATED . LIFE OF 9L YRS. DOSE PRIOR TO
/ . f ," / O "
ENV. TEST RADS BASED ON AMBIENT DOSE DURING TEMP OF c/ 'F EIN. TEST Ale d C RADS t j AGING TEMP./ TOTAL DOSE /. 5 /0 RADS DURATION 302~ / / (/ /@ l REL. HUMIDITY ll.') e r,. i 'r ? / I<- g CYCLE AGING (R: Sec he,, 6. 3 o c. ) NOT AEDMUSTIFIED , CYCLES REQUIRED -- /}C BY ANALYSIS TO [1 j , ,e YRS. 3 CYCLES PERFORMED _/2 O
) (Electro-Mechanical Equip. only) l V T N evr; G<,/c tc: t / wa //c./ by 16:e 7 /?
3 i ts j REVIEWER: ' e -(A W f a e n > c (* t DATE: 4 R: Test Report Page No. Reference 7/1/81
$ ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. /5.8Y- O / SHOREHAM NUCLEAR POWER STATION-UNIT 1 3 SPEC. TITLE So fe /y #ela /ccl Sc/eno,c/ Va /,/e t SPEC. NO. 15.5 4 P.O. 3109 79 VENDOR VQ lc n r~ [n a , n e_ e r r n u ( ora TEST ITEM DESC. 8c/cnc,d Va/./c MAKE Vo /cor- MODEL V516 00 - 5 /f VENDOR TEST REPORT NO. O /2 52 (,00 -5W0-1 APPLICABLE STANDARDS TEST REPORT NO. /8.dV- O / IEEE 12 3 -/ 9 7 Y TEST METHOD decaen fi o / E 4 f[/ln d /v:,;'J IEEE DOCUMENTATION ACCEPTABILITY Acc c/) fo ['/r._ IEEE ' NUREG 0588 CAT. 1 QUALIFIED LIFE 4/t) e o/s TEST SEQUENCE (R: Aonen d, y Y7T o00e yf ) e/ i *
- 1. Ta u r,ol Acceorame ihr s. ses sm.o Simulation /neofance T&-r
- 2. The, mal Ag :na //hcrn nor, h/ ,. LCCA Te -r/Auer,tonce Ye d
- 3. caI,e nmna /k< eo fa,,<e 7est
- a. D, w ssem A Iy End In, ve-c h c.r
< r- - .
- 4. AOdiohen 9.
- 5. D, e /ea- }rso onJ Ins ala ttoa Ac s.it' 10.
TEST ENVIRONMENT (R: Ono F Of Apo A #1 ou ,j e _ 4-/ - / 6 ) APPLICABLE
, Q f R.t f' App ZT. k 0 Eu, paye 30 f je Repxr l14t,4 -sidO2. ENV. EONES TIME 1//D 2 NS$ 2 NMS 3NM5' '/ //4) 8/N//$ 28 08 RAD C3 TEMP. 'F 346 l'fa 3% 337 3ir '2 6 F l 2'/5 PRES. PSIG //3 // 3 %~ 6 22 ' /3 T/P / 2 9 ro R.n. /00 s il OP. TIME DEMO / /cor # ACC/PERF DEMO /VM/
RADIATION AGING (R: I,NM #) THERMAL AGING (R: A go x'// Sec I-/. ;2. 2- ) g Wyie,10rpc.t /7464 Vs'O.4 DOSE RATE 73_hO RAD /HR AGED TO SIMULATED LIFE OF '-/O YRS. DOSE PRIOR TO y ENV. TEST 3 //d RADS BASED ON AMBIENT DOSE DURING . OF /2O T ENV. TEST McdC RADS AGING TEMP./ , , , TOTAL DOSE 3 y/O RADS CYCLE AGING (R: 4M // ler 4.23)
- NOT AGED W STIFIED j CYCLES REQUIRED BY ANALYSIS TO N//h YRS.
CYCLES PERFORMED ~/EOO e> (Electro-Mechanical Equip. only) REVIEWER: M.- '
.--/MUr*b DATE: 8!/ /
R: Test Report Page No. Reference 7/1/81
EINIRONMENTAL QUALIFICATION SUfetARY NO. 83 kh-O i GHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE .#F )r hnn S+eei N/aive MOV SPEC. NO. SH l- 99AD P .O. 310 511 VENDOR \/r 30 TEST ITEM DESC. Li miTOrG U d, MOV MAYI Li m'i+ n r n U (* MODEI VENDORTESTREPORYNO. san 69 4 ado B(4CISM ' (nOO 37(oA
~
h-O-f S OfIIFinCE CIMS M APFLICABLE STANDARDS 'dE'ST REPORT NO. IEEE - 9E3- 7-l TEST METHOD SFn a fenti &i T<asti e)o r o IEEE - $@ 2 - M DOCUMENTATION ACCEPTABILITY Ace eetable, IEEE Se e C o m rn e nt -+ s ner t a l cB nd i + tens g g gg g, ggy_ g i NUREG 0588 CAT. II. QUALIFIED LIFE > 409 rS TEST SEQUENCE (R: On 3-6 ( (n* n 03"I-(o A) )
- 1. The rmal Adinn 6.
- 2. Mechanir[I A%ina U U 7.
- 3. bArliPL+ inn Asi ns 8.
v v
- 4. 8ei9 mic Q ualificAYtOO 9.
- 5. A cci ole n+ Si ma la+i ors 1o.
TEST EfNIRONMENT (R:1 rAnhlin~1nMNU49 beOncttFc344l ) APPLICABLE pg '6- 5 ' EIN . ZONES TIME _Q -- 1 1-bhr Io-9hr 9-[Zhr 11-13 hr 13h r -Mdad RAD O, @ 3Lt 0 % TEMP. *F S40 Mo 320->2s2, Z5i PRES. PSIG t05 % to$ 77 t9 i5 TfP 3. 2z R.!!. J o O % OP. TIME DEMO 30 da\1S ACC/PERF DEMO RADIATION AGING (R: nrq 4 [f4(\376,M THERMAL AGING (R: oA 3 1[ Ann 53-On10 Ill) DOSE RATE l Y \O
'd RAD /HR ont the motbr%titor g' AGED . SIMULATED LIFE OF Nb YRS.
DOSE PRIOR TO E!N . TEST EO4 x.10 4 RADS nASED ON AMBIENT DOSE DURING E!N . TEST - RADS g j TOTAL DOSE E04 x l Oof RADS ! CYCLE AGING (R: n o %4 (ro003%AT ) i o REL HUMID m Ac.tuo.To r W-gen s CYCLES REQUIRED 50 O [ 33j $ 7 7 " > 4 0 YRS. CYCLES PERFORMED ROO Qut v. age a& 153'F is de.tcrm's ned O (Electro-Mechanical Equip. only) 'gy proporhonirq to thCr rn &l 1[Q Et Gu tts o ivtrL i n 6005 8 REVIEWERy (M [/ ). 7XL DATE: i l bO / R: Test Repert Page No. Reference 7/1/81
EtWIRONMENTAL QUALIFICATION
SUMMARY
NO. R 9 A N - O ?_ SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE fA rhnn 3iPP.) \laive M ON/ l SPEC. NO.SH 1-M/ TOP.O. 31 OSOl VENDOR Anchne hariIncg TEST ITEM DESC. lIrh l' YA Mt le M OV k r MOTO 6 t AC,TUATC6- EMB-0-45 MAKE L.1 m 14 O F G, U e_ MODEL MO TO8S [ALONET 2.9 40 h-/b start tg VENDOR TEST REPORT NO.80058+ Acob- Bon 03 ' Reiidnee .AC mm 8 TAttMorogT] APPLICABLE STANDARDS TEST REPORT NO. IEEE . <2$ 2 - l972 TEST METHOD M OstentiAI TeSTi M IEEE - 3G - i971 DOCUMENTATION ACCEPTABILITY Accentable _ IEEE
*Pe Cnm me nH w moer i At ' -
Mnef i+t a n s EG R EF- MV-3 NUREG 0588 CAT. 1T.. QUALIFIED LIFE 4/d Vr5 i TEST SEQUENCE (R: oa 7 -t O (BOO 09 )
- 1. Th errnal Aairvr v v .
6.
- 2. Mechanical Asma u v 7.
- 3. AAcs ia+1on Asina 8.
U ()
- 4. 9 t F M fYu c An'i n c, 9.
- 5. P_ nv i r o n rne ni A Tes4 10.
TEST ENVIRONMENT (R: ain (BOOOM ) APPLICABLE O ENV. ZGNES v TIME O .5hr .5 'Lhr E-Glhr ZM-2.5hr 23h r -IGdas RAD T./2 TEMP. 'F Z.50 2 +I2.0 7.60 zen-foo 2.00 PRES. PSIG ?5 -
'25 -
io Tfp i,2 s y,in R.H. in0 s i t #1 OP. TIME DEMO lGdA S ACC/PERF DEMO RADIATION AGING (R: nA R [MOOb ) THERMAL AGING (R: rYT *4 ('BOCONFf(158 o12)) ' I U Fd DOSE RATE I ( lO b RAD /HR AGED TO SIMULATED LIFE OF 131 dap DOSE PRIOR TO EIN. TEST 2. r.10 7 RADS DASED ON AMBIENT DOSE DURING ' EtN. TEST RADS AGING TEMP./ TOTAI. DOSE 1ElOY RADS A N 1 ro5 F / 20d b99.8)ng
* ""IUI" I '
CYCLE AGING (R: m 4 -% (80003 ) ) I O 89 0 O CYCLES REQUIRED B 40 vRS. CYCLES PERFORMED . / 3 C) 3 I.q 12-l'5 occ55] . (Electro-Mechanical Equip. only) g' Equi v. %e o ro POrf M cnG Ten i040R to-fo hermal brainedhtebgGurs t REVIEWER: r.d [d. IN- DATE: /2!l / R Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 8 3\/-01 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE farbon bied.k MIV6 -Mk SPEC. NO. 3H 1 99V P.O 36,50*L VENDOR V 6.l & O TEST ITEM DESC. Li mitoca o e. M o v MAKE LI mNn en O F_ MODEd4CISM fb- O-M Aeliance Cle: RH VENDORTESTREPORYNO. SAO 69 4 b D O b' '** In O O 3 7 In A
, - APPLICABLE STANDARDS YE'ST REPORT NO.
IEEE. - 973 *.I. l TEST METHOD Stodi fantiai aTr sti no Y O IEEE - 3% 2 - 72. DOCUMENTATION ACCEPTABILITY Ateeatao e IEEE Se e c om ments -+ s inm ia l c hnd itens - g g gg g , ggy_ g NUREG 0588 CAT. .II. QUALIFIED LIFE '> H O u e s TEST SEQUENCE (R: On 3-5 C rnnoSTro A) >
- 1. ThermAlAdinA "
6.
- 2. Mechanic A I A$ina . U U 7.
- 3. bAdi&+ inn Asi v ns v 8.
- 4. 6ei9 m'i e (I)Uali E e AYi on 9.
- s. A ce'i nt e n+ Si mtila+i on lo.
TEST ENVIRONFENT (R:T~rAnhlin'ln44-NU te benor-tlF"c3L/A/ / ) APPLICABLE O 9% 3-5 ENV. ZONES TIME O-% b6hr 6-Shr 9-lEhr i1-lShe 13h r -Mk ' RAD p. c M x, L TEMP. *r s1-10 C4, 340 326 A2N2R2, Z5i PRES. PSIG t05 % ios 77 t9 s5 rfP i . z t 5 m is R.H. f00 % 27 OP. TIME DEMO SO dam _9 ACC/PERF DEMO RADIATION AGING (R: n n 4 [ A n A 3'J [, M THERMAL AGING (R: n A 3 1 [An n S S -O n !n .Ill)
'd DOSE RATE l jf IO RAD /HR oniy the motbr%1 tor g' AGED 40 SIMULATED l DOSE PRICR TO LIFE OF N3 YRS.
ENV. TEST E O 4 x. 1 O ' RADS BASED ON AMBIENT DOSE DURING ENV. TEST - RADS g ggp_j t l TOTAL DOSE EON K lO b RADS CYCLE AGING (R: n a S M (fooO3 % Al) REL. HUMIDITY Not - 61 Ve A % ggg v NC'" '.0Q-JUSTIFIED CYCLES REQUIRED E0 O sY ANALYSIS TO >4 (1 YRS. CYCLES PERFORMED ROO O (Electro-Mechanical Equip. only) E.qut v. Me a+- 15B"F is de.+ermi ned
'o O to e rn &l lifc REVIEWER- / 7/ [/ ). ML DATE: I f bO /
R: Test Report Page No. Reference 7/1/g1
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. BBM -02. SHOREHAM NUCLEAR POWER STATION-UNIT 1 p SPEC. TITLE _ C ARIScQ M INRCR OPERATED VAbjES SPEC. NO. M-NY P.O.N050~2-- VENDOR VEN TEST ITEM DESC. Lim iYO rn o c' M OV MAKE Li mi Yn t-(' O P MODEL SM B F_5 Ae lianc e.bC, class M VENtORTESTREPORTbO. 60058 + Ano E. Bnoo9 APPLICABLE STANNARDS ' TEST REPORT NO. IEEE - 9 M _"/ E TEST METHOD % fiFfit1Ell~TCS YiO G IEEE - 323
- 7 l DOCUMENTATION AC EPTABILITY hrcP Se e co m me r +s &nri soec'Off \a IEEE -
pg g j p g g y_ g g g g. ,g y . g NUREG 0588 CAT. T QUALIFIED LIFE >4/ O u r3 I TEST SEQUENCE (R: &_(c- 9 (6000@ )
- 1. Ther mal Aainn 6.
- 2. Merhan'iratU Adina 7.
- 3. AAciiPLticn AcJm" 8.
- 4. 8Pmmir TcSti NG 9.
- 5. Erwi ron rt1e n-t Al -Yest 10.
TEST ENVIRONMENT (R: nn,in [fEOOO b O APPLICABLE
)
IO ENV. ZONES TIME O-l h r l-7 hr E-4hr L4**4hr 'I - En hr5 RAD TEMP. *F 12.0 +34 0 340 S30 SIB EIZ PRES. PSIG O -> (A (c8 +lnd 104+$ EloM3 O T/P R.H. /GO % OP. TIME DEMO 2.3 h r3 ACC/PERF DEMO RADIATION AGING (R: on 7 ( f>O O O b ) THERMAL AGING (R: (v1. In + 4nnM1. [800b) 1O DOSE RATE - RAD /HR 140to AGED TOrSIMULATED Stater On1Q d LIFE OF / Ot5 vRS. DOSE PRIOR TO ENV. TEST l V. l O RADS BASED ON AMBIENT I DOSE DURING EW. TEST - RADS AGING TEMP./ m n DOSE i z i n'3- RADS DURATION I SO c / In n CYCLE AGING (R: nn 4 (ROOOM )
~ * '
ra Actudhr [80GS*[ CYCLES REQUIRED 5OO yg [] 13"I g, g CYCLES PERFORMED 2.00Y c viv. ye cteeived b p repo rtio
; (Electro-Mechanical Equip. only) y REVIEWER: ,
6 (> l. , E DATE: l2 !/ / R: Test Report Page No. Reference 7/1/81
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 99V-O3 SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE CA ( bon $Yed* l Yd lV 6 - M O\/ SPEC. NO.SMI-98V P.O.310CO2. VENDOR VP (r'i n TEST ITEM DESC. Urn l' +n rar e M Os/ r MOTo6t AC,TUATCti SMB-0-45 MAKE L. .I rn i 40 FO U e. MODEL VENDOR TEST REPORT NO.80058+ Acob- PtdO3 M O M W Werm Retidner.Ac d WaW lAu. h -/ b#M% Motor.T] APPLICABLE STANDARDS TEST REPORT NO. IEEE - % 2 - l972 TEST METHOD 8t*Or pFnt1 A \ TFMTs'/'VT _ IEEE - O E.3 - l N I DOCUMENTATION ACCEPTABILITY Accen+ak 9 f" Ct3 m (Y) F rNA -. 90e'e i di ' IEEE ~ rhorf i r o n s - _ E Q R E F - % V 'R NUREG 0586 CAT. IT QUALIFIED LIFE 4./d V r,3 i
)
TEST SEQUENCE (R 41C1 7 -1 O ( BOO 05)
- 1. Th ermM AairYT 6.
- 2. MechAnieb Mins v v 7.
- 3. AAciiation AMna 8.
* .u s) * --
- 4. 91 es m t c A& t n G 9.
- 5. l~ nvi e on rne ntA Tes4 10. _
S TEST EfNIRONMENT (R _ O(1 1n ( 6000N ) ,\PPLICAPLE 4 I O ENV. ZONES TIME O .5hr .5- ?_hr E-Ulhe 24-25hc 2She -IGdap RAD G, H; L, M, O TEMP. *F Edo 2!'/w120 7.60 2 8'sA-100 2.00 PRES. PSIG 2.5 7'5 - 10 T/P i 2. 9. 7.9, In. R.H. InO
- 12;I4 M OP. TIME DEMO l A el a s ACC/PERP 0T:10
-m_--
RADIATION AGING (R: n r1 9 [ @ A O C b )l THERMAL AGING (R: rn ".1- (B^COMM8 rM2h iU ro - DOSE RATE l I lO b RAD /HR AGED TO SIMULATED LIFE OF P, .31 day DOSE PRIOR TO EfN. TEST 2.XlO RADS BASED ON AMBIENT DOSE DURING ErN. TEST RADS AGING TEMP./
'IDTAL DOSE ~
2,. X l ()Y RADS DURATION 165 / 20o [l99.S h CYrLE AGING (R: ryt 4 *R I60003 ) ) REL HUMID M fM % 5O ED CYCLES REQUIRED $O O B S pg_ CYCLES PERFORMED _/303 12-15 60055] (Electro-Mechanical Equip. only) Equiv. %e in 10400' o btained by p ro p orf TO n(<16 Eo-f hermal life +'iGurs REVIEWER: /M [l). b/A DATE: /2 / R: Test Report Page No. Reference 7/1/81
I ENVIRONMEtrIAL QUALIFICATION
SUMMARY
NO. 20/8 Revision O SHCREHAM NUCLEAR PCWER STATION-UNIT 1
. SPEC. TITLE SPEC. No. $/HMS P.0.31001O VENDCR /$1*>nf4e. b1 as w r TEST ITEM DESC. ht"; f o f .$ w e ?t r' MAKE , 34errD4L# MODEL S.I.I VENDGR TEST REPORT NO SAtk.rodcf Necab r/4 'N 9 3 ._ _ _ _
APPLICABLE STANDARDS TEST REPCRT NO. .3l2/$-A IEEr 322-/97/ , TEST METHOD $ FM4T( IEEE DOCUMENTATICN ACCEPTABILI"'Y
~
19CCC/17ML ef IEEE - NUREG 0588 CAT. .Z QUALIFIED LIFE ( )'er 8v 4ud4YSlf TEST SEQUENCE (R: 24t#todstf - 99f_3 )
- 1. Fue;c.rronede 6.
- 2. G me /p~anermn a. n 1.
- 3. A ,., e n ., %
- 8. _
- 4. 9.
- 5. 10. . ___ ___
N TEST E!NIRCNMENT (R: bles 04( g"- 9 99,"C_ ) APPLICABLE
'j ENv. :CNES TIME 84/#3 pan (,,
TEMP. *F 2/2 PRES. PSIG .27 7fp / R.H. /00 % % CP. TIME DEMO /4 //4 ; ACC/PERP DEMO '2, ? 95 / C'5 88 RADIATICN AGING (R:EDIC*c A ds3s oor-ca) THERMAL AGING (R: g;* @ <. /), M? o -oc / . r/ , ) i LCSE RA'"E A/c a> r RAD /HR AGED TO SI.WI.ATED ! LIFE CF A 1 e p> .:- YRS. ! DCSE PRICR TC Eh"J. *EST Alo a> sr- RADS 3ASED CN AMEII:,"O n, e.,. .,URINu
,, " 2 CF . l04 **' '.
Z:U. TEST U o s1 *f RADS
- AGING ~E:G.l l"CTAL IOSE 3 V /C' St Audty3 / 5 RADS N#
l 0?C E AGI::c (R: /h,msoaty (f 99 g i E* EMIDIU O Od F 3 4 - t C"CLES REQUIRE: Um arnwuSa I~ s-m f .50f.? E5_3
~~ m -a-> - o ,, _ . z.a . 'C"CLES ?ERFCRMEO /2 i (V) j 'EIect:0-Me:hanical Eq np. Only l
Rr/IrdER: ;AT;: /2,d/ 3 R: Test Reper: Face No. Reference Snes! ' : '
ENVIRCNMENTAL QUALIFICATICH
SUMMARY
NO. TCE/ Revision C? SHOR2 HAM NUCLEAR PCWER STATICN-UNIT 1 m SPEC. TITLE SPEC. NO. 6N/-or23 P.O. 3I001 O VENDOR dePMFAt. 8 Eft:##/c. TEST ITEM DESC. / /*/STON Suvrep MAKE S4tt.r0 dtF~ MODEL D2N VENDOR TEST REPORT NO. SdetS oAe 8ecerNee 9 993 _ APPLICABLE STANDARDS TEST REPORT NO. 'RO2/- A IEEE ?? J - /97/ TEST METHOD TcFA#4rr IEEE DOCUMENTATION ACCEPTABILITY IEEE AU i~M/MJ" NUREG 0588 CAT. C QUALIFIED LIFE 8 /#.s 6 Y' Aw4l VJ I I TEST SD'UENCE (R: $Nn04s- 9f93 f )
- 1. F~vove r w A u' 6.
- 2. Srvnonl/~moeAt hr *1.
- 3. /~ve, o s a. fe:7- 8.
- 4. _ 9.
- 5. 10.
TEST ENVIRCNMENT (R: d4REfoWF Nf3 ) APPLICABLE ENV. ZCNES TIME $ NRf RAD G,)/ TEMP. *F 2 /2 PRES. PSIG ,25 T/p j,/O,fy R.H. /Co 7o % OP. TIME CEMO 8 /r'c.t ACC/PERF DEMO ((r /S M RADIATICN AGING (R (D) (Au- Ah &R>ee/-d/1 ) THERMAL AGING (R:605 C4u AJ. 4620w/- 3/4 ) I DCSE RATE AleAlf RAD /HR AGED TO SIMLU TED LIFE CF 00 4 YRS. DOSE PRICR TO E!N. TEST N04 RADS 3ASED Ct! AMBIENT l CCSE ::URING
~^~ , ~". Joy --
- t I U . "'EST N 0815 RADS f AGING TE.v./
To AL DCSE 34 to# dy Au RA:S OUR^T C" U# ! CvCLE AG!nG cR kev.sou qq93 3 R:L HUMID:~ NG s CvC:.ES RE;c!RE: Uooereeu,m o NOT^G:?,gS3!FI:D _ j y ,um .S.o .. 60 ,,R CvCLIS FEFJCF;'ED l'2 +
; Electro-Mecnanical Equip. Only l Fr/IEWER: > d[ 2AT : 25y3/
R: Test Reper: Pace ';c. Reference ShE9; E Of /2
ENVIRONMENTAL QUALIFICATICN
SUMMARY
NO, 3025' Revision _C SHCREHAM NUCLEAR PCWER STATICN-UN!T 1 SPEC. TITLE SPEC. NO.S//}-ME _ P.O. 3l00l0 VENDOR 60/dG4t. $LCCT9'l' j TEST ITEM DESC. hGr!909 Ir.x/ / TE. N MAKE As9/Pd rat.F" MODEL M/// VENDOR TEST REPORT NO. 84er3 car 40e500?? 999 "A _ APPLICABLE STANDARCS TEST REPORT NO. M26 - E IEEE 32_1-/97/ TEST METHOD $6PA#dTE IEEE DOCUMENTATICN JCCEPTABILITY
~
M Ce s't*>A 6L. 5 IEEE NUREG 0588 CAT. _IZ' QUALIFIED LIFE 8 /gpes:. of e3sve9ty_sif TEST SEQUENCE (R Serr34/ #' 9 973 )
- 1. k m rookom ,
6.
- 2. f re9wn 8;mee rto ar 44. Idr? 7. ,
- 3. Gr r m.Ar. 8.
- 4. 9. -
- 5. 10.
i TEST ENVIRONMENT (R: -84Ad 0A r - 7 793 ) APPLICABLE ENV. ZCNES TIME /[ ##l RAD 6
#~
TEMP. *F 2/2 / PRES. PSIG ,2I T/P / R . E .- J 0d */o % CP. TIME DEMO [ ##_f ACC/PERF DEMO /. 7 N MM&~ il i RADIATICN AGING (R:EDS CAtZ ua G30-00hP72) *HERMAL AGING (R:eos (4u oo /jfD@/-022 ' 1 DCSE RA?I _ klea'e 14AD/HR AGED TO SIMULATED I LIFE CF Ajoug YRS. l DOSE PRICR TO i ! ENV. TEST A!e ed" PADS 3ASED CN AMBIENT uCS,. c CURING 75.9 CF /C7 Y #P 'F l E!."J. TEST Aj ede- RADS AGING "'EMP./ . TOTAL DCSE 5 x lo ' h /6 vse, RA:S " 22 " d* " . CYCLE AGING,(R: de cue c @@T )
*
- I i '
CYCLES REQUIPID O /ADar7EAPAr /Uc:a N ^ 3Y ANALYSIS TO ./, RS CYCLES PERFCRMED /2 , s (Elect.re-Mechanical Equ:.p. only; l l REVIEWER: _ ..A~... /2/?/-[6 R: TOct Report Page No. Referenca EU660 Cf _ l
. - _ _ . _ . - - _ . = _ _ _ - . _ . .. - _- _ . __ . . - . . . .__
i FNVIRONMENTAL QCALIFICATION
SUMMARY
NO. 202 7 Revision CD SHOREHAM NUCLEAR POWER STATION-UNIT 1
% SPEC. T!?LE SPEC. NO.$4/-dD_5 P.O. 3 00/O VENDOR SeAlegde [t e r_TA'ic TEST ITEN DESC. 1 % P r~es & N ti k AN5Svee /**tto471a)6 $r,,,si72.17 MAKE /7 7~ d#94TO 4 MODEL '2 8 b h 8 9#4 VENDOR MST REPORT NO. /77* 8487DA) 79Y9,/2/7 2 Asa 43 -2 @?'4-/ _
APPLICABLE STA N TEST REPORf NO. 2C2 7-4 f J'C2 78 I IEEE .3 22 -/9 7/ TEST METHOD <~ m y IEEE 3N ~/9 7 f' DOCUMENTATION ACCEPTABILITY Aceareaw IEEE NUREG 0588 CAT. T QUALIFIED LIFE 4 d Vendi dyr Akon wsc TEST SEQUENCE (R: b OWod ) Sprim; 4f9R/2/~71 / 7T(fWt rike R7-? tPA-/
- 1. h ersuAL 77Ex r- feautAnnes> ) I /pd arneN d henen.At feti
- 2. $1 m Tesr~ Z ke7somm. 5 ,
- 3. Svec rio ar *%. & hiernrremo)1 RamT'* *
. . 4.. + %n nr4 Ssr
- 5. I $r/S***e
, TES ENVIRONMENT (R /77~ 8MMa/ 19 99. /2/7 e 2 ) APPLICABLE ENV. ZONES TIME 4 Wes RAD AN nnP. F p ir_ *f PRES. PSIG 7 /4/ H/C- T/P / , 2 . /O / '> _
/0$*/a R.R. %
OP. TIME DEMO 6 86 ACC/PERF DEMO I!O RADIATION AGING (Ra fvemas D-29@A -//) THERMAL AGING (R: EtM d'= Alo osIo@/olo ) fD5 CesL jar $10-ooldC/O DOSE RATE /Y/O' RAD /HR AGED TO SIMULATED LIFE cr /halv YRS. DOSE PRIOR.TO g ENV. TEST S 4 10 RADS 3ASED CN AMBIENT DOSE DURING OF Md T ENV. TEST dl0Al#" RADS AGIUG *l 3xtos Gyrdsr/ }}g , TOTAL DOSE __f ( po7 Sy A>4c.vfr5 RADS CYCLE AGING (R: Se r>as CD8/9-/ ) CYCLES REQUIRED Ijalar-r>+Per eN(O gg , CYCLES PERFCRMED 3b (Electro-Mechanical Equip. only) REVIEWER: _
# : ATE: //!// 2 t
R: 73SO Report ? ace MO. Eeferen03 eet Of
._- .- . . . - . - - - _ _ . _ - - . . .-..- __ - .. . . = _ _ _ _ _ _ . . . -
ENVIRONMENTAL QUALIFICATION
SUMMARY
NO. 303E Revision g SHOREHAM NUCLEAR POWER STATICN-UNIT 1 s SPEC. TITLE SPEC, NO. .SHl-COS P.O. 3 f oo tD VENDOR / Teases,4t. tr un ree,e TEST ITEM DESC. 8t?icif u4 #" S u> t Y C. H MAKE { TAT"I C - C- 41 o i /. MODEL 6V[6N) $stiSS VENDOR TEST REPORT NO. 1/f rs Ams. /. 4Soa*7ePres 7e" se tr/rt[4 /t/rpe Cr- Ale 30203 -/ _ APPLICABLE STANDARDS TEST REPORT NO. 3 031 - A IEEE 323-/97/ TEST METHOD .$sPM47F IEEE DOCUMENTATION ACCEPTABILITY Aue97A6t G IEEE NUREG 0588 CAT. :!!~ ' QUALIFIED LIFE /L47pe) TEST SEQUENCE (R VWs4 ? 30203-/ )
- 1. F,uc.victvri. -
s.
- 2. AtetsjaE I TEkker JLGl f4JmIQ1W 7.
- 3. IA/S Pt=cx toA)
- 8.
- 4. 9.
- 5. 10.
TEST ENVIRONMENT (R VstiM 6
- So "to3 -/ ~ ~ l APPLICABLE fin 80a AM&G \ fI4 U.to fM& { L<'o n 0AW N _
TIME h N/23 h Atti _ b NR5 RAD [1 l TEMP. *F 212. b 1 M. 0E' I 211Y PRES. PSIG .25 I . 05 0116 , L5 I . 05 P5t I,
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R.R. I n /) h %
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NO. 30 9 Revision O SHOPI. HAM NCCLEAR PC'JER STATICN-CNIT 1 SPEC. TIT E SPEC. NO. (Ul-013 P.C.3iSoIO VCIDOR /k're 1 N 4 8: /~=~_m* TEST ITEM DESC. / <.0/h o'~r t E/FL- .~~r> /2 8 C_ A7 <t. MAKE O. () .
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. SPEC. NO. $///-DO3 P.O.110010 VENDCR 6 603MP AL. G UEt_T0 J C.
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DNIRCRENTAL QUALIFICATICN SQceARY NO. '3075 Revision O SECREHAM NCCLFJ.R PCWER STATICN-UNIT 1 SPEC. TITLE (m SPEC. NO.f#/- 003__ P.O. .'2/Co /C VENDCR $ mr>Fe4<, 8r.ey.rse ir. TEST ITEM DESC. Souvo/o l/A_ the MAKE A S C- o MCDEL //7~- X- 9S2 0 -4 23. VCIEOR TEST REPORT NO. b_ r eit. Md'Poe7" Mo ~> #2 C 2 , de / _ APPLICABLE STANDARDS _ TEST REPORT NO. M96-4 IEEE ~> 2 3 - /G 7/ TEST ETHCD Groep A7:-J IEEE DOCUMENTATION A W TABILITY IEEE - As r r:a rna c:
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NO. ~2 / 2 8- Revision A SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE SPEC. NO. FEM /-CO.i P.O. 210O/0 VENDOR 62ap>d9P44- b6c 7F/c TEST ITEM DESC. [4ev M4/.S* //7~est Am/a [c E* Ex/7" MAKE A# cr i era MODEL C 79- 60 M VENDOR TEST REPORT NO. /le "T237 d474 NO Atb _ l APPLICABLE STANDARDS TEST REPO1E NO. IEEE 3~23-/9-g TEST METHOD IEEE DOCUMENTATION ACCEPTABILITY IEEE , NUREG 0588 CAT. 7Z* QUALIFIED LIFE TEST SEQUENCE (R: )
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NO. bI 2.9 Revision O SHOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE SPEC. NO.G lM P.O.3l00( 0 VENDOR b ervretet. b rer7e/C. TEST ITEM DESC. /6Ver _ 7"~f /4/t45 /h / 776/ MAEE I Pr I3 A(2.T o^) MOoEL 7 G, o VENDOR wST REPORT NO. AN[ T 3J0 -2//t/ _ APPLICABLE STANDARDS TEST REPORT NO. 3/29 4 IEEE 3 3 3 * / 't"W TEST METHOD SepAe479-IEEE DOCDMENTJCION ACCEPTABILITY '
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ENIPO!JC CAL QUALIFICATICN
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NO. bI4O Revision O SECLEHAM NCCLEAR PCWER STATICN-UNIT 1 SPEC. TITIZ k SPEC. No. SHI- 003 P.O. 2>f CCI O VENDCR 6'6bJ MAL EL GCRIC TEST ITEM CESC. i EV!' t. SW ITC#I MAXE //IAf-A/6790L HCDEL 6. 8 ~7 61 - I V - M P/-, - M I 4 H'1' VCIDOR TEST REPORT NO. dW.c (so ,8EPo# ef/o 4f P 2 3 $~- / O-> <f i e d 4 _ APPLICABIS STAiDARDS TEST PIPORT NO. 3/42- 4 IEEE 32 'b - I 9 7 4. TEST METHCD < 5:0ooci A 9 IEEE 6 44 - IMD DOCCMc G TICN ACCEPTABILITY
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CYCLES PERTCR:ED / O . 60 o (Electro-Hechanical Ecuip. cnly) REVIDiER: I eWh wbmW- OATE:/7/l//E! R: Test Report Page No. Reference Sheet of
ENVIRONMENTAL QtDLLIFICATION
SUMMARY
NO. ?/VV Revision o SBOREHAM NUCLEAR POWER STATION-UNIT 1 SPEC. TITLE SPEC. NO. !J} l-003 P.O. 2109/0 VENDOR doneut [t.arnr>e re TEST ITEM DESC. , l atver_ "7"AAsifAf/ /7FR MAxE /rr R.4.erou MoDEL 34 3 l VENDOR TEST REPORT NO. /) b C)>vr/torv e :/t/TM L 7E" s 7 h _ APPLICABLE STA4 N TEST REPORT NO. IEEE 323-/ W/ TEST METHOD IEEE DOCUMENTATION ACCEPTABILITY IEEE NUREG 0588 CAT. I QUALIFIED LIFE TEST SEquz.m.s (R: )
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NO. _3 9 00 SHOREHAM NUCLEAR POWER STATION-UNIT 1 Revision 1 SPEC. TITIC SPEC. No. T///-co~? P.O. 3/OQ/O VENDOR b7EdestA6 8 (c."Dt'l C TEST ITEM DESC. Mump No rvet MAKE dewenede NEC Me MCCEL Sk 324 Ak 2 o14-VENDOR TEST REPORT NO. Alo Tcsr 04M Fer/No _ APPLICABLE STANDARDS TEST REPORT NO. IEEE 2 2.7 - /f 4 / TEST METscD IEEE DOCUMENTATION ACCEPTABILITY IEEE NUREG 0588 CAT. C QUALIFIED LIFE TEST SEQUENCE (R: )
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SUMMARY
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SUMMARY
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a ,a - E ar . .~ as- - --+ .-1 - W - - . u--- l APPENDIX C ENVIRONMENTAL ZONE MAPS I i i l l l l l l
APPENDIX C ENVIROhMENTAL ZONE MAPS The drawings which follow define the areas of the plant determined to be- in a potentially harsh environment. The drawings divide the plant into apatial zones. Radiation zones are identified with letters while pressure / temperature zones are identified with numDers. The radiation zones snown on Figures C-1 through C-15 are the same as Figures II.B.2-1 through 15 in the NUREG-0737 NRC submittal, and are included herein for convenience. Temperature and pressure zones are shown on Figures C-16 through C-22. O l l O C-1 1
INDEX OF ZONE MAPS
) Title Fiqure No. Zone No.*s Radiation Zones, Section View, C-1 A,B,C,D,E, Reactor Containment F,H Radiation Zones, Plan El b* to C-2 G 20' North, Reactor Containment Radiation Zones, Plan El 88 to C-3 G 20* South, Reactor Containment Radiation Zones, Plan El 20* to C-4 G 40' North, Reactor Containment Radiation Zones, Plan El 20* to C-5 G 40* South, Reactor Containment Radiation Zones, Plan El 40* to C-b G,L 63* North, Reactor Containment Radiation Zones, Plan El 40' to C-7 G,L 63* South, Reactor Containment Radiation Zones, Plan El 63* to C-8 G 78* North, Reactor Containment
\_/ Radiation Zones, Plan El 63* to C-9 G,L 78
- South, Reactor Containment Raalation Zones, Plan El 788 to C-10 G,H,M 112' North, Reactor Containment Radiation Zones, Plan 788 to C-11 G,H 112* South, Reactor Containment Radiation Zones, Plan El 76* to C-12 T 96*, Reactor Containment Radiation Zones, Plan El 112* to C-13 H,J,K,N,P 150' North, Reactor Containment Radiation Zones, Plan El 112* to C-14 H,J,N,P 150' South, Reactor Containment Radiation Zones, 150* and Partial C-15 H,N,P,Q,R,S Plans, Reactor Containment Temperature and Pressure Zones, C-16 1 Plan El 8' to 40*, Reactor Containment C-2
Title Fiqure No. Zone No.'s Temperature and Pressure Zones, C-17 2,21 Plan El 40* to 638, Reactor Containment Temperature and Pressure Zones, C-18 2,3,4,5, Plan El 63* to 788, Reactor 6,7 Containment Temperature and Pressure Zones, C-19 8,9,10, Plan El 78
- to 112 8, Reactor 11,12 Containment Temperature and Pressure Zones, C-20 13,14,15, Plan El 1128 to 1508, Reactor 10,17,21 Containment Temperature and Pressure Zones, C-21 18,19,21 Plan El 150* to 175*, Reactor Containment Temperature and Pressure Zones, C-22 20,22,23 Section View, Reactor Containment O
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- 2. 3EE FIGURE C-22 FOR PRIMARY TEMPERATURE AND PRESSURE ZONES CONTAINMENT TEMPERATURE 2,21 AND PRESSURE ZONES PL AN EL. 40'- 0" TO 63'- 0" O REACTOR CONTAINMENT SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFIC ATION REPORT FOR CLASS 1E ELECTRICAL EQUIPMENT
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d REACTOR CONTAINMENT SHOREHAM NUCLEAR POWER STATio-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS 1E ELECTRICAL EQUIPMENT
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" stra= " ' ' ' ' to ""*"' SECTION VIEW REACTOR CONTAINMENT SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUtPMENT
1 j
- l i
APPENDIX D RADIATION, TEMPERATURE, AND PRESSURE DATA I i l l l 1 l 1
APPENDIX D RADIATION, TEMPERATURE, AND PRESSURE DATA The normal and accident service conditions are tabulated and graphed with respect to time as shown on the tollowing sheets. The normal service conditions for primary and secondary containment temperatures, ressures, and levels of humidity are l listed in Tanle D-1 as taken from FSAR tad 1e 3.11.2-1. The reactor building primary containment environmentai service conditions and the secondary containment radiation conditions are tabulated on Figures D-1 and D-2, respectively, which are taken f rom Figure; II.B.2-16 and -17 in the NUREG-0737 submittal to the NRC and are included herein for convenience. Radiation curves are shown on Figures D-3 through D-20. Temperature curves are shown on Figures D-21 through D-40. Pressure curves are shown on Figures D-41 and D-42. Curve D-43 indicates the pressure transient in the secondary containment due to a LOCA and is reproduced from an FSAk tigure. O o G D-1
INDEX OF ENVIRONMENTAL TA8LES AND FIGURES Title Table No. Normal Pressure, Temperature and D-1 Humidity Conditions Title Fiqure No. Reactor Building, Primary Containment D-1
- Environmental Zones Reactor building, Secondary Containment D-2 l Normal and Accident Radiation Zones Reactor building, Primary Containment D-3 Radiation Level for Zone A Reactor Building, Primary Containment D-4 Radiation Level for Zone B Reactor Building, Primary Containment D-5 Radiation Level for Zone C Reactor Building, Primary Containment D-b i Radiation Level for Zone D Reactor Building, Primary Containment D-7 Radiation Levels for Zones E and F Reactor Building, Secondary Containment D-8 Radiation Level for Zone G Reactor Building, Secondary Containment D-9 Radiation Level for Zone H Reactor Building, Secondary Containment D-10 Radiation Level for Zone J Reactor Building, Secondary Containment D-11 Radiation Level for Zone K Reactor Building, Secondary Containment D-12 Radiation Level for Zone L Reactor Building, Secondary Containment D-13 i Radiation Level for Zone M i
Reactor Building, Secondary Containment D-14 Radiation Level for Zone N 1 O n-2
Title Fiqure No. Reactor building, Secondary Containment D-15 Radiation Level for Zone P Reactor Building, Secondary Containment D-1b Radiation Level for Zone Q Reactor Building, Secondary Containment D-17 Radiation Level for Zone R Reactor Building, Secondary Containment D-18 Radiation Level for Zone S Reactor Building, Secondary Containment D-19 Radiation Level tor Zone T Reactor Building, Secondary Containment D-20 Radiation Level Reactor Building, Secondary Containment Temperature D-21 Levels for Zone 1 Reactor Building, Secondary Containment Temperature D-22 Levels for Zone 2 Reactor Building, Secon'dary Containment Temperature D-23 Levels for Zone 3 Reactor Building, Secondary Containment Temperature D-24 Levels for Zone 4 Reactor Building, Secondary Containment Temperature D-25 Levels for Zone 5 Reactor Building, Secondary Containment Temperature D-2b Levels tor Zone 6 Reactor Building, Secondary Containment Temperature D-27 Levals for Zone 7 Reactor Building, Secondary Containment Temperature D-2 8 Levels for Zone 8 Reactor Building, Secondary Containment Temperature D-29 Levels for Zone 9 Reactor Building, Secondary Containment Temperature D-30 Levels for Zone 10 Reactor Building, Secondary Containment Temperature D-31 Levels for Zone 11 0 D-3 _ ..._ .. . J
1 Title Fiqure No. Reactor Building, Secondary Containment Temperature D-32 Levels for Zone 12 Reactor Building, Secondary Containment Temperature D-33 Levels for Zone 13 Reactor Building, Secondary Containment Temperature D-34 Levels for Zone 14 Reactor Building, Secondary Containment Temperature D-35 Levels for Zone 15 Reactor Building, Secondary Containment Temperature D-36 Levels for Zone 1b Reactor Building, Secondary Containment Temperature D-37 Levels for Zone 17 Reactor Building, Secondary Containment Temperature D-38 Levels for Zone 18 Reactor Building, Secondary Containment Temperature D-39 Levels for Zone 19 Reactor Building, Secondary Containment Temperature D-40 (s Levels for Zone 20 V Reactor Building, Secondary Containment Pressure D-41 Levels tor Zones 1-12 and 15-20 Reactor Building, becondary Containment Pressure D-4 2 Levels tor Zones 13 and 14 Simulated Pressure Transient in Secondary Containment D-4 3 O) V D-4 I
) - ____ - -- _ - -a
TABLE D-1 NORMAL PRESSURE, TEMPERATURE, AND HUMIDITY CONDITIONS SHOREHAM NUCLEAR POWER STATION - UNIT 1 Temper- Relative ature Humidity Area Pressure *F A I. Primary Containment
- 1. Area above shield -3 to 2 psig 150 max 40-55 wall to top of 127 avg drywell (Zone A-22)
- 2. Region adjacent to -3 to 2 psig 150 max 40-55 core (Zone B-22)
- 3. Under reactor -3 to 2 psig< 150 max 40-55 pressure vessel, I
inside of shield wall (Zone C-22)
- 4. Vicinity recircu- -3 to 2 psig 150 max 40-55 lation pump motors (Zone D-22)
[
- 5. Suppression cumn- -3 to 2 psig 150 max 40-55 Der air space (Zone E-23)
- 6. Suppression pool -3 to 2 psig 150 max 40-55 (Zone F-23)
II. Secondary Containment l 1. All areas except -0.5 to 0 60 to 104 50 steam tunnel and inches water MCC cubicles gage, static pressure ( 2. Main steam tunnel same as above 120 to 135 50 i (Zone ST)
- 3. MCC rooms El. 112' Atmospheric 80 to 104 90 (Zone N-21)
O 1 of 1 l
f l NORMAL ZONE PRIM ARY R ADI ATION TE M PER ATU RE HUMIDITY PRESSUF ARE A ABOVE 8.8 X IOs R AD y 4 p4 I I "# 100% FOR EXTENDED -3 TO 2 P1 A-22 SHIELD WALL TO TOP 6.3 X IO'8 12 7 F AVG. OFDRfwELL NEUT/CM 2 PERIO D S REGION ADJACENT TO 7. 0 X 107 RAD y B-22 CORE OUTSIDE OF 8. 3 X 10'* 150 F M A X SHIELD WALL NEUT/CM 2 UNDER RPV INSIDE OF 2.5 X I O* R A D y C-22 SHIELD WALL AND 1. 3 X 10' RE ACTOR PEDESTAL NEUT/CM 2 l.8 X 10 7R AD y VICINIT Y OF RECf RC. 0-22 2. 5 X 10'2 PUMP MOTORS N EU T/ C M M XIO*RADy WPRESSION 2.5 X 10" E-23 CHAMBER AIR SPACE 2 N EU T/ C M 3.5 X IO* R AD y SUPPRESSION POOL 2.5 X 10" F-23 2 N EU T/ C M Y U 1[ NEUTRON EQUlVALENT NEW TOTAL NOTES: ZONE RADSy FLUENCE RADSy 1. " NORM AL R ADI ATION"lS CUMUL ATIVE 40-Y F 4.OX10 3 1.1 X IO e 2." ACCIDENT RADI ATION"lS CUMUL ATIVE 6-6.3 X IO'3 N E U T/ C M* RADS y RADy 3. CONSIDER"NEW TOTAL RAD" COLUMN FOR y
- 4. THE EFFECTS OF THE NEUTRON FLUENCE 13 g 8.3 X 10'* 5.5 x 10 8 1. 76 X I O e 2
N E U T/C M RADS y RADy
- 1. 3 X 10' 8.68 X 100 1. 0 X I O s 2
N EU T/C M RADS y RAD y 2.5 X 10 12 1 67 X 10 4 1. 2 X I O s O N EU T/CM 2 RAD y RAD y 2.5 X I O l.67 x lO 3 1.OXIOe E N EUT/ C M 2 RADy RAD y 2.5 X 10" 1.67 X 10 3 1.OXIOe N EU T/C M 2 RAD y RAD y I i -
ACCIDENT (LOCA) TOTAL E R A DI ATION TEMPERATURE HUMIDITY PRESSURE RADI ATION 40 ~ I O OTo oto48 PSIG-Oto 6 HRS 8 l X 10 R AD y 3 0 F- 6 9 (SUPERHEATED) 4 8 tol5 PSIG-6HRSto4 DAYS g RAD $ IX10' RAD S 6 3 X 60'3 O - -4 D YS FIRST DAY 150 F 180 D AYS 1.7 X IOs R AD y I X IOe R AD y IXIO' RAD $ IXIO'RADg 8.3 X IO'" N EUT/CM 2 1 X I O' RA D y IXIO' RADS l . 3 X 10' 2 N EU T/C M 1.2 X IOe R AD y IXIO' RADS 2.5 X10 2 N EU T/C M 225 F- 0-12 HRS I X IOs RAD y 212 F- 12 H RS- I DAY IXIO' RADS 150 F- I- 7 D AYS 2.5 X 10" 2 90 F 180 D AYS N EU T/C M lXIOeRAD y IXIO' RADS 2.5 X 10" lI lI U N E UT/ C M 2 TOTAL 'AOMTH TO TAL R ADI ATION NEGLlbl8LE FIG. D-l REACTOR BUILDING PRIMARY CONTAINMENT ENVIRONMENTAL ZONES SHOREHAM NUCLE AR POWER STATION-UNIT I ENVIRONMENTAL QUALIFIC ATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT I l l
p I I ZONES G H J K L h NORMAL 3 3 RADIATION l.8 x 10 3
- 1. 8 x 10 3 l.8 x 10 1. 8 x 10 1.8 x 10 3
- 1. 8 x (R ADSE)
(40Y R) RE ACTOR BLOG ACCIDENT SUPPRESSION ( AIRBORNE) H YDROGEN RBSVS 24 INCH 8FT4 RADIATION POOL LOCA RECOMBINER FILT ER RHR PC (6 MO) WATER P80C PIPE Pl TIME (HR ) RAD /HR RAD RAD /H R RAD RAD /HR RAD RAD /HR RAD RAD /HR RAD RAD /HR O.0 1.96 +5 0.00 0.00 0.00 1.40+ 4 0.00 0.00 0.00 1.43+5 0.00 1.87+4 O.I 1.60 + 5 1.77+4 1.05+4 L22 + 3 3.14+ 1 1. 24+ 0 1.18 + 5 1.3O+ 4 1.33 + 4 7 2 8.80 + l 2.41 + 1 804+3 0.5 1.42 + 5 781 + 4 4.90 + 3 2.60+ 2 5.19 + 1 1.0 5 + 5 5.76 +4 9.54 +3 5.63+ 3 3t35+3 1.45+2 8.3 2+ l I.O l.16 + 5 1.42 + 5 4.57+3 5B8+3 6.52+ 3 8.53+ 3 7.23+2 2.78+ 2 8.65 + 4 1.05 + 5 7. 61 + 3 5.0 4.51+ 4 4.20 + 5 2.74+ 3 2.76 +4 6.14 + 3 1.34+4 3.3 4 +4 3.ll + 5 2.46+3 78 3 I.70 4 8.0 327+4 536+5 2.06+3 3.47+ 4 1.0 8 + 4 3.86 +4 2.40+ 4 3697 + 5 2.20 + 3 1 3
.24.O l.36+4 8.74 +5 1.06+3 5B1 + 4 3.36 +4 3.90 + 5 9.60 +3 6.41 + 5 1.07+3 f6 2 3 3 8.42 +0 4.87+4 720.0 1.00&3 2B246 9.48-4 3.45+4 4.36+ 1 2.10+5 9.52 +4 9.G+7 6.95 +2 1.96 + 6 2.77+ 1 4
2160. O 3.34+ 2 362+6 7. 4 + 0 2.34 + 5 1.40 + 3 1.27+8 2.43+ 2 2.52+ 6 1.30 - l 5 2 45
~
4380.0 1.60+2 4.14 + 6 9-9 3 45 3.37+0 2.45+ 5 791-I l.27+ 8 1.17 + 2 2.91 + 6 9.24-2 5.97+1 6.20+ 6 1.58 + 0 245+5 2.25-3 1.27+ 8 4.3 5 + l 3.3 8+ 6 7.25-2 (1 YE AR) 5 BETA DOSE RATE AND INTEGRATED DOSE- ALL SECONDAR TIM E (HRS) 0.0 0.1 0.5 'l.O 4.0 8.0 24.0 72.0 216 0
=s,a4re ,,,
0.0 1.0 i. 2 3.,e.02 5.31 2 1.22 3 i.68 3 2.26 3 8.iO. i i.07.i INTEGEGRATED DOSE O.0 5.79 +0 9.14 + 1 3.06 + 2 3.09+3 8.4 6+ 3 4.18 + 4 4.81 + 5 5.13+ 5 NOTE FOR PBOC CASE, USE ZONE H VALUES FOR ENTIRE REACTOR SECONDARY CONTAINMENT I e
I N P O R S T 3 3 8 10 1. 8 x 10 1.1x10 5 1.3 x 10 2.1 x 10 3 1. 8 x 10 6 4. 9 x 10 5 INCH MCC RWCU RWCU RWCU FPC& CU STEAM LC CUBICLE PUMP FILTERS HEAT ROOM TUNNEL E ROOM & TANKS EXCHANGERS fRAD ROD /HR RAD RAD /HRl RAD RAD /HRl RAD RAD /HRl R AD R AD/HRl RAD RAD /HRl RAD O.00 0.00 0.00
.58+3 2.32 + 1 1.24 + 0 B.11 + 3 8.84+1 2.41 + l SAME AS .04+4 1. 4 6 + 2 8.36 + 1 ZON E
- .85 + 4 3.0 2+2 1.10+ 3 SAME AS ZONE H I
.55o4 3.244 2.02+3 I.96 + 4 3.46 +2 7. 37 + 3 99+5 2.00+2 2.39 + 5 2BS+0 3.05 + 5 f.05o5 .06o5 1.08-2 3.06 + 5 06+5 2.25-3 3.06 + 5 CONTAINMENT ZONES 380 6570 8760 10950 1314 0 15330 17520 .78+0 3.20 + 0 1.7 7+ 0 9.78-1 5.42-1 3.00-1 l.60-1 R ACTOR BUILDING SECONDARY 5.4l+ 5 CONTAINMENT NORMAL AND ACCIDENT 31 + 5 5.4 6 + 5 5.49+5 5.50+5 551 + 5 5.52 + 5 RADIATION ZONES SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
I
, _j i.in to8 ) ,pgo gONE lI A
1 10,7. ______ _ _ _ _ ____ ______ I, to' l f.
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D*- ~
,os_ INTEGRATED TOTitL-RAD (ZONE B) a: -_.- _ _ _ --___ _ _ _ _ _. - - - .-- _ -- -- y 10 7 --
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408
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10 40 0 10 ' 105 10 3 10 4 103 lo s TIME -HOURS s wCNTHS 2 YEARS 40 VEARS i NOTES: THE FROFILE FOR THE INTEGRATED TOTAL RADIATION SHOWS THE 2 YEAR LOCA PROFILE BEG lNNING AFTER THE 40 YEAR l TOTAL (LINE o-b) l IT IS ASSUMED HERE THAT THE LOCA FIG. D-5 OCCURS AFTER 40 YEARS AT NORMAL OPERATION AND THE DOSE IS CUMULATIVE REACTOR BUILDING
- PRIMARY CONTAINMENT RADIATION LEVEL FOR ZONE C f (,i/
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SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
,oe /O .
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SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL OUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
toe, (h ; f I 7 40 8o g .
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lO 10 100 go l got so3 got 3o5 so6 TIME-HOURS 6 MONTHS 2 YEARS 40 VEARS NOTES: THE PROFILE FOR THE INTEGRATED TOTAL RADIATION SHOWS THE 2 YEAR LOCA PROFILE BEGINNING AFTER THE 40 YEAR TOTAL (LINE o-b) IT IS ASSUMED HERE THAT THE LOCA FIG. D-7 OCCURS AFTER 40 YEARS AT NORMAL OPERATION AND THE DOSE IS CUMULATIVE PRERY REETOR CONTAINMENT WILDM'ATION RADI LEVELS gm FOR ZONES E E. F i
'") SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT l
1
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- 1. ACCIDENT DOSE FROM LOCA ONLY
- 2. SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE ACCIDENT DOSE + FlG D-8 40 YEAR NORMAL DOSE (LINE o b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL
. FOR ZONE G
- t. SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT
l n N,,/ I 4380 HRS , _ i so? _ a lo s g _ i . E [ i h _ I y .
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- LOCA RADIATION-RAD (ZON E H) -
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IO'I 10 0 10' 40 2 go 3 10 ' 10 5 10 6 MONTHS 2 YEARS 40 YEARS TIME - HOURS NOTES 1 ACCIDENT DOSE FROM LOCA ONLY 2 SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE: ACCIDENT DOSE + FIG. D-9 40 YEAR NORMAL DOSE (LINE o-b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL p FOR ZONE H V SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QU ALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT
ios_ b) !~ %/ _ 7 4380 H8tS I 107 _
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- 1. ACCIDENT DOSE FROM LOCA ONLY.
- 2. SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE ACCIDENT DOSEf FIG" D-10 40 YEAR NORMAL DOSE (LINE o-b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL r~N FOR ZONE J ( ,) SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
j i27xlO' RADS
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to8 bh ! 's f . u 4 380 HRS. to? ! f LOCA RADI ATION-RAD (ZONE K)w l }
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ic i to 8 lo 3 so* to' c' TIME - HOURS 6 MONTHS 2 YEARS 4oVEARS NOTES
- l. ACCIDENT DOSE FROM LOCA ONLY.
- 2. SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE ACCIDENT DOSE + FIG. D-1I 40 YEAR NORMAL DOSE (LINE o-b). g CONTAINMENT RADIATION LEVEL FOR ZONE K p/
q, SHOREHAM NdCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EOUIPMENT
loe_ b i 4380 HRS lo! _
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- 2. SEE FIGURE D-20 FOR P80C RAD.
- 3. INTEGRATED DOSE = ACCIDENT DOSE + FIG. D-12 40 YEAR NORMAL DOSE (LINE a b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL FOR ZONE L {)) q SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT 1
soa_ U : ,
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to io O so l no t go 3 go t io s ,o s TIME-HOURS sMoNTHS 2 YEARS to YEARS l NOTES I ACCIDENT DOSE FROM LOCA ONLY.
- 2. SEE FIGURE D-20 FOR PBOC RAD.
1 INTEGRATED DOSE ACCIDENT DOSE + FIG. D-13 40 YEAR NORMAL DOSE (LINE o-b) REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL n FOR ZONE M l h SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT
io s u (VD i 4380 HRS
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io'I ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' l ' ' ' ' ' ' ' 'r'tt' 1 1t f t so*8 so O to 8 to t io s ' ' ' ', o' e io s ,o s TIME - HOURS 6 MONTHS 2 YEARS to YEARS NOTE 9
- 1. ACCIDENT DOSE FROM LOCA ONLY.
- 2. SEE FIGURE D-?O FOR P80C RAD.
- 3. INTEGRATED DOSE: ACCIDENT DOSE + FIG. D-M 40 YEAR NORMAL DOSE (LINE a-b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL p FOR ZONE N i SHOREHAM NUCLEAR POWER STATION-UNIT I
- ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT
io s O 5
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- 1. ACCIDENT DOSE FROM LOCA ONLY.
- 2. SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE ACCIDENT DOSE + FIG. D-15 40 YEAR NORMAL DOSE (LINE o-b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL FOR ZONE P SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
i.3 a lo s _ ios I (] (j 5
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- 1. ACCIDENT OOSE FROM LOC A ONLY.
- 2. SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE: ACCIDENT DOSE + FIG. D-16 40 YEAR NORMAL DOSE (LINE o-b).
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL A FOR ZONE Q
- b. SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUAltFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
los_ j
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t 4380, HRS I 10 ' I : ' l to. = g i E : A o_m__ _ _ __. _ _ _ _ _. _ _ _ _ _ ._____._____
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- l. ACCIDENT DOSE FROM LOC A ONLY.
- 2. SEE FIGURE D-20 FOR P80C RAD.
1 INTEGRATED DOSE ACCIDENT DOSE + FIG. D- 17 40 YEAR NORMAL DOSE (LINE o-b). REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL O C/ FOR ZONE R SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT
loe ; g
- 4380 HRS
/ ,7 IO' -
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- 1. ACCIDENT DOSE FROM LOCA ONLY. a
- 2. SEE FIGURE D-20 FOR PBOC RAD.
- 3. INTEGRATED DOSE ACCIDENT DOSEt FIG. D-18 0 40 YEAR NORMAL DOSE (LINE o-b).
REACTOR BUILDING. SECONDARY CONTAINMENT RADIATION LEVEL s FOR ZONE S g~j
\' SHOREHAM NUCLEAR POWER STATICN-UNIT I ENVIRONMENTAL QUALIFIC ATION REPORT FOR CL ASS lE ELECTRIC AL EQUIPMENT
no e I (n i
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1 I f 4380 HRS. so? _
== a, ll LOC A RADI ATION - RAD (ZONE T) p-106 s P .
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- 2. SEE FIGURE D-20 FOR P80C RAD.
- 3. INTEGRATED DOSE ACCIDuNT DOSE + FIG. D- 19 40 YEAR NORMAL DOSE (LINE a b)
REACTOR BUILDING, SECONDARY CONTAINMENT RADIATION LEVEL q FOR ZONE T i ) SHOREHAM NUCLEAR POWER STATION-UNIT l k/ ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT
to e i l. '.O} t : 4380 HRS
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'PBOC RAO' APPLIES TO ALL SECONDARY CONTAINMENT (RBS) ZONES FIG. D-20 REACTOR BUILDING, SECONDARY CONTAINMENT PBOC RADIATION LEVEL
(] \v SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CL ASS IE ELECTRIC AL EQUIPMENT
180 HIGH ENERGY LINE BREAKS
- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
150 - NOTE 1
\ LIMITING PROFILE g \ FOR MELB o \ NOTE 2 E 140 $ N a N = N E 130 - \
d 6"RWCU N
" N N
[U 120 - LIMITING PROFILE FOR HELB
\ N N
N l N 11 0 - N IO" H PC I \ g 104 - - - - - -
\
100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPER ATURE RISE WITHIN 700 SECONDS FIG. D-El FR M ME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMIT!hG PROFILE FOR CONTAINMENT TEMPER ATURE "EL0, ALSO ENVELOPES gL9 LEVELS FOR ZONE 1 nv SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT FOR CL ASS lE ELECTRICAL EQUIPMENT l
l
180 V HIGH ENERGY LINE BREAKS
-- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
[ NOTE 1 150 N, a N N LIMITING PROFILE FOR MELB NOTE 2 140 - N 3 \ LIMITING PROFILE
< \ FOR HELB b \ 6" R W C U i n. 13o -
N
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3 \ N N Ov 120 -
\
N N N tio - \ N 104 - - - - - -
\
100 -
, i i i i i i go O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 700 SECONDS FIG. D-22 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPER ATURE MEL LS N LOPES C EL LEVELS FOR ZONE 2
\ SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EOUIPMENT
l l IBO HIGH ENERGY LINE BREAKS
-- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
150 NOTE 1
> x b 140 5 \ $ LIMITING PROFILE FOR MELB fr \ NOTE 2 130 - 6" \
3 RWCU \ F g L MITING PROFILE FR LB O 120 - N
-4"RWCU \ \
104 - - - - - . 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 700 SECONDS FIG. D-23 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE
(,D S """ " ' ' " ' ' ' ' "' "" SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS IE ELECTRICAL EQUIPMENT
180 HIGH ENERGY LINE BREAKS
-- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
NOTE 1 150 - E g NOTE 2 140 - \
\
3 N
$ \
g 130 N w N
\
N 120 -
\ % NOTE 3 6" RWCU N tio - \
N 104 - - - - - - N 100 - 90 ' ' ' ' ' ' t O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 70 SECONDS FIG. D-24 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPER ATURE "EL , ALSO ENVELOPES yELB. LEVELS FOR ZONE 4 (Q) 3. LIMITING PROFILE FOR SHOREHAM NUCLEAR POWER STATION-UNIT 1 B
ENVIRONMENTA QUALIFICATION REPORT
'1'g, g ALSO ENVELOPS FOR CLASS IE ELECTRICAL EQUIPMENT l
180 O [ NOTE 1 HIGH ENERGY LINE BREAKS
-- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
150 - W w 140 A NOTE 2
- N $ \
w \ g 130 - N w
" N N \
O 120 - N 6" RWCU tio - N N 104 - - - - - - 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 47 SECONDS FIG. D-25 FROM TIME ZERO.
- 2. LIMITING PROFILE FOR RUMOR BRD% SE%MW "ELB ALSO ENVELOPES CONTAINMENT TEMPERATURE uL. LEVELS FOR ZONE 5 O '
MELB SO N E OPES SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT HELB. FOR CLASS IE ELECTRICAL EQUIPMENT
s 220 HIGH ENERGY LINE BREAKS 210 -
- MODERATE ENERGY LINE BRE AKS (RHR) 200 -
NOTE 1 180 - g 170 -
, NOTE 2 N 160 -
o 6 150 - s w s 14 0 - N g D N N 130 - N N NOTE 3 120 - N
,,g _ 6"RWCU N g N
104 - - - - - - 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS l l NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 32 SECONDS FIG. D-26 FR M ME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE "ELB' ALSO ENVELOPES yEL B. LEVELS FOR ZONE 6
! 3. LIMITING PROFILE FOR ( MELB, ALSO ENVELOPES ENVIRONMENTAL QUALIFICATION REPORT HELB. FOR CLASS 1E ELECTRICAL EQUIPMENT l
180 f} V HIGH ENERGY LINE BREAKS
- MODERATE ENERGY LINE j7O -
NOTE 1 BREAKS (RHR) 160 - 150 - N
- u. N.
N NOTE 2 E 140 - N m N S N
< \ $ \
N g 130 - w
\
120 - N
\ NOTE 3 11 0 -
6" RWCU N
\ g 104 . . . , , _
100 - I l 90 ' I t i i , , O 2 4 6 8 10 12 14 16 TlME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE C
WITHIN 66 SECONDS FIG. D-27 FROM TIME ZERO. REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFtLE FOR CONTAINMENT TEMPER ATURE "ELB ALSO ENVELOPES l uEL . LEVELS FOR ZONE 7
'" " SHOREHAM NUCLEAR POWER STATION-UNIT
- MEL8 ALSO EN ELOPES ENVIRONMENTAL QUALIFICATION REPORT H E L 8'. FOR CLASS 1E ELECTRICAL EQUIPMENT i
f l
220 O\ NOTE 1 HIGH ENERGY LINE BREAKS 210 -- MODERATE ENERGY LINE 3"MSD PEAKS AT 215*F 200 - 3'RCIC PEAKS AT 214.73 F 190 - 180 - g 170 - o I LIMITING PROFILE E 160 - FOR HELB o NOTE 2 4 b n. 150 - 140 - NOTE L 2- ,f- N 130 - N N N NOTE 4 120 - N! 3"MSD 3"RCIC g\g N 110 - N 104 - - - - - 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 26 SECONOS FIG. D-28 FROM TIME ZERO REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPER ATURE "ELB ALSO ENVELOPES yEL . LEVELS FOR ZONE 8 s 3 3,MSD RETURNS TO SHOREHAM NUCLEAR POWER STATION-UNIT 1 104oF AT 2.8 HRS. ENVIRONMENTAL QUALIFICATION Rc_ PORT FOR CLASS 1E ELECTRICAL EQUIPMENT
- 4. LIMITING PROFILE FOR MELB, ALSO ENVELOPS HELB
i 220 O HIGH ENERGY LINE BREAKS 210 -
-- MODERATE ENERGY LINE BREAKS (RHR) 200 -
190 - NOTE 1 180 m 170 - o i N 160 - o
$ LIMITING PROFILE FOR HELB $ 150 -
h w NOTE 2
- 140 3 %
) N ,/ 130 - N N
N 120 - N 3', M S D N g NOTE 3 110 -- N 6.. RWCU % 104 - - - - - - \ 100 - go e i i i i e i O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 25 SECONDS FIG. D- 29 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE HEL NV LOPES EL N. AL LEVELS FOR ZONE 9 SHOREHAM NUCLEAR POWER STATION-UNIT 1 MELB, ALSO E VELOPES ENVIRONMENTAL QUALIFICATION REPORT HELB. FOR CLASS 1E ELECTRICAL EOUIPMENT
. 180 fNOTE 1 HIGH ENERGY LINE 6REAKS - MODERATE ENERGY LINE 170 -
BREAKS (RHR) 160 - 150 - NOTE 2 b 140 N 5 N
- N $ N 130 -
2 \ W \ x 120 -
\
[U) N
\ NOTE 3 HO N
6" RWCU s \
\
104 - -- - - - -
\
100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 33 SECONDS FIG. D-30 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE "ELB ALSO ENVELOPES uEtB LEVELS FOR ZONE 10 SHOREHAM NUCLEAR POWER STATION-UNIT 1 O< 3. LIMITING PROFILE FOR ENVIRONMENTAL QUALIFICATION REPORT MELB' ALSO ENVELOPES FOR CLASS iE ELECTRICAL EQUIPMENT E B.
220
/g b HIGH ENERGY LINE BREAKS 210 - -- MODERATE ENERGY LINE BREAKS (RHR) 200 -
NOTE 1 190 - 180 - g 170 - o 160 - a b 150 - s uJ 14 0 % N N N/ 130 - N N N N 120 - QOTE 3 110 N 6" RWCU 104 .- . . _ _ _ g_ 100 - 1 I f I I i i t 90 0 2 4 6 8 10 12 14 16 TIME - HOURS 1 NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 29 SECONDS FIG. D-31 ,
FR M TIME ZERO. REACTOR BUILDING, SECONDARY l
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE "EL ALS NV LOPES y Ld LEVELS FOR ZONE 11
\ SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT NELO' ALSO E VELOPES FOR CLASSlE ELECTRICAL EQUIPMENT HELB.
~
s, 220 O ; ,A g g l HIGH ENERGY LINE BREAKS 210 " ' N
- MODERATE ENERGY LINE s . _ , BREAKS (RHR) 200
- NOTE 1 100 - -
n.
\.
s, , s s 180 -
\_ - u. 170 ~
a ' l % ( E 160 -
\" . 6072 2 , -
o , - F- +
< s ~ ^
6 150 - a , 2 .- w F 34g x ^
\
N s N O 130 -
,' N N
N ' ~ N N
~'
N 120 - N NOTE 3 N 110 - 6"RWCUs N N \ 104- - - - - - - - 100 - 90 - ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISG WITHIN 15 SECONDS '
FIG. 0-32 FROM TIME ZERO. REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR "EL CONTAINMENT TEMPERATURE q
I yEL$. ALSO ENVELCDES LEVELS FOR ZONE 12 V /
- 3. LIM! TING PROFILE FOR SHCREHAM NUCLEAR POWER STATION-UNIT 1 IAELD, ALSO EN% ELOPES ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS 1E ELECTRICAL EQUIPMENT 1
g
220 CNOTE 1 HIGH ENERGY LINE BREAKS
~ -- MODERATE ENERGY LINE BREAKS (RHR) 200 -
190 - 180 - g 170 - o NOTE 2
$ 160 -
3 4 b 150 - c. b 140 - Os 130 120 - NOTE 3 110 -
~-%
304 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 9 SECONDS FIG. D-33 FR M TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE "EL q uELN. ALSO ENVELOPES LEVELS FOR ZONE 13 Q SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT MELB ELOPES H ELB.' ALSO EN FOR CLASS 1 E ELECTRICAL EQUIPMENT i
220 O r NOTE 1 HIGH ENERGY LINE BREAKS 210 -
-- MODERATE ENERGY '.lNE BREAKS (RHR) 200 -
190 - 180 - g 170 - o a N 160 - 3 4
~
NOTE 2 2 f w 14 0 -
~
130 - 120
%-N- -%----
N -- NOTE 3
~
6"RWCU/ 104 - - - - - - D' 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAR. TEMPERATURE RISE WITHIN 9 SECONOS FIG. D-34 FR M ME ZERO.
l REACTOR BUILDING, SECONDARY l 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE "ELB ALSO ENVELOPES O uEt , LEVELS FOR ZONE 14 V 3 LIMITING PROFILE FOR SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUAllFICATION REPORT MELB, ALSO ENVELOPES FOR CLASS lE ELECTRICAL EQUIPMENT l i l
180 HIGH ENERGY LINE BREAKS
- MODERATE ENERGY LINE 170 -
BREAKS (RHR)
' ~ NOTEI 150 -
h, g 140 E
$ LIMITING PROFILE FOR HELB (NOTE 2 F-p 120 -
V '% l ' ~ , N l
%
- NOTE 3 11 0 -
3~MSD -. 104 - - - - - - 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 , TIME - HOURS t l l NOTES l 1. PEAK TEMPERATURE RISE WITHIN 36 SECONDS Fla D-35 FROM TIME ZERO. REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR "ELO ALSO ENVELOPES CONTAINMENT TEMPERATURE uEL , LEVELS FOR ZONE 15 SHOREHAM NUCLE AR POWER STATION-UNIT 1 O4 3. LIMITING PROFILE FOR LB, RSO ENVELOPES ENVIRONMENTAL QUALIFICATION REPORT
[ELg, FOR CLASS lE ELECTRICAL EQUIPMENT
r NOTE 1 HfGH ENERGY LINE BREAKS
-- MODERATE ENERGY LINE 170 -
BREAKS (RHR) 160 - LIMITING PROFILE FOR HELB 15 0 -
/
W 14 0 - NOTE 2 5 0 5 g 130 w t-120 - V *% % N N
% NOTE 3 11 0 -
4" RWCU 6" RWCU % 10 4 -- - - - - - %- 100 - 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 36 SECONDS FIG. D-36 FR M TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPER ATURE "EL ALSO ENVELOPES LEVELS FOR ZONE 16
\q \J uELB SHOREHAM NUCLE AR POWER STATION-UNIT 1
- 3. LIMITING PROFILE FOR ENVIRONMENTAL QUALIFIC ATION REPORT N$, ALSO ENVELOPES FOR CL ASS lE ELECTRICAL EQUIPMENT
fNOTE1 HIGH ENERGY LINE BREAKS 210 -- MODERATE ENERGY LINE BREAKS (RHR) 200 - 190 - 100 - g 170 - o 1 iso - NOTE 2 a
$ 150 -
s w 14 0 - U 130 - 120 - 110 :-- - _ _ 4" R WCU 104 - - - - - 7 - 100 - 90 O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 35 SECONDS FIG. D-37 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LiuiTING PROFILE FOR CONTAINMENT TEMPERATURE HEL ' ALSO ENVELOPES
's LEVELS FOR ZONE 17
{d yELB. SHOREHAM NUCLEAR POWER STATION-UNIT 1 ENVIRONMENTAL QUALIFICATION REPORT MELB' ALSO EN ELOPES HELB. FOR CLASS 1E ELECTRIC AL EQUIPMENT
18 0 HIGH ENERGY LINE BREAKS
- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
150 - U us 140 -
$ NOTE 1 a
5
- n. . LIMITING PROFILE FOR HELB 130 -
2 y '30TE 2 120 - 3" M S D 11 0 -
- - - - - _ g. j NOTE 3 104 - - . . . -.L. --- -
100 - l l l l 90 ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 ! TIME - HOURS l l l NOTES ,
- 1. PEAK TEMPERATURE RISE WITHIN 103 SECONDS FIG. D-38 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY } 2. LIMITING PROFILE FOR CONTAINMENT TEMPER ATURE "EL LS N LOPES l uELB. LEVELS FOR ZONE 18 ! SHOREHAM NUCLEAR POWER STATION-UNIT 1
- 3. LIMITING PROFILE FOR
- L ALSO ENVELOPES ENVIRONMENTAL QUALIFICATION REPORT gELB. FOR CLASS 1E ELECTRICAL EQUIPMENT l
180 HIGH ENERGY LINE BREAKS
- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
150 [ NOTE 1 b 140 - 5 H h NOTE 2 E 130 - 3 F 120 - NOTE 3 "U ~ _ _ _ _ _ 6" R WCU - 104 - ~ ~ _
~ , _
10 0 -
, i i i ' '
O 2 4 6 8 10 12 14 16 TIME - HOURS NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 54 SECONDS FIG. D-39 FROM TIME ZERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPERATURE "ELB, ALSO ENVELOPES 3 yEt9 LEVELS FOR ZONE 19 SHOREHAM NUCLEAR POWER STATION-UNIT 1
. 3. LIMITING PROFILE FOR ENVIRONMENTAL QUALIFICATION REPORT MELB, ALSO ENVELOPES FOR CLASS 1E ELECTRICAL EQUIPMENT HELB.
180 HIGH ENERGY LINE BRE AKS
-- MODERATE ENERGY LINE 170 - BREAKS (RHR) 160 -
150 - W, w 14 0 - b ti 5 g 130 W F 120 [f NOTE 2 11 0 --------
--- % - NOTE 3 104 - - -
6"RWCU 7 -- 10 0 - 90' ' ' ' ' ' ' ' O 2 4 6 8 10 12 14 16 TIME - HOURS l NOTES
- 1. PEAK TEMPERATURE RISE WITHIN 517 SE'ONDS FIG. D-40 rR u TiuE zERO.
REACTOR BUILDING, SECONDARY
- 2. LIMITING PROFILE FOR CONTAINMENT TEMPER ATURE
^ HELB Al SO ENVELOPES E( , LEVELS FOR ZONE 20 SHOREHAM NUCLEAR POWER STATION-UNIT 1 MELB, ALSO ENVEL S ENVIRONMENTAL QUALIFICATION REPORT HELB. FOR CL ASS IE ELECTRICAL EQUIPMENT
O O O 1.1 HIGH ENERGY LINE BREAKS LIMITING PROFILE FOR HELB - MODERATE ENERGY LINE O.9 BREAKS (RHR)
/NOTEI/ N N
[ \
\
LIMITING PROFILE FOR MELB f LIMITING FOR HELB PROFILE O.7 [ \ NOTE 2 NOTE 1 f / N s
/ x s'
8 "5
/ N ,'s W t 'N
- a. i 6.. R WC U (3" RCIC N o.3 - / N
/ f- 3" M S D -
N
/ N x + o. / N o - . . . . . . . .gg a t t t i I e t t t i 1 i t i f i O 2 4 6 8 10 12 14 16 18 TIME - MINUTES FIG. D-41 REACTOR BUILDING, SECONDARY NOTE i
CONTAINMENT PRESSURE LEVELS
- 1. LIMITING PROFILE FOR HELB- FOR ZONES 1-12 & 15-20 l ALSO ENVELOPES MELB F M LB, SHOREHAM NUCLEAR POWER STATION-UNIT 1 ALSO ENVELO ES HELB ENVIRONMENTAL QUALIFICATION REPORT FOR CLASS lE ELECTRICAL EQUIPMENT l
O O O l.7 HIGH ENERGY LINE BREAKS I - MODERATE ENERGY LINE BREAKS (RHR) 1.3 l 1.1 f LIMITING PROFILE FOR HELB g NOTEI E i O.9 - N% LIMITING PR LE FOR MELB gLIMITING PROFILE FOR HELB O.7 -
/ N [ NOTEI w
a
/ '~N O.5 ' - / %
6"RWCU N O.3 -
/ N N /
N 3" RCIC w~
+ 0.1 / N N
O - - - - - - -
- 0.1 O 2 4 6 8 10 12 14 16 1B TIME-MINUTES l
FIG. D-42 l REACTOR BUILDING, SECONDARY l CONTAINMENT PRESSURE LEVELS NOTE FOR ZONES 13 & 14
- 1. LIMITING PROFILE FOR HELB, SHOREHAM NUCLEAR POWER STATION-UNIT 1 ALSO ENVELOPES MELB. ENVIRONMENTAL QUALIFICATION REPORT
- 2. LIMITING PROFILE FOR MELB, FOR CLASS lE ELECTRICAL EQUlPMENT ALSO ENVELOPES HELB.
I
( O O O i l 14.7o 0.o E J
- l
- 1.0 N -
I
^
14.6 5 w m 3 3 -
-2.o g '8 w
m g i4.6o ( E a
-3.o 4 3 H x ' 5 e m i4.55 1 li'.
u E 5
< s y - - 5.0 z o 2 o 14.5 0 z " E 4 - 6.0 $
O o z o o >- O 14 .4 5 E g (/ -
-7.o g
5 o i4.4o ' ' ' ' ' ' " ' ' ' ' ' ' " ' '"" ' ' ' ' " " ' ' "" ' ' ' ' ' " ' io-' ioo io ' io2 103 io
- io5 Tl ME AFTER ACCIDENT (SECONDS)
FIG. D-43 PRESSURE IN SECONDARY CONTAINMENT FOLLOWING A LOCA SHOREHAM NUCLEAR POWER STATION-UNIT I ENVIRONMENTAL QUALIFICATION REPORT FOR CLASSIE ELECTRICAL EQUIPMENT
..__,__a - _ . - -. . aan--._nw -.-aw a..-n. .u.m -.na-.m m.--- . -.s - - -. -. a ..a s a _ .m- - --s,.-= .
4 i I f I t I ! r l l APPENDIX E ENVIRONMENTAL PROFILE CALCULATIONS I i f t i I l
APPENDIX E 7-~s i ENVIRONMENTAL PROFILt. CALCULATIONS E.1 INTRODUCTION This appendix describes the environmental profile calculations methodology, as indicated in Section 3 of the text. E.2 SHORT TERM RESPONSE TO HIGH ENt.RGY LINE BRt.AKS (Ht.LB) In the HELB analysis, the following specific treaks are considered:
- 1. Six inch RWCU break in RWCU pump room, "B" pump, elevation 112 ft.
- 2. Four inch RWCU break in RN CD heat exchanger room, elevation 126 ft.
- 3. Ten inch HPCI steam line break, elevation 8 it.
- 4. Three inch RCIC steam line and three inch Main Steam Drain (MSD) breaks in steam tunnel, elevation 7b tt.
Blowdown due to breaks is calculated by using tne Moody critical (~N tlow model, from " Maximum Flow Rate of a Single Component, Two-
\_,) Phase Mixture , " by F.J . Moody, Transactions of the ASME, February 1965. This model states that the mass release rate is equal to the mass flux times the cross-sectional area of the break. I m = GA , (eg-1) where m = mass release rate, G = mass flux based on a pressure or 1055 psia, and A = cross-sectional area or the pipe.
A 1s the area of the smallest restriction in the pipe upstream of the break. To include the volume of pipe between the smallest restriction and the break with the volume of piping downstream trom the break in the blowdown determination requires the tollowing equations (f rom GE Mark III Pressure Suppression Containment System Analytical Model, June 1974, Appendix B) : a E-1
tor liquid breaks: O m = 0.5 GA, (eg-2A) tor steam breaks: m = 0.75 GA, (eg-2B) where Ar = cross sectional area of the break pipe These volumes are assumed to blowdown in this manner at a constant pressure until the mass initially contained in the pipe is depleted. The blowdown continues in accordance with eg-1 until blowdown isolation occurs. The following assumptions are made concerning blowdown duration: l 1. For tne 6 inch RWCU, 4 inch RWCU, 10 incn HPCI, and 3 inch MSD breaks, the blowdown is isolated automatically on area high temperature.
- 2. For the 10 inch HPCI and 3 inch MSD breaks, the blowdown is assumed to end abruptly upon isolation valve closure due to the relatively small size or the isolation
() 3. valves. For the 6 inch RWCU and 4 inch RWCU breaks, the isolation valve is a large gate valve which causes the blowdown rate to ramp down as the valve closes.
- 4. Blowdown duration is determined as follows:
- a. The pipe break node reaches setpoint temperature of the automatic closure system rollowed by a 10 second " soak" time for the detector to respond, tollowed by the isolation valve closure time.
- b. Simultaneously with the pipe break, a loss or offsite power is assumed which requires an additional 19 second delay until power is restored via the diesel generator.
- c. For some breaks the area high temperature setpoint is achieved almost instantaneously. In these cases, the time to reach the setpoint temperature and the detector " soak" time are assumed to occur during the 10 second duration ot power loss.
Thererore, isolation volve closure starts 10 seconds atter the creak occurs. E -2
- d. The 3 inch RCIC break does not have automatic isolation. Thus, blowdown duration includes all
( other time delays in addition to a ten minute operator response time to manually initiate clowdown isolation due to area high temperature alarm. For pipe breaks which cause a plant trip and an assumed loss of power or for cases where normal ventilation is unavailanle, the reactor building RBSVS would be initiated automatically and operate throughout the duration of the analysis. However, credit is taken for only one train or RBSVS (the other train is assumed to be a single tailure). Heat sinks are modeled in the short-term analyses but only concrete heat sinks were considered and no. energy transfer out of ' the secondary containment is assumed through the heat sinks. Metal heat sinks are neglected for conservatism. A 20 zone model of the Reactor Building secondary containment is used (see environmental zone maps in Appendix D) . This 20 zone model with blowdown data, ventilation data, and heat sink data are input into a camputer code (called THREED) which calculates peak temperatures and pressures. This computer code was developed by SSW and used in previous Section 6.2 FSAR analyses. E.3 SHORT TERM RESPONSE TO MODERATE ENERGY LINE CRACKS (MELB) The blowdown rate is based on Bernoulli's theorem. The crack postulated consists of a sub-cooled liquid and is modeled as an orifice with an area of: A = D/2 x th/2 where A = area of crack, D = Diameter of cracked pipe, and th = wall thickness of the cracked pipe. The blowdown is assumed to be frictionless ano an orifice discharge coefricient of 1.0 is used. The following equation represents the mass blowdown rate in lbm/sec: m = 0.52Sd2 C /AP 6 (eg-3) where m = mass release rate, d = ef fective diameter or the crack, C = orifice discharge coefficient, O E-3 i
, . . ~ . - . _ . _ _. _ .-.
AP = difference in pressure between (~ RHR system pressure and atmospheric pressure, and 6 = density of the system water. d is determined from the following: d=2 /A/ w The energy release rate Q is determined by multiplying the mass release rate m by the enthalphy h of the fluid. Q=mh The RHR crack is assumed to be isolated in 11 minutes after the crack occurs. The 11 minutes includes time for water to accumulate at the 8 f t elevation for a high water alarm f ollowed by the time required for an operator to initiate isolation and time for the isolation valves to close. The model of the Reactor Building secondary containment used for an RHR crack is a 24 zone model, similar to the 20 zone model mentioned earlier except that El. 8 It is subdivided into two zones and El. 40 it is subdivided into tour zones. m Heat sinks are modeled in 20 of the 24 zones. Heat sinxs for the smallest zones are neglected. No part or the ventilation system is considered in the RHR crack short-term analysis. l The 24 zone model data, blowdown data, and heat sink data are input into a computer code (called THREED VER12 LEVO) whicn I calculates peak temperatures and pressures. E.4 RADIATION CALCULATIONS A. Source Term Radioactive Scurce Release and Distribution assumptions are as rollows: l 1. Radioactive Source Release i The percents of core inventory radioactive tission products assumed to be released from the tuel rods tor LOCA events are: noble gases (Kr, Xc) 100$ iodine 50% g others 1A
)
E-4
A This entire release is assumed to occur instantaneously at the start of the accident. 7-
- 2. Radioactive Source Distribution In order to envelope the full spectrum of break sizes and depressurization rates, two bounding events and source distributions are considered.
The rirst event considered is a LOCA (both pressurized and depressurized events) . In this event, the following fission products are considered to be uniformly mixed in the rollowing volumes:
- a. Suppression Pool noble gases 0%
iodine 50% others 1%
- b. Combined Drywell/Wetwell Air Space noble gases 100%
) lodine 25%
others 0%
- c. Reactor Coolant System Steam Space The following distribution is used for determining reactor building pipe shine doses due to HPCI, RCIC and MSIV-LCS operation noble gases 100%
iodine 25% others 0% Using tne above distribu tion, time history radiation zones are established within the primary containment and within tne secondary containment as follows:
- 1. Primary Containment -
Previously described accident radiation levels (FSAR Table 3.11.2-1) adequately bound all LOCA O V E-5
events for equipment within the primary (w containment and no new analyses are required.
- 2. Secondary Containment - Time history radiation zones are established tor the secondary containment using the above sources distributed in the steam and liquid piping in the following fluid systems wnich are conservatively assumed to operate concurrently:
- a. High Pressure Coolant Injection (HPCI)
- b. Reactor Core Isolation Cooling (RCIC)
- c. Residual Heat Removal (RHR all essential modes)
- d. Core Spray
- e. Reactor Building Standby Ventilation System (RBSVS)
- t. Main Steam Isolation Valve -
Leakage Control (MSIV-LCS) 9 Primary Containment Atmospheric Control [) (PCAC) \_/ In addition to the radiation shine trom the above system piping and components, the primary containment is assumed to leak at technical specification limits resulting in an airborne source term which is included in the radiation zoning. As provided by NUhEG 0737, no additional leakage is assumed.
- 3. Excluded Systems
- a. All piping which could potentially carry undiluted reactor coolant into the secondary containment is isolated and is nonessential (e .g . , RWCU, shutdown cooling mode of RHR) . Accordingly, the i undiluted reactor coolant liquid source discussed above is exclud ed . Adequate 3means are provided (Post Accident
- Sampling System) to insure sate radiation levels exist prior to use or any of tnese nonessential systems.
D. The post accident sampling lines are excluded from specific evaluation due to O L-6
their size (typically 3/8 in. tubing) and because they are flushed after each use. O. Sufficient conservatism in integrated dose calculations exists to bound any effects of these small sources.
- c. The gaseous radwaste system lines are also excluded because they do not act as sources for any safety-related equipment.
They are also located outside the reactor building and are isolated.
- 4. Outside Reactor Building - the calculated dose rates and integrated dose values for components located in buildings other than the Reactor Building are derived from the following sources:
- a. Direct shine from radioactivity within the Reactor Building which is both airborne and contained in specific components.
- b. Airborne activity in the respective building due to ventilation intake.
- c. Semi-infinite radioactive cloud which surrounds the respective building.
{}
- d. Skyshine from radiation originating in the Reactor Building and air-scattered to a receptor.
The pipe break inside primary containment and nonpipe break events are bounded by the LOCA event above. The other event considered is a pipe creak in secondary containment. This event provides the bounding values in some zones within the secondary containment in the snort term (i.e. , less than 30 days) . However, the LOCA doses provide the boundary values for dosee tor tames longer than 30 days. O E-7 l
,a- u. A g .- _ ____, m_
O APPENDIX F ENVIRONMENTAL QUALIFICATION STATUS REPORT I lO l O
APPENDIX F ENVIRONMENTAL QUALIFICATION STATUS REPORT The following is a sample of an entry into the Environmental Qualification Status Report (EQSR) : Di PNI tt') . PF1-650 5ffyat Are HtPSf te ItICittf eltG t &t N A T IUlf P'*0Jf Cf t'N'Irtif NT S TSit et - (IS-1tti FtrL9T DAT[ 01/11/62 PACf TS 100 ##erfP lle n0*s? (IntrattritiT AL fJU.ilIFIC Af fUPI SI Altri Stropf PE<f f fR Oct
.w ILvit 91rwil4!t - teilt n Rt5tf PAlf 07/01/01 .ite CL Itttf LILCO 50H1f D 97 - HrJ4 / IMO / SrtC E91!tt'Fl!T OF5tplPitfft IIAl:f / HYll?F Ae.IUPLIP IQ SPEEI DP IIf t[ ACC / Pf9F tes_f 8f F911P18Ff:t 19 tref t / cat ALO"o PO WAL SIAT tW. Cf D Vf f Mut 10 Vil410't terJ2 QAC 101E op to f.PEC 0t t1G (LEV $'JI': tre P0 frf TLp esseeeeeee eroe sesseesposenesse ese seseesseeeeeeeeeeeeeeessee emessessesse seeeeeeeeeeeeeeeeee, eeeeeeeems eseessee f!' %CTfNF ret ESupt Bl#TfPt J129 160 DY$ 7.5 !!t. et G ,1FfleP101s* off ALL t tttt99. ELEC lt G 10 740 e:1 tme!D A !!cete 003 WE S 00974 fig t Definitions or the entry headings are given below. An alphabetized list of equipment type aooreviations is provided in Appendix H.
Data definitions for entry headings are as follows: , EQUIPMENT ID VENDOR ID The first line identifies the Stone & Webster unique identification or mark numner for each equipment. The first four characters represent the system number followed by an asterisk,
"*" , to indicate the equipment is safety-related or a dash " " ,
to indicate the equipment was not originally safety-related but is now identified by NRC hegulatory Guide 1.97 or other requirements. The key to the system code is described in Section 2. The succeeding characters indicate the equipment type using the equipment identification symbol as documented in the Shoreham Project Procedures. The key to the equipment type symbol is provided in Appendix H. Additional characters provide a unique alpha-numeric identification for identical or redundant equipment. The second line indicates the General Electric identification code (the Master Parts List number) if the item is in the NSSS design. !O F-1 l . .
f EQUIPMENT DESCRIPTION VENDOR NAME PO NUMBER The top line provides an abbreviated tunctional or application description of the equipment identified. IT DOES NOT GENERALLY INDICATE THE EQUIPMENT TYPE. The middle line is the equipment supplier. The lower line is the purchase order number for the equipment . QAC SPEC The upper line is the Quality Assurance Category of the eq uipment, which is Class #1E" or "2E*. The second line is the specification number under which the equipment is procured; the specitications are ideatified by the specification numbers listed in Section 2. ZONE BLDG ELEV The first line provides an alpha-numeric code for the environmental zone in which the equipment is located in a format of " letter - two digit number." The radiation zone is designated by the first (letter) character. The two digits atter "" designate the temperature / pressure zone. Radiation zones and
'i temperature / pressure zones do not necessarily coincide. The second line provides building and elevation (f eet above sea level) to describe equipment location. T.he key to the building anbreviations is as f ollows:
Building Code Building Name RBD Reactor Building Drywell RBS Reactor Building Secondary RBP Reactor Building Primary YD Yard ST Steam Tunnel MAKE/ MANUFACTURER MODEL/ CATALOG NO. < The rirst line identifies the equipment manuf acturer. The second line provides the manuf acturer's model or catalog number, or any other identifying number for the equipment. EQ SHEET QUAL STAT SUBMG The first line identities the Environmental Qualification Summary Sheet (EQSS) . Each EQSS tor BOP equipment is identitled by the O specitication number, summary sheet number, and revision level if F-2
I not the original issue. For NSSS e quipment , each EQSS is identified with a four digit number. The first digit is "3" (~) representing Specification Sill-003 . w lth the equipment group (/ designated by the succeedir.g digits. The second line lists the qualification status of equipment in an abbreviated torm as follows: s EQ - Equipment is qualified QG - Equipment is qualified except for aging PT - Documentation has been reviewed, further test / analysis recommended , MR - Modification of equipment is recommended for qualification RR - Replacement is recommended, test report ior qualified replacement will De evaluated DR - Documentation is in review TA - Testing / analysis program has been initiated O IJ - Qualification documentation not expected to be completed prior to ruel load, refer to Appendix G of this report for status The third line indicates whether the equipment is exposec to containment spray or mist conditions. The rollowing abbreviations are used: SPR - Containment spray MST - Mist conaltions OP TIME This field describes the time required, including the margins applied, for the equipment to operate during and subsequent to a design basis event. The first portion or the tield is a number tollowed by one or the tollowing abbreviations to record the units of time: CON - Continuous YRS - Years MON - Months -
/ DYS -
Days
\ RRS -
llours F-3
-..m.._. __
MIN - Minutes O ACC/PERF This field indicates the accuracy specification or instruments for trip functions and post-accident monitoring. Wnere not applicable to the specitic equipment, "N/A" is entered. NU CAT EMG CND OP CD The first line will indicate "RG" if the equipment must be qualitied to the requirement of Nuclear Regulatory Guide 1.97. The second line indicates for which design basis event (s) the equipment must be qualified, with abbreviations as follows: L - Loss of Coolant Accident (IDCA) H - High Energy Line Break (HELB) M - Moderate Energy Line Crack (MELB) ALL - LOCA, HELB, MELB The third line indicates operability code with letters A or B referring to the equipment categories defined in NUREG-0588, Appendix E. Equipment designated as operability code A with 3 operability time less than 180 days revert to operability code b for the remainder of the 180 days unless otherwise noted. l O F-4
-)
1T46 EFT 004A REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIR0tetENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STONE APO HEBSTER EtGINEERItG CCRPORATION JOB FRAtBER 1160002 PROJECT EQUIPHENT SYSTEM - (IS-129 ) REPORT DATE 01/18/82 PAGE 2 JCB NAttE SHOREHAM - tjNIT 1 EtNIRotetENTAL QUALIFICATION STATUS REPORT RESET NO. 0G3 JOB CLIENT LILCO SCRTED BY - HAM / H00 / SPEC RESET DATE 07/01/81 EQUIPHENT ID EQUIPilENT DESCRIPTION HARE / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VEtOOR ID .VEtOC,1 NAHE QAC ZONE HODEL / CATALOG NO QUAL STAT EHG Cte PO NUfBER SPEC BLDG ELEV SUBHG OP CD evowmanamenemmen emmemme**menemmeneenemoneesene nousemannen mannuemmeemmees**mee monomamma ***menau sommensue emme REPORT GRotP ttAM = AI2 HONITOR CORP.
.1T40 EFT 004A RBSVS EXH AIR FLOH mAIR HONITOR CORP. m319-31 180 DTS mRG PCHEPS REGUL 1E H-18 eVELTRON 800 mIJ ALL 310738 319 RBS 00150 A .1T46mFT004B RCSVS EXH AIR FLON mAIR H0HITOR CORP. e319-01 180 DTS mRG POWERS REGUL IE H-18 eVELTROM 800 mIJ ALL 310738 319 RBS 00150 A
IE32cFT037A REPORT No. PES-800 JOB 1160002 01/18/82 EtNIRotetENTAL QUALIFICATION STATUS REPORT REPORT t10. PES-800 ST0r4E Ato HEBSTER ENGINEERING CORPORATION JOB tiUf fBER 1160002 PROJECT EQUIPHEtiT SYSTEH - (IS-129 ) REPORT DATE 01/18/82 PAGE 3 JOB f4AME SHOREHAH - UNIT 1 EtNIROtDIENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JOB CLIENT LILCO SORTED BY - HAM / HCD / SPEC RESET DATE 07/01/01 EQUIPtfENT ID EQUIFHENT DESCRIPTION HAME / hat 0FACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDOR ID VEtCOR HAffE QAC Z0 tie HODEL / CATALOG tia QUAL STAT EHG CtB FO FU'BER SPEC BLDG ELEV SUBttG OP CD commmmmmmmmmmmme mammmmmmmmmmmmmmmmmmmmmmmmame* ************ maammmmmmmmmmmmmemum maammannan mammmmme mununummum name REPORT GROUP ttAM = A!!ETEM
.1E32mFT037A HSIV A LEAM TO LPH AttETEM m3128 100 DYS E32-N053B GENERAL ELEC IE G-05 078-5004 mDR mL 310010 003 RBS 00063 A OP CODE B FOR HELB & HELB .1E32mFT0378 HSIV B LEAM TO LPH AffETEH m3128 100 DYS E32-N053F GENERAL ELEC 1E G-05 078-5004 eDR mL 310010 003 RBS 00063 A OP CODE B FOR HELB & HELB .1E32mFT037C HSIV C LEAK TO LPH AHETEM m3128 100 DYS E32-N053K GENERAL ELEC IE G-05 078-5004 *DR mL 310010 003 RBS 00063 A OP CODE B FOR HELB & HELB .1E32mFT037D HSIV D LEAM TO LPH AHETEN m3128 100 DYS E32-N053P GEtlEPAL ELEC IE G-05 078-5004 mDR mL 310010 003 RBS 00063 A OP CODE B FOR HELB & HELB O O O
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J v v 1821 50V81AX REPORT t:0. PES-800 JOB 1160002 01/18/82 ENVIRotetENTAL QUALIFICATI0H STATUS REPORT REPORT to. PES-800 STONE At0 HEBSTER ENGINEERING CORPORATION JOB NUtfCER 1160002 PROJECT EQUIPHENT SYSTEH - (15-129 ) REPORT DATE 01/18/82 PAGE 4 JOB NAttE S:f0PEHAH - UNIT 1 ENVIR0t#fENTAL QUALIFICATION STATUS REPORT RESET No. 003 JOO CLIENT LILCO SORTED BY - HAK / HOD / SPEC RESET DATE 07/01/81 EQUIPifENT ID EQUIrl'ENT DESCRIPTIDH HAME / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT vet 00R ID VEtocR NAME QAC ZONE HODEL / CATALOG NO QUAL STAT ENG CND PO NU:fbER SPEC BLDG ELEV SUBHG OP CD e............... enneewonnenenemonenemone ***e **m....e**** emmeneeneue==ememene menee neen emmenene emeseemene emme REPORT GROUP HAM = ASCO
.1821 SOV81AX 1821*AOV081A CONTROL ASCO 3096 070 HIN WA eB21-F022A GENEPAL ELECT IE eD-22 HT-X-8320A20 eIJ ALL 310010 003 eRBP 00082 mHST A .1821eSOV81AY 1821*A0V081A CONTROL ASCO 3096 070 HIH WA (B21-F022A GENERAL ELECT 1E *D-22 HT-X-8320A20 mIJ ALL 310010 003 eRBP 00082 *HST A .1821.SOV81AZ 1B21.AOV081A CONTROL ASCO 3096 070 HIN WA KB21-F022A GENERAL ELECT IE eD-22 HT-X-8320A20 mIJ ALL 310010 003 *RSP 00082 eHST A .1821eSOV81BX IB21st0V081B CONTROL ASCO 3096 070 HIN WA (B21-F022B GENERAL ELECT 1E eD-22 HT-X-8320A20 mIJ ALL 310010 003 mRBP 00002 *HST A .1B21eSOV81BY 1B21eA0V081B CONTROL ASCO 3096 070 HIN WA sB21-F022B GENERAL ELECT 1E eD-22 HT-X-8320A20 mIJ ALL 310010 0C3 mRBP 00082 *HST A .1821eSOV818Z 1821 A0V0818 CONTROL ASCO 3096 070 HIN WA KB21-F022B GENEPAL ELECT IE eD-22 HT-X-8320A20 eIJ ALL i 310010 003 mRBP 00082 eHST A i .1821*SOV81CX 1821=AOV081C CONTROL ASCO 3096 070 HIN WA *B21-F022C SENE9AL ELECT 1E *D-22 HT-X-8320A20 *IJ ALL 310010 003 mRBP 00082 *HST A .1821mSOV21CY 18215A0V081C CONTROL ASCO 3096 070 HIN WA (B21-F022C GENEFAL ELECT 1E =D-22 HT-X-8320A20 eIJ ALL 310010 003 *RBP 00062 .HST A ~ .1B21.SOV81CZ 1821eA0V081C CONTROL ASCO 3096 070 HIN WA <B21-F022C GENEKAL ELECT 1E eD-22 HT-X-8320A20 mIJ ALL 310C10 003 mREP 00082 eHST A .1B21eSOVSIDX 1821eA0V0010 CONTRCL ASCO 3096 070 HIN N/A EB21-F022D GENERAL ELECT 1E *D-22 HT-X-8320A20 mIJ ALL 310010 003 dBP 00082 eHST A 7 .1B21eSOV810Y 1(.21*A0VC810 CONTROL ASCO 3096 070 HIN WA ED21-F0220 CENE"AL ELECT 1E =D-22 HT-X-8320A20 eIJ ALL 310010 003 mRSP 00082 *HST A
IB?l:50V810Z REPORT to. PES-800 JCB 1160002 01/18/82 EirJIRotetENTAL QUALIFICATION STATUS REPORT REPORT NO. DES-800 STCt4E Ato HEBSTER Et1 GINERING CORPORATION JOB FO!SER 1160002 PROJECT EQUIPMENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 5 JCB tiAME SHOREHAH - UNIT 1 Erf/IRCtetENTAL QUALIFICATI0ti STATUS PEPCRT RESET No. 003 JCB CLIEt4T LILCO SORTED BY - HAH / H00 / SPEC RESET DATE 07/01/81 EQUIPMENT ID EQUIrt.EtiT DESCRIPTION ttAKE / flatlUFtCTURER EQ SHEET OP TIffE ACC / PERF r4U-CAT VEtCOR ID VEtCC7 NAME QAC ZCriE HODEL / CATALOG NO QUAL STAT ENG Ctc PO tiMaER SPEC BLOG ELEV SUSitG OP CD e..... ......... eeneseeeeeeeeeeeeeeeeeeeeeee*e .. ......... aussemenemmenennemen es**emenee menneeen esseneense seem
.1821 SOV810Z IB21.LOVOSID CONTROL . ASCO 3096 070 HIN WA eB21-F0220 GENEPAL ELECT IF eD-22 HT-X-8320A20 *IJ ALL 310010 003 eREP 00082 ettST A .1821 SOV82AX IB21e;.OV082A CONTROL ASCO 3096 070 HIN WA eB21-F028A GLNE"AL ELECT IE eT-08 HT-X-8320A20 mIJ ALL 310010 003 eST 00082 A. .1B21 SOV62AY 1821.f.rJ082A COtiTROL ASCO 3096 070 HIN WA (221-F028A GENERAL ELECT 1E .T-08 HT-X-8320A20 eIJ AL L 310010 003 eST 00082 A .1B21 SOV82AZ 1821eA0V082A CONTROL ASCO 3096 070 HIN N/A cB21-F028A GENER E ELECT 1E eT-08 HT-X-8320A20 mIJ ALL 310010 003 eST 00062 A .1B21eSOV82BX 1B21.A0V0820 CONTROL ASCO 3096 070 HIN WA (B21-F028B GENEPAL ELECT 1E *T-08 HT-X-8320A20 mIJ ALL 310010 003 eST 00082 A .1821 SOV82BY IB21 ACV082B CCHfROL ASCO 3096 070 HIN N/A (B21-F028B GENERAL ELECT 1E *T-08 HT-X-8320A20 mIJ ALL 310010 003 eST 00082 A .1B21 SCV3*BZ 1821eLCV002B CONTROL ASCO 3096 070 HIN WA (B21-F0288 GENE;'+,L ELECT 1E *T-08 HT-X-8320A20 mIJ ALL 310010 003 eST 00082 A .1821 FCV82CX 1821e O O82C CONTROL ASCO 3096 070 HIN N/A tB21-F028C GEt1EFAL ELECT 1E eT-08 HT-X-8320A20 *IJ ALL 310010 Oc3 eST 00082 A .1821eSOV82CY IB21 AOVOS2C CONTROL ASCO 3993, 070 HIN N/A j (B21-F028C GENEPAL ELECT IE eT-08 HT-X-8320A20 m2J ALL ,
310010 003 eST %0P2 A 'r
~ .1821 SOV82CZ 1D214AOV002C CONTROL ASCO 3076 070 MIN WA cB21-F028C GE"!FAL ELECT IE eT-08 HT-X-8320A20 eIJ ALL 310010 003 eST 00082 A .1821eSOV82DX 1821*AOV0620 CONTROL ASCO 3096 070 HIN tVA rB21-F0290 CENERAL ELECT 1E eT-08 HT-X-8320A20 *IJ t' ALL 310013 GJ3 eST 00082 A 7 .1821 SOVS20Y IB21rAOVOS2D cot 4TRCL ASCO 3096 070 HIN WA (821-F0260 GEt,E!:AL ELECT 1E eT-08 H T-X-8322 Ad mIJ ALL 310010 003 *ST 00082 A O O O
f
% Y '
N./ 1821mSOV820Z REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIRONitENTAL QUALIFICATION STATUS REPORT REPORT NO. PE!-800 STONE AfD HEBSTER ENGINEERING CORPORATION JO3 tO?BER 1160002 PROJECT EQUIPHENT SYSTEH - (IS-129) REPORT DATE 01/18/82 .PAGE 6 JOB NAt1E SHORZHAN - UNIT 1 ENVIR0tDfENTAL QUALIFICATION STATUS REPORT RESET No. 003 JOB CLIENT LILCO SORTED BY - HAK / HOD / SPEC RESET DATE 07/01/81 4 EQUIPifENT ID EQUI?t'ENT DESCRIPTION HAME / HANUFACTURER EQ SHEET OP TIHE ACC / PERF NU-CAT VEtCOR ID VEN009 NA!!E QAC ZONE HODEL / CATALOG ~ NO QUAL STAT EttG CND PO iU!!BER SPEC BLOG ELEV SUBitG OP CD mmmmmmmmmmmmmmm* mum *** men *****mmmmmmmmmen***** ****menum*** maammmanummmens**ms* mummmmmen* ***mmmm* mammmmmmum ****
.1B21pSOV82DZ IB21mAOV082D CCNTROL ASCO 3096 070 HIN WA 2 <B21-F0280 CEllERAL ELECT 3E *T-08 HT-X-8320A20 mIJ ALL
! 310010 003 mST 00082 A
.1T46mSOV035A OPERATES IT46mAOVO35A ASCO 070 MIN WA FISHER CONT. IE G-01 HV200-926-1F-EP *RR ALL 310555 111 RBS 00112 A .1T46mSOV0350 OPERATES AT46mA0V035B ASCO 070 MIN WA FISHER CONT. IE G-01 HV200-926-1F-EP *RR ALL 310655 111 RBS 00112 A .1T46mSOV037A OPERATES 1T46aA0V037A ASCO _
070 HIN WA , FISHER CONT. IE G-01 HV200-926-1F-EP *RR ALL 310655 111 RBS 00095 A
.1T46mSOV037B OPERATES IT46mA0V037B ASch 070 HIN WA FISHER CONT. IE G-01 HV200-926-1F-EP *RR ALL 310655 111 RSS 00095 A .1T46mSOV038A PRI CONTAItaiENT PURGE VALVE ASCO 070 MIN WA FISHER CONT. IE D-22 HV200-926-IF-EP mRR ALL m373023 *172 RBP 00078 mHST A .1T46mSOV038B PRI CONTAItRtENT PURCE VALVE ASCO 070 HIN WA . FISHER CONT. 1E H-10 HV200-926-1F fp mRR ALL I *373023 *172 RBS 00078 A i .1T46mSOV03t!C PRI CONTAltetENT PURGE VALVE ASCO 070 HIN WA 4 FISHER CONT. IE L-02 HV200-926-1F-EP mRR ALL 310574 172 RBS 00040 A .1T46mSOV0383 PRI CONTAITHtENT PURGE VALVE ASCO 070 HIN WA FISHER CONT. 1E L-02 HV200-926-1F-EP mRR ALL 310574 172 RBS 00040 A i ~ .1T46mSOV039A PRI CONTAItttENT PURGE VALVE ASCO 070 HIN WA FISHER CONT. 1E B-22 HV200-926-1F-EP mRR ALL 310574 *172 REP 00112 *SPR A .1T46mSOV0393 PRI CCNTAltDtENT PURGE VALVE ASCO '070 HIN WA FISitER CONT. IE H-15 HV200-926-1F-EP *RR ALL 310574 172 RBS 00112 A 7
T. 1T46mSOV039C PRI CONTAIt# TENT PURGE VALVE ASCO 070 HIN WA FISHER CONT. IE 'G-02 HV200-926-IF-EP *RR ALL { m373023 m172 RBS 00040 A i
IT46: SOV03?D REPCRT fl0. PES-800 JOB 1160002 01/18/82 EtiVIR0taiENTAL QUALIFICATION STATUS EEPORT REPORT tto . PES-800 ST0flE AND HEBSTER ENGINEERING CORPORATION JOB NUMBER 1160002 PROJECT EQUIFMENT SYSTEH - (15-129 ) REPORT DATE 01/18/82 PAGE 7 J03 F8*FE
. SHOREHAH - UNIT 1 EtiVIR0tittENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JOB CLIENT LILCO SCRTED BY - HAM / HOD / SPEC RESET DATE 07/01/81 21UIPilEtlT ID EQUIPl!ENT DESCRIPTION ttANE / HArlUFACTURER EQ SHEET OP TIHE ACC / PERF NU-CAT VENDCR ID VENDC7 NA!!E QAC ZONE HODEL / CATALOG NO QUAL STAT ENG CND PO FL".BER SPEC BLDG MV SUBt!G OP CD m..uneenenes**me *********me*umann****** men ***n ***** man.,** womven***ummu*mammum ****menes* wonnumae **mmum**** **** .lT46*SOV039D PRI CONTAItclENT PURGE VALVE ASCO 070 HIN N/A FISHF7 CONT. 1E G-02 HV200-926-lF-EP mRR ALL *3736?3 *172 RBS 00040 A .lC11*SOV042A BACK UP SCRAH SYSTEH mASCO *3909 070 HIN *N/A mRG lE G-05 *NP8316C37 *QG ALL 310010 003 RBS CM63 A .lC11mSOV042B BACH UP SCRAtt SYSTEH mASCO *390% 070 HIN mH/A mRG lE G-05 *NP8316C37 wQG ALL 310010 003 RBS 00063 A .lP42aPS021A PUllP 1 N *P005A DISCH ASCO 070 HIN 1% SP AUTO SHITCH IE H-18 SB11AMR/TF10A32B TA ALL 10072 348 RBS 150 A .lP42*PS021R PUHP 1P42*P005B DISCH ASCO 070 HIN 1% SP AUTO SHITCH IE H-18 SB11AKR/TF10A328 TA ALL 10072 348 RBS 150 A .lP42mP5021C PUllP 1942*P005C DISCH ASCO 070 HIH 1% SP AUTO SHITCH lE H-18 SBilAMR/TF10A328 TA ALL 10072 348 RBS 150 A .lP42mPS022A PuttP IP42*P005A DISCH ASCO 070 HIN 1% SP AUTO SHITCH lE H-16 SB11AHR/TF10A32B TA ALL 10072 348 RBS 150 A .1P42*PS022B PUt1P 1P42*P005B DISCH ASCO 070 HIN 1% SP AUTO SHITCH IE H-18 SB11AKR/TF10A32B TA ALL 10072 3p RBS 150 A .1P42*PS022C PUttP 1P42*P005C DT.SCH ASCO 070 HIN 1% SP AUTO SHITCH IE H-18 SB11AHR/TF10A32B TA ALL 10072 348 RBS 150 A
~
.1P42*PS046A PUHP IP42eP005A DISCH ASt.0 100 DYS 1% SP AUTO SHITCH IE H-18 SBilAHR/TF10A32B TA ALL 10072 348 RBS 150 A .lP42*PSO46B PUI'P 1P'42mP005B DISCH ASCO 180 DYS 1% SP AUTO SHITCH lE H-18 SB11AKR/TF10A32B TA ALL 10072 348 RDS 150 A 7 .lP42*PSO46C PUttP 1P42*P005C DISCH ASCO 180 DYS 1% SP AUTO SHITCH IE H-18 SB11AKR/TF10A32B TA ALL 10072 348 RBS 150 A O O O
( V N \ IP50*PS105A REPORT tl0. PES-800 JOB 1160002 01/18/82 EtWIRONHEllTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STONE AND HEBSTER ENGINEERIliG CORPORATION JOB nut!SER 1160001 PROJECT EQUIPHEllT SYSTEH - (IS-129) REPORT DATE 01/M/82 PAGE 8 JOB HAlfE SHOREHAH - UNIT 1 EtWIRotatENTAL QUALIFICATI0tl STATUS REPORT RESET NO. 003 JOB CLIEtiT LILCO SORTED BY - HAM / H00 / SPEC RESET DATE 07/01/81 EQUIPttENT ID EQUIPHEtiT DESCRIPTION MAHE / HANUFACTURER EQ SHEET OP TIHE ACC / PERF NU CAT VENDOR ID VEtCOR HAME QAC ZONE HODEL / CATALOG HQ QUAL STAT EHG CHO I PO NUi'BER SPEC BLDG ELEV SUCHG OP CD nunumm***munumme m.mun*munnmmmmmmmm****mm****** *mm*me****** ununummmeenomannenum num** mum ** *mummmma mum *mamman amme $ .1P50*PS105A SERV AIR HDR A PRESS ASCO 070 HIH 1% SP 04450008 AUTO SHITCH IE H-18 SS11AHR/TG10A32B TA H.H 10072 348 RES 151 A OP CODE B FO'4 LOCA
.1P50mPS105B SERV AIR HDR B PRESS ASCO 070 HIN 1% SP 04470008 AUTO SWITCH IE H-18 SB11AHR/TG10A328 TA HH 10072 348 RBS 151 A OP CODE B FOR LOCA .1PS0mPS113A SERV AIR FOR A tVRif StM ASCO 070 HIH 1% SP 04490008 AUTC SHITCP IE H-18 SB11AHR/TG10A32B TA H,H 10072 348 RBS 151 A OP CODE ta EGl3 LOCA .1P50mPS113B SERV AIR HDR B NCMH SUP ASCO 070 HIH 1% SP 04510008 AUTO SHITCH IE H-18 SB11AHR/TG10A328 TA H,H 10072 348 RBS 151 A OP CODE B FOR LOCA .1B21mSOV036A CPERATES 1821mA0V036A ASCO m232-01 070 HIH VELA'i 1E H-18 mHJHHX-8320-AB7E *EQ L 310595 232 RSS 00087 A CP CODE 3 FOR PELB & HELB 4 .1B21mSOV0368 REACTOR FH IHLET A0V036A ASCO *232-01 070 HIH VELAt- IE H-lo *HJHKX-8320-A89E *EQ L 3105M 232 R*5 00087 A OP CODi B FOR HELB & HELB #1E11mSOV081A m0H IE11mA0V081A *ASCO *232 01 m180 *DYS ele .D-22 *HJHNX-8320-A89E mEQ
- ALL ADDED *310595 m 232' mRBP =00079 ettST mB i .1E11mSOV081B nFO'? IEll*A0V081B mASCO *232-01 *180 mDYS
~
VELAti *1E *D-22 mHJHHL 8320-AS9E *EQ ALL m31059S m232 mRBP *00079 *HST eB
.lE21mSOV081A nFOR 1E21mA0V081A mASCO m232-01 *180 *DYS VELAtt ale *B- 22 *H11HX-8320-A89E *EQ L m310595 *232 mRBP *00126 *HST eB .1E21mSCV081B nFOR 1E21mA0V081B m4SCO m232-01 *180 mDYS l VELAti ale eB-22 *HJHOC-8320-A89E *EQ L "[ m310593 m232 *RBP *00126 *HST eB .1P42mSOV282 RBCLCH RETURH CHECH VLV ASCO *232-01 070 HIN l
IP42aSOV282 AEPCRT f:0. PES-300 JCB 1160002 01/18/32 ENVER0lOfEi4TAL QUALIF2 CATION STATUS REPORT REPCRT tG. PES-800 STONE Af fD HEBSTER ENGIt4EERIt4G CORPCRATION JCB t; UMBER 1160002 PROJECT EQUIPl!EtiT SYSTEH - (IS-129 ) REPORT DATE 01/18/82 PAGE 9 JOB tiAftE SHOREHAH - UNIT 1 Et3VIRotPtEt4TAL QUAL 1FICATION STATUS REPORT RESET NO. 003 JOB CLIErtT LILCO SCRTED BY - HAM / HOD / SPEC RESET CATE 07/01/81 EQUIP 11E;1T ID EC'J IPHtt!T DESCRIPTIOri itAHE / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VEriDOR 10 VENDC1 i4AME QAC ZOttE It00EL / CATALOG tiO QUAI. STAT Ef tG CtlD ' PO TC6CER SPEC ELOG ELEV SUBH3 OP CD o***w*********** *3**nwt**************s******** *******a**** ******************** ********** ******** ********** **** VELAri lE G-01 HJHHX-8320-A89E *EQ ALL 310593 232 RB:'i 00016 A
.lP42*SOV293 RBCLC:4 RETUPN CHECK VLV ASCO *232-01 070 MIN VELAti 1E G-01 HJHHX-8320-A8?E *EQ ALL 310595 232 RBS C0039 A .lP42*SOV294 PBCLC! RETURN CHECH VLV ASCO *232-01 070 HIN VELAN 1E G-S1 HJHHX-8320-A89L *EQ ALL 310595 232 PBS 00039 A .ZB31*SOV081 OPERATES 1B31*A0V081 ASCO *318-01 070 HIN NA CCP:S VULCAN 1E H-15 HJHHX-8320-A89E *EQ ALL 310735 318 RBE 00133 A .1B31*SOV082 OPEPATES 1831*A0V092 ASCO m318-01 070 HIN NA COPE 3 VULCAN lE H -18 HJHKX-8320-A89E *EQ ALL 310735 318 RBS 0o155 A .1E11*SOV003A STil TO RHR HX SHELL ASCO *318-01 180 DYS NA COPES VVLCAti 1E G-03 HJHHX-8320-A89E *EQ ALL 310735 318 RBS 65 B .1E11*S0V003B STH TO RHR HX SHELL ASCO m318-01 180 DYS NA CCPES VVLCAN 1E G-07 HJHHX-8320-A89E *EQ ALL 310735 318 RBb 65 B .1E11*SOV007A STil TO RHR HX SHELL ASCO *318-01 180 DYS NA COPES VVLCAN 1E G-01 HJHKX-8320-A89E *EQ ALL 310735 318 RBS 12 B .1E11*SOV007B STH TO RHR HX SHELL ASCO *318-01 180 DYS HA COPES VVLCAN 1E G-01 HJHhX-8320-A89E *EQ ALL 310735 318 RBS 10 B
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.1E11*SOV051A RHR St.ftPLE LINE VALVE ASCO *318-01 070 HIN NA COPES VULCAN 1E G-01 HJHHX-8320-A89E *EQ ALL 310733 318 RBS e A .lE11*SOV061B RHR StHPLE LINE VALVE ASCO *318-01 070 HIN NA CCPES VULCAN lE G-01 HJHHX-8320-A89L *EQ ALL 310735 318 RBS 8 A
~
.lE11*SOV052A RHR SUPLE LINE VALVE ASCO *318-01 070 HIN NA COPES VULCAN 1E G-G1 HJHHX4120-A89- *EQ ALL 310735 318 RBS 8 A I
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V \ D 1E11mSOV0628 REPORT NO. PES-800 JCB 1160002 01/1(u'82 ENVIRONMENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STONE AND HEBSTER ENGINEERItiG CORPORATION JOB NUttDER 1160002 PROJECT EQUIPHENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 10
.,08 NAME SHOREHAH - U'4IT 1 ENVIRota-tENTAL QUALIFICATION STATUS PEPORT RESET NO. 003 JOB CLIENT LILCO SORTED BY - HAK / HOO / SPEC RESET DATE 07/01/81 EQUIPt:ENT ID EQUIPl!ENT DESCRIPTION HAHE / HANUFACTURER EQ SHEET OP TIHE ACC / PERF NU-CAT VENDOR ID VENCOR ttAHE QAC ZONE ItODEL / CATALOG NO QUAL STAT EHG CND PO tutBER SPEC BLDG ELEV SUBitG OP CD mem**mmmmmmmmmum *mmen.nummmmmmmmmm*mummmmmmmme summuuanmuun m*mannemannemunhunne nummmmmmme **memmum wommmmmmme amme .1E11mSOV0628 RH9 SAtPLE LINE VALVE ASCO m318-01 070 HIN NA COPES VULCAN lE G-01 HJHKX-8320-A89E mEQ ALL 310735 318 RBS 8 A .1E41mSOV081 CPERATES 1E41mA0V081 ASCO m318-01 070 HIN NA COPES VULCAN 1E G-01 HJHMX-8320-AB9E mEQ ALL 310735 318 RBS 00008 4 HARK No. REPRESENTS 4 SHITCHES .1E41mSOV002 OPERATES 1E41mA0V082 ASCO m:18-01 070 HIN NA lE COPES VULCAN G-01 HJHKX-8320-A89E mEQ ALL 310735 318 RBS 00008 A HARK NO. REPRESENTS 4 SHITCHES .1E41mS0V083 OPERATES 1E41mA0V083 ASCO m318-01 070 HIN NA COPES VULCut IE G-01 HJHHX-8320-A89E mEQ ALL 310735 318 RBS 00008 A .1E41mSOV091 OPERATES IE41mLCV091 -mASCO *318-G1 m180 *DYS mN/A .
- COPES VULCAN *1E nG-01 mHJHKX-8320-A89E *EQ MALL 310735 v318 mRBS m00008 m8
.lE41mSOV095 OPERATES 1E41mLCV095 ASCO m318-01 070 HIN NA COPES VVLCAN 1E G-01 HJHKX-8320-A89E mEQ ALL 310735 318 RBS 00008 A .1E51mSOV081 OPERATES 1E51mA0V081 ASCO m318-01 070 HIN NA CCPES VULCAN 1E G-01 HJHMX-8320-A89E mEQ ALL 310735 318 RBS 00008 A .lE51mSOV082 OPERATES 1E51mA0V082 ASCO m318-01 070 HIN NA ! COPES VULCAN 1E G-01 HJHKX-8320-A89E mEQ ALL 4
310735 318 RBS 00008 A
.1E51*SOV083 0"ERATES 1E51mA0V083 ASCO .=T18-01 070 HIN NA ~
CGPES VULCAN lE G-Ol' HJHHX-8320-A89E mEQ ALL
- 310735 318 3 t%S 00008 A
.1E51mSOV091 OPERATES 1F51mLC'!O91 - ASCO m316-01 180 DYS NA CC'ES VVLCAN 1E G-01 HJHHX-8320-A89E mEQ ALL 310735 318 RBS 00008 B .1E51=%Vv95 OPEPATES 1E51mLCV095 ASCO m318-01 070 HIN HA 1 COPES VVLCAN lE G-01 HJHHX-8320-A89E mEQ ALL 7 31073S 318 RBS 00008 A .1146mSOV040A m0PERATES A00040A mASCO *319-03 *070 *HIN
- IT46x50V340A REPORT fio. PES-800 JOB 1160002 01/18/82 EtiVIROM ENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STONE AffD HEBSTER ENGINEERING CORPORATION JOB ifJt!BER 1160002 PROJECT EQUIPtCNT SYSTEN - (IS-129) REPORT DATE 01/18/82 PAGE 11 JOB tiAttE SHOREHAN - U;iIT 1 ENVIR0talENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JOB CLIENT LILCO SORTED BY - ItAH / F.00 / SPEC RESET DATE 07/01/81 EQUIPHENT 10 E0 dipt:ENT DESCRIPTION HAHE / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VEtCCR 10 VENC09 ftAttE QAC ZOtlE HODEL / CATALOG NO QUAL STAT E' CND PO iPJ.3ER SPEC BLOG ELEV SUCHG Or CD ammmmmmmmmmmmmne muunnsmene*mmmennenumm>manan*u amenemummmm* um**mmmmmmmmmmmmmmum unnumme*** mummemum amanummmen mens POHERS REGUL *1E *H-18 mHJHHX-8320-A89E *EQ *ALL 310738 m319 mRBS *001S0 mA
.lT46mSOV040B mOPERATES A00040B *ASCO *319-03 =070 mHIH e PODERS REGUL *1E *H-18 *HJHHX-8320-A89E *EQ *ALL 31073S m319 m7OS *00150 *A .1T46mSOV0414 *0PERATES A00041A wASCO m319-03 w070 mHIN
- POWERS REGUL *1E *H-15 *HJHHX-8320-A89E *EQ MALL 310738 m319 *RBS *00112 mA
.1T46mSOV041B *0PERATt-3 A00041B mASCO *319-03 m070 wNIH
- P0HERS PEGUL ale *H-15 wHJHHX-8320-A89E mEQ *ALL 310738 *319 *RBS *00112 mA
.1P42*SOV001H RDCLCH HX E-11A BYPASS ASCO e423-01 180 DY3 NA FISHER CONTRO 1E G-01 HJHHX-8320-A89E *EQ ALL 310772 423 RBS 00008 A LOCA IS OP CODE B AFTER 70 NIH .1P42mSOV001X RBCLCH HX E-11A BYPASS ASCO *423-01 180 DYS NA FISHER L0aTRO 1E G-01 HJHHX-8320-A89E nEQ ALL 310772 423 RBS 00008 A LOCA IS OP Of)E B AFTER 70 HIH .1942mSOV00lY RBCLCN HX E-11B BYPASS ASCO e423-01 180 DYS NA FISHER CONTRO 1E G-01 HJHHX-8320-A89E *EQ ALL 310772 423 RBS 00008 A LOCA IS OP CODE B AFTER 70 ftIN .lP42*SOV001Z RBCLCal HX E-11B BYPASS ASCO -m423-01 183 DYS NA FISHER CONTRO 1E G-01 HJHHX-8320-A89E *EQ ALL 310772 423 RES 00008 A LOCA IS OP CODE B AFTER 70 NIH ~ .1T2n*SOV001A DRYHELL ISCL VLV 1724mAVO001A ASCO *318-02 180 DYS NA CCPES VULCAN 1E G-02 HJH206-380-6F *EQ L 310735 318 RDS 00040 A .1T24mSOV001B CRYHELL ISCL VLV IT24mAV0001B ASCO *338-02 180 DYS NA COPES VULCAN lE G-02 HJH206-380-6F mEQ L 310735 318 RBS 00040 A .1T46mSOV078A NR tt3V 070A ASCO *318-02 070 HIN NA C COPES VULCAN lE G-12 HJH206-380-6F *EQ ALL 310735 318 RBS 00090 A i
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IT46mSOV0788 REPORT No. FES-800 JOB 1160002 01/18/82 EtNIR0tetENTAL QUALIFICATIUN STATUS REPORT REPOPT t:0. Pc5-800 ST0t1E AND HEBSTER ENGINEERING CORPORATION PROJECT EOUIPMEt4T SYSTEH - (IS-129 ) REPORT PATE 01/18/82 PAGE 12 JCL Ntf t2ER 1160002 RESET NC. 003 JOB NAt!E SHOREHAH - UNIT 1 ENVIR0tetEliTAL QUALIFICATI0ti STATUS REPORT SORTED BY - HAK / tt0D / SPEC RESET DATE 07/01/81
. JOB CLIENT LILCO HAKE / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT EQUIPMENT ID EQUIP!!Et4T DESCRIPTION EH3 CND VENDCE tlAHE QAC ZONE HODEL / CATALOG NO QUAL STAT VENDOR ID OP CD PO tf".CER SPEC BLDG ELEV SUBitG **********n********* ***umaannu ******** ***wm**mme *wm* *mam***mme****me amm******mana*****a**wuw****** ***m*****www DRYHELL VENT TO PRIH CNT ASCO m318-02 070 HIN NA .1T46*SOV0788 AL.
COPES VULCAtt 1E G-12 HJH206-380-6F *EQ 00090 A 310735 318 RBS OPERATES IT46mA0V079A ASCO m318-02 070 HIN NA
.1746*SOV079A ALL COPES VULCAN 1E G-06 HJH206-380-6F aEQ 00063 A 310735 318 RBS OPERATES IT46aA0V0798 ASCO m318-02 070 HIN - NA .1T46mSOV0798 ALL COPES VULCAN 1E G-06 HJH206-380-6F *EQ RBS 00063 A 310735 31C 480V AUTO TRANSFER SHITCH ASCO 180 DYS 1 m *TRS111X ALL ASCO 1E N-21 307A660 TA 112 A 310922 438 RBS 480V AUTO TRANSFER SHITCH ASCO 180 DYS 1R24mTRS112Y ALL ASCO 1E N-21 307A66C TA 112 A 438 RBS l
m M
1T48*PtL4*A REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIR0tRtENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STONE AND HEBSTER EtlGIllEERING CORPORATION JCB tlUttBER 1160002 PROJECT EQUIPitEtiT SYSTEN - (IS-129) REPORT DATE 01/18/82 PAGE 13 JOB tiAME SHCREHAtt - LT4IT 1 EtNIRONitENTAL QUALIFICATIOtl STATUS REPORT RESET tio. 003 JOB CLIENT LILCO SORTED BY - itAH / HOD / SPEC RESET DATE 07/01/81 EQUlrHENT ID EQUIP!!ENT DESCRIPTION HAME / HAtCFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDOR 10 VENDOR NAttE QAC ZOt4E HODEL / CATALOG NO CUAL STAT EttG CND PO ifJf CER SPEC BLDG ELEV SUBttG CP CD wennemensween... u n ma n n e n**** *c:.em unwe se*** m u ne enemannemen* ane,*mmun*u**=mmunen menne.unan unnmww . nummmmunum muun REPORT GROUP ltAH = ATCl TICS INT
.1T48ePtL48A ehYD REC 0tt PHR PtL A mATCHICS INT
- 180 OYS NA ATCHICS INT 1E J-16 *N/A *TA L 31062:4 289 RBS 00112 A
.1T48aPIL40S HYD NEC0ft PHR PtL B *ATot1ICS INT 180 DYS NA AT0!!IC3 INT 1E J-16 *N/A *TA L 310624 289 RBS 00112 A .1T48*RC002A NYDROGEN REC 0tt0 ATONICS INT
- 180 DYS AT0ftICS INT 1E J-15 ft/A *TA L 310624 289 RBS 00112 A
.lT4 hNC0026 HYDROGEN REC 0ttB AT0ftICS INT
- 180 DYS ATOHICS INT 1E J-15 ft/A mTA L 310624 289 RBS 00112 A W
S O O O
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x % s IE11*PT003A REPCRT NO. PE3-800 JCB 1160002 01/18/82 EtNIRONMENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STot4E AND HEBSTER E!IGIIIEERING CORPORATION JOB tUfSER 1160002 PROJECT EQUIPHENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 14 JOB NAttE SHOREHAH - UNIT 1 EtNIRot(HENTAL QUALIFICATION STATUS REPORT RESET NC. 003 JOB CLIEtiT LILCO SORTED BY - HAM / HOD / SPEC RESET DATE 07/01/81 EQUIPNENT ID EQUIF?iENT DESCRIPTION HAME / HAtUFACTURER~ EQ SHECT OP TIllE ACC / PERF NU-CAT VENDOR ID VENGCR NAME QAC ZottE HODEL / CATALOG NO QUAL STAT EHG CND PO IM.3ER SPEC BLDG ELEV SUBifG OP CD unnm******wumemu **************mmmmmmmm**mmmm** **mmmmmmmmme anunmans***mmunnuw** amen ** men
- mw***mme ammmmmmmmu ann a REPORT GROUP HAN = BAILEY
.1E11*PT003A 3TH TO RHR HX SHELL BAILEY 3094 180 DYS 2X E11-N026A GENERAL ELEC IE G-01 HG556100AAA1HEH *RR ALL 310010 003 RBS 00008 8i .1L11*PT003B STil TO RHR HX LHELL . BAILEY 3094 180 DYS 2%
E11-N0268 GENERAL ELEC IE G-01 HG55610DAAA1HEH *RR ALL 310010 003 RBS 00008 B
.1E11mPT005 RHR HX SHELL TO RCIC BAILEY 3094 180 DYS m2%
E11-N028 GENERAL ELEC 1E G-01 HG556110CAAA1HEL *RR ALL 310010 003 RBS C0008 8 , .1E21*PT001A CORE SPRAY PUltP DISCH BAILEY 3094 180 DYS * < E21-N001A GEt4ERAL ELEC IE G-01 HG5541100AAA1HEH mRR L
- i. 310010 003 RBS 00008 8 i
.1E21*PT001B CORE SPRAY PUHP DISCN BAILEY 3094 180 DYS
- E21-N001B GENERAL ELEC IE G-01 HG5561100AAA1HEH *RR L 310010 003 RBS 00008 8
.1C61mPT006 frJCLEAR PRESSURE = BAILEY *3904 180 DYS 4 C61-N006 GENERAL ELEC 1E G-09 e556100EAAA1 HEN mRR ALL 310010 003 RBS 00078 8 .1E51mPT001 RCIC PUNP SUCTION
- BAILEY *3904 180 DYS *1%
E51-N005 GENERAL ELEC IE G-01 *S56110EAAA1 HEN mRR ALL 4 310010 003 RBS 00008 B
.1E51mPT002 RCIC PUHP DISCHARGE .mBAILEY m3904 180 DYS *1%
E51-N004 GENERAL ELEC IE G-01 mS56110EAAA1 HEN *RR ALL 310010 003 RB3 00008 8
.1E51mPT004 RCIC STH TO TURBINE eBAILEY *3904 180 DYS *1%
E51-N007 GENERAL ELEC IE G-01 m556110EAAA1 HEN *RR ALL 310010 003 RBS 00008 B
.1E51*PT005 TURBINE DISCHARGE
- BAILEY *3904 180 DYS *1%
E51-N008 GENERf.L ELEC *1E G-01 m556110EAAA1 HEN mRR ALL 310010 003 'RBS 00008 8 7
IB21tPS022A REPORT NO. PES-800 JOB 1160002 01/18/82 EiWIRotetENTAL QUALIFICATI0H STATUS REPOR E REPORT NO. PES-800 ST0fiE AffD HEBSTER ENGINEERIt4G CORPORATION JCB NUMBER 1160302 PROJECT EQUIPHENT SYSTEH - (IS-129) REPORT DATE 01/16/82 PAGE 15 JCB t4AttE SHOREHA!! - UNIT 1 EtWIPONitENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JOB CLIENT LILCO SCRTED BY - HAH / HOD / SPEC RESET DATE 07/01/81 EQUIPl!ENT ID EQUIPMENT DESCRIDTION HARE / ItANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDOo ID VEND 07 NAME QAC ZONE HODEL / CATALOG HO QUAL STAT EHG CND PO NUMBER SPEC BLDG ELEV SUBMG OP CD enemmmmmmmmmmune *mman.mmmmmmmmmmmmmmmmmmmmmmmu ammmmmmmmmme m******mmmmmmmmmmmme **mensamma **munnan wmmmmmmmme mama REPORT GROUP HAH = BARHSDALE
.1821mPS022A HAIN STEAN LINE ISO mBARHSDALE m3018 070 HIN *l.5%
B21-N020A GENERAL ELEC IE G-10
- BIT-H12SS mIJ L 310010 003 RBS 0007S A OP CODE B FOR HELB & HELB
.1821mPS0228 ftAIN STEAH LINE ISO mBARHSDALE m3018 070 HIN *l.5%
B21-N020B GENERAL ELEC IE G-10
- BIT-H12SS *IJ L 310010 003 RBS 00078 A OP CODE B FOR HELB & HELB
.1821*PS022C ttAIN STEAM LINE ISO .BARHSDALE *3018 070 HIN *1.5%
B21-N020C GENERAL ELEC lE G-12
- BIT-H12SS *IJ L 310010 003 RBS 00078 A OP CODE B FOR HELB & HELB
.1821mPS02ED HAIN STEAM LINE ISO mBARHSDALE *3018 070 HIN *l.5%
B21-N0200 GENERAL ELEC IE G-12
- BIT-H12SS *IJ L 310010 003 RBS 00078 A CP CODE B FOR HELB & HELB
.1E41*PSC02 HPCI PtXtP DISCHARGE eBARKSDALE 3018 001 DYS E41-N027 GENERAL ELEC IE G-01
- BIT-H12SS mIJ ALL 310010 003 RBS 00008 A
.1E51*PS002 RCIC PUHP DISCHARGE BARMSDALE 3018 001 DYS m2.6%
ESI-N020 GENERAL ELEC IE G-01 BIT-H12SS *IJ ALL 310010 003 RBS 00008 A
.1E11mP3134A RI.R PUHP DISCHARGE BARHSDALE 3018 1 DYS *.8%
E11-N016A GENERAL ELEC lE G-01 BIT-H12SS *IJ MALL 310010 003 RBS 8 A ~
.lE11*PS1348 RHR PUMP DISCHARGE BARHSDALE 3018 1 DYS *.8%
E11-N0168 GENERAL ELEC IE G-01 BIT-H12SS *IJ MALL 310010 003 RBS 8 A
.1E11mPS134C RHR PUMP DISCHARGE BARHSDALF 3018 1 DYS m.8%
E11-N016C GENEPAL ELEC IE G-01 BIT-H12SS *!J MALL 348838 003 RBS 8 A 7 .1E11mPS134D RHR PUHP DISCHARGE BARHSDALE 3018 1 DYS *.8% E11-N0160 GENERAL ELEC IE G-01 BlT-II12SS .IJ *ALL 310010 003 RBS 8 A O O O
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IE11tPS135A REPORT NJ. PES-800 JOB 1160002 01/18/82 v ENVIRONHENTAL QUALIFICATION STATUS REPORT v REPCRT NO. PES-800 STONE AND HEBSTER ENGINEERING CORPORATION JCB NUttBER 1160002 PROJECT EQUIPitENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 16 JCB NAttE SHOREHAM - UNIT 1 EtNIR0talENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JOB CLIENT LILCO SORTED BY - HAM / H00 / SPEC RESET DATE 07/01/81 l EQUIPHENT ID EQUIPitENT DESCRIPTION HAHE / HAtlUFACTURER EQ SHEET OP TIHE ACC / PERF NU-CAT VEllDOR ID VENCC1 NAME QAC ZCNE HODEL / CATALOG NO QUAL STAT EHG Cte PO FUSER SPEC BLDG ELEV SUBHG OP CD man **menemmene** mem*m**me*******wwman**m=***** mamanum** mum *mmuuuuwammmmmmewone amm****uwe ww***mww mammenwume wwww
.1E11*PS135A RhR PUltP DISCHARGE BARMSDALE 3018 1 DYS w.8%
E11-N020A GENERAL ELEC IE G-01 BIT-H12SS =IJ *ALL 310010 003 RBS 8 A
.1E11*PS135B PHR PU!!P DISCHARGE BARHSDALE 3018 1 DYS w.8%
E11-N020B GENER*1 ELEC 1E G-01 BIT-H12SS sIJ *ALL 310010 003 RBS 8 A
.lEll*PS135C RHR PUHP DISCHARGE BARKSDALE 3018 1 DYS m.8%
E11-N320C GENERAL ELEC IE G-01 B1T-H12SS mIJ =ALL 340038 003 RBS 8 A
.1EllmPS135D RHR PU?!? DISCHARGE BARMSLALE 3018 1 DYS *.8%
Ell-N020D GEIG AL ELEC IE G-01 BIT-H12SS mIJ *ALL 310010 003 RBS 8 A - .lE41mPS025A DRAIti POT VENT BARKSDALE 3021 001 DYS 4 E41-N012A G.E. IE G-01 02H-H150SS *IJ ALL 310010 003 RDS 00008 A
.1E41*PS025B DRAIN POT VENT BARKSDALE 3021 001 DYS E41-NJ12B G.E. IE G-01 D2H-H15055 *IJ ALL 310010 003 RBS 00008 A .lE41*PS32SC DRAIN POT VEtiT BARKSDALE 3021 001 DYS
, E41-N012C G.E. lE G-01 D2H-H150SS mIJ ALL 4 310010 003 RBS 00008 A
.1E41*PS025D DRAIN POT VENT BARKSOALE 3021 001 DYS E41-N0120 G.E. IE G-01 D2H-H150SS mIJ ALL 310010 003 RBS 00008 A .1E41=P5026A HIGH EXHAUST LINE PRESS BARKSDALE 3021 001 DYS *10%
E41-H017A G.E. IE G-01 D2H-H150SS *IJ ALL 310010 003 RBS 00008 A
~ .1E41*PS026B HIGd EXHAUST LINE PRESS BARKSDALE 3021 001 DYS *10%
E41-H017B G.E. 1E G-01 D2H-H150SS *IJ ALL 310013 003 RBS 00000 A
.1E11*PS138A PRIHXtY COMTAltOfENT HP BARHSDALE 3021 070 HIN n.1 PSIG E11-N010A GENEF:AL LLEC IE G-10 02H-hl8SS *IJ L 310010 003 RBS 00008 A OP CGDE S FOR HELB & HELB .1E11*PS138B PR1HARY EONTAIt# TENT HP BARHSDAL E 3021 070 HIN w.1 PSIG E11-N0108 GENEEAL ELEC IE H-12 D2H-H18SS *IJ L 4 .
1E11tPS138B REPCRT NO. PES-800 JOB 1160002 01/18/82 ENVIR0t:tENTAL QUALIFICATION STATUS REPORT REPCRT NO. PES-800 STONE AtlD HEBSTER Et431NEERING CORPORATION JOB bU!fBER 1160002 PROJECT EQUIFi?ENT SYSTEM - (IS-129 ) REPORT DATE 01/18/82 PAGE 17 JOB NAllE SHO9EHAN - L"iIT 1 ENVIRO llHENTAL CUALIFICATION STATUS REPORT RESET tiO. 003 J00 CLIENT LILCO SORTED BY - HAM / HOD / SPEC RESET DATE 07/01/81 EQUIPHENT ID EQUIPMENT CESCRIPTIOff HAME / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDOR ID VETO M HAHE QAC ZONE h0 DEL / CATALOG NO QUAL STAT ENG CND PO to:SER SPEC BLDG ELEV SUBMG OP CD rumenm********** eme*w-*****menuw************** man ****mumme ***mmmm*****mummen** ummeneemm* ummunam* mummmmmmen m*u* 310010 003 RBS 00078 A CP CODE S FOR HELB & HELB
.1E11*PS138C PRIHf.RY CONTAIt01ENT HP BARKSDALE 3021 070 HIN *.1 PSIG E11-N010C GENERAL ELEC IE G-10 D2H-H18SS *IJ L 310010 003 RBS ;3078 A OP CODE B FOR HELB 1 HELB .lE11*PS1380 PRIHARY CONTAItttENT HP BARMSDALE 3021 070 HIN *.1 PSIG E11-N0100 GENERAL ELEC lE H-12 DZH-H18SS *IJ L 310010 003 RBS 00078 A OP CODE D FOR HELB & HELB .1E51erS025A DRAIN FOT VENT BARKSDALE 3021 001 DYS *2.7%
E51-N312A GENEPAL ELEC lE G-01 02H-H80SS *IJ ALL 310010 003 RBS 00008 A
.lE51mPS0253 CRAIN POT VENT DARKSDALE 3021 001 DYS m2.7%
E51-N012B GENER/.L ELEC IE G-01 02H-H80SS *IJ ALL 310010 003 RBS 00008 A
.1E51*PS025C DR AIN POT VENT BARMSDALE 3021 001 DYS *2.7%
E51-N012C GENERAL ELEC IE G-01 D2H-H80SS *IJ ALL 310010 003 RBS 00008 A
.lE51mPS0250 DoV.N POT VENT BA9HSDALE 3v21 001 DYS *2.7%
E51-NJ120 GEtiERAL ELEC 1E G-01 02H-H80SS mIJ ALL 310010 003 P' S A0008 A
.lE51*PS026A HIGH EHAU3T LINE PRESS BARKSDALE 3021 001 DYS *2.5%
E51-N009A GENERAL ELEC 1E G-01 D2H-H80SS *IJ ALL 310010 003 RBS OJ008 A
.1E51*PS0268 HIGH EHAUST LINE PRESS DARKSDALE 3021 001 DYS *2.5%
E51-N009B GENERAL ELEC 1E G-01 02H-H80SS *IJ ALL 310010 003 RBS 00008 A
.lE21mPS012A COPE SPRAY PU!P DISCH BARKSDALE 3025 007 DYS *1.5%
E21-N003A GENERAL ELEC IE G-01 PlH-H34SS *IJ L 310010 003 RBS 8 A
.lE21*PS0128 CORE SPRAY Pulp DISCH BARHSDALE 3025 007 DYS *l.5%
E21-N0008 GENEE L ELEC IE G-01 P1H-H34SS *IJ L 310010 003 RBS 8 A
.1E21 PS013A CORE SPRAY PUt.' DISCH BARHSDALE 3025 007 DYS *1.5%
E21-N007A GENERAL ELEC lE G-01 P1H-H34SS *IJ L O O O
O O 1E21mPS013A REPORT FC. PES-800 JOB 1160002 01/18/82 EINIR0t#1 ENTAL QUALIFICATI0H STATUS REPORT REPORT P10. PES-800 STONE AtB. HEBSTER ENGINEERING CORPORATICH JOB Nut!EER 1160002 PROJECT EQUIPitENT SYSTEH - (IS-129 ) REPORT DcTE 01/18/82 PAGE 18 JOB flAttE SHOREHAH - LafIT 1 EtNIRTRIENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JCB CLIENT .LILCO SORTED BY - HAH / HOD / SPEC RESET DATE 07/01/81 EQUIPitENT ID EQUIFl!EtiT DESCRIPTION HAME / HANUFACTUREit EQ SHEET OP TIME ACC / FERF NU-CAT vet 00R ID VENDOR HAHE QAC ZONE H00EL / CATALOG NO QUAL STAT EHG Cie PO NUl!BER SPEC BLOG ELEV SUBHG OP CD
*mummmmmmmmmmm** mumm *****mmen**mm**um*m* man *** **munummenum mummmmmmm****mmmmm** *munumme ms **mmanum summmmmmme
- mum 310010 003 RBS 8 A
.1E21mPS013B CORE SPRAY PUHP DISCH BARKSDALE 3023 007 DYS *1.5%
E21-N0098 GEriERAL ELEC IE G-01 P1H-H34SS mIJ L 310010 003 RBS 8 A l
IB21*PDS02n REPORT NO. PES-8G0 JCB 1160002 01/18/8? EtNIR0!iHENTAL QUALIFICATIO.i 3TATUS REPORT REPORT NO. PES-800 STONE Arc HEBSTER ENGItiEER1? G CORPORATION JOS t1UtEER 1160002 PROJECT EQUIPt!ENT SYSTEH - (IS-1291 REPORT DATE 01/18/82 PAGE 19 I JOB NAME SHOREHAM - UNIT 1 ENVIRC:2fENTAL QUALIFICATICN STATUS REPORT RESET NO. 003 JCS CLIENT LILCO SORTED BY - itAH / H00 / SPEC RESET DATE 07/01/81 EQUIPMENT ID EQUIPMENT DESCRIPTION HAhE / HAto!.irTURER EQ SHEET OP TIME ACC / PERF NU-CAT VEtOOR NAttE QAC ZCNE HOCEL / CATALnG NO QUAL STAT EHG CiG vet 1COR ID POtC OER SPEC BLD3 ELEV SU3tfG OP CD
***me=amenennamn monum amummm**menemme****mn*** **me**memen* **memanumm**me***mme amamenemme anunumme sammenenne usan REPORT GROUP HAM = BARTON .1B21mPDS02A1 MAIN S?H LINE A FLCH DET BARTON 3027 001 DYS m2X B21-N006A GENERAL ELEC IE G-02 288A mIJ H 310010 003 RBS 00040 A .1821mPDS02A2 HAIN STH LINE A FLOH DET BARTON 3027 001 DYS *2%
B21-N006B GENERAL ELEC IE G-02 288A mIJ H 310010 003 RBS 00040 A
.1821mPDS02A3 HAIN MH LI?tE A FLOH DET BARTON 3027 001 DYS m2%
GENEr4L $ EC IE G-02 288A mIJ H B21-N0060 310010 003 RBS 00040 A
.1B2'..M $0 D4 HAIN STH LINE A FLOH DET DARTON 3027 001 DYS m2%
GEf2ERAL ELEC IE G-02 288A *IJ H B2146660 310030 003 RBS 00040 A
.1021*PDS0281 HAIN STH LINE B FLOH DET BARTON 3027 001 DYS m2%
GENERAL ELEC 1E G-02 286A *IJ H B21-N007A 310010 003 RDS 00040 A l
.EB21*PDSO2B2 HAIN STN LINE B FLOH DET BARTON 3027 001 DYS m2%
IE G42 280A *IJ H l 821-N0078 GENERAL ELEC 310010 003 PES 00040 A
.1821*PDS0283 MAI'1 STH LINE B FLOH DET BARTON 3027 001 DYS m2%
B21-N007C GENERAL ELEC IE G-02 288A mIJ H 003 RBS 00040 A 310010
.1B21.PDS02B4 HAIN STH LINE B FLnH DET BARTON 3027 001 DYS m2%
E21-t:007D GENERAL ELEC 1E G-02 28tA *IJ H 310010 003 RBS 00040 A
~ .1921mPDS02C1 HAIN STH LINE C FLOH DET BARTON 3027 001 DYS m2%
B21-N008A CENERAL ELEC IE G-02 288A mIJ H 310010 003 RBS 00040 A
.1821*PD502C2 t'.AIN S1H LINE C FuM 03T BA4 TON !021 001 DYS m2%
B21-N008B GENERAL ELEC 1E G-32 28SA a2J H 310U10 003 RSS 00040 A 7 .1821*PDS MC3 ftAIN STH lit 1E C FLOH DET BARTON 3027 001 DYS m2% GENERtL ELEC IE G-02 288A mIJ H B21-N008C 310010 003 RBS 00040 A O O O
O r [\ k 1821mPDS02C4 REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIROt8tENTAL QUALIFICATION STATUS REPORT REPCRT No. PES-800 STONE AND HEBSTER ENGINEERING CORPORATION JOB NUtfBER 1160002 PROJECT EQUIPitENT SYSTEH - (IS-129 ) REPORT DATE 01/18/82 PAGE 20 JCB NAME SHCREHAM - UNIT 1 ENVIRON!tENTAL QUALIFICATION STATUS REPORT RESET No. 003 JOB CLIENT LILCO SORTED BY - itAH / HOD / SPEC RESET DATE 07/01/81 EQUIPitENT ID EQUIP!ENT DESCRIPTION ltAME / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDOR ID VENCCR NAME QAC ZONE HODEL / CATALOG NU QUAL STAT EHG Ctc PO NUttBER SPEC BLDG ELEV SUDNG OP CD
**wwwwammunnam** *******mnume**wnsmanam***mm*** unsw.ww****z **wmanumw*****mgu*me *wumunum*w nummmwww *w******** ****
I
.1821mPDS02C4 MAIN STH LINE C FLOH DET BARTON 3027 001 DYS *2%
B21-N0080 GENCAL ELEC IE G-02 288A *IJ H 310010 003 RBS 00040 A
.1D21mPD% 201 HAIN STH LINE D FLOH DET BARTCN 3027 001 DYS *2X B21-H009e GENERAL ELEC IE G-02 288A w!J H 310010 003 RBS 00040 *. .1B21 90502D2 HAIN STM LINE D TLOH DET BARTON 3027 001 DYS *2%
B21-N009B GENERAL ELEC 1E G-02 288A *IJ H 310010 003 RBS 00040 A
- .1821*PDS0203 ftAIN STH LINE D FLOH DET BARTON 3027 001 DYS *2%
GENEP.4. ELEC IE G-02 288A *IJ H B21-N009C 310010 003 RBS 00040 A
.1821*PDS0204 MAIN STH LINE D FLOH DET BARTON 3027 001 DYS *2%
B21-N0093 GENERAL ELEC IE G-02 288A *IJ H 310010 003 RBS 00040 A
.1".71ePS004 PRIttA'tY CONTAINHENT HP BARTON 3027 180 DYS *1% PSIG 071-N004 GENERAL ELEC IE G-10 288A *IJ ALL 310010 003 RBS 00078 8 .IE21*PDS033A CORE SPRAY PUFP DISCH BARTON 3027 180 DYS
- E21-N005A GENERAL ELEC IE G-01 288A *IJ L 310010 003 RBS 00008 A
.1E21 PDS033B CCRE SPRAY PUNP DISCH BARTON 3027 180 DYS
- E21-N005B GENERAL ELEC IE G-01 288A *IJ L 310010 003 RBS 00008 A
.1E41mPDS022A HPCI AUTO ISCLATION BARTON 3027 001 DYS *.8%
GENERAL ELEC IE G-01 288A *IJ ALL , E41-N004 003 RBS 00008 A 310010
~ .1E41*PDS022B HPCI AUTO ISOLATION BARTON 3027 001 DYS *.8%
GINERAL ELEC IE G-01 288A *IJ ALL E41-N005 310010 003 RBS 00008 A
.1E41*PS023A HPCI AUTO ISOLATION BARTON 3027 001 DYS *.5%
GENERAL ELEC IE G-01 288A *IJ ALL E41-N001A 31001C 003 RBS 00008 A I C .1E41*PS023B HPCI AUTO ISOLATION BARTON 3027 001 DYS *.5% i GENERAL ELEC IE G-01 288A *IJ ALL E41-H001B 003 RBS 00008 A 310010
IE411PS023C REPORT r:3. PES-800 JCB 1160002 01/18/82 EtNIRotatENTAL QUALIFICATION STATUS REPORT RLTORT NO. PES-800 ET0 tie AND HEBSTER ENOINEERIN3 CORPORATION JOB hut'CFR 1160002 PROJECT E Q'JIPMENT SYSTEN - (IS-129) REPCRT DATE 01/le<82 eAGE 21 J03 NAlfE SHOREHAN - UNIT 1 ENVIPot# ENTAL QUALIFICATION STATUS REPCRT RESET F10. 003 JCB CLIENT tILCO SORTED BY - HAM / tt00 / SPEC RESET DATE 07/01/81 EQUIPitENT ID EQUIP.tEtiT DESCRIPTION t!AME / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT vet 0CR ID VEtiDC3 NAt1E QAC ZONE HODEL / CATALOG NO QUAL STAT EMG CtB PO Nt210ER SPEC BLDG ELEV SUBitG OP CD cuevammmmmmmmmem **=m.imamunummmmmmmmmmmmmmmmum nummmmmmmmma mam***mmmmmmmmmmmmmu en*munuman mummmmen ammmmmmmme aman
.lE41*PS003C HPCI AUTO ISCLATION Bt7 TON 3027 001 DYS *.5%
E41-N001C GENERAL ELEC IE G-01 288A mIJ ALL 310010 003 RBS D0008 A
.1E41mPS023D HPCI AUTO ISCLATION BARTCH 3027 001 DYS *.5%
E41-N0010 GENERAL ELEC IE G-01 288A mIJ ALL 310010 003 RBS 00008 A
.1E51mFS053 RCIC PuttP DISCHARGE Bs.RTON 3027 001 DYS *5%A E51-H002 GENERAL ELEC lE G-01 288A mIJ ALL 310010 003 RBS 00008 A .lE51mPDS022A RCIC AUTO ISOLATION BARTON 3027 001 DYS *2%
E51-N017 GENERAL ELEC 1E L-02 288A mIJ ALL 310010 003 RBS 00040 A 1E51mFOS020E, RCIC AUTO ISOLATION BARTON 3027 001 DYS m2% E51-N018 GENERAL ELEC 1E L-02 288A *IJ ALL 310010 003 RBS 00040 A
.1 Ell *PDS001A VALVE INTERLCCH BARTON m3027 180 DYS 1.5%
Ell-H021A GEtlEFAL ELEC IE G-01 289A mIJ AL' . 310010 003 RBS 00008 A
.lEllePOS001B VALVE INTERLOCH BAnTON *3027 180 DYS 1.5%
Ell-N021G OENERAL ELEC IE G-01 289A mIJ ALL 320010 003 RBS 00008 A 2 UTS002A CORE SPRAY PUttP DISCH BARTON m3027 180 DYS *
'.1-b 06A GENERAL ELEC IE G-01 2C9A *IJ L 31C010 003 RBS 00008 A .lE21mFIS002B CORE SPRAY PUtlP DISCH BARTON m3027 180 DYS =
E21-N006B GENERAL ELEC 1E G-01 289A mIJ L 310010 0D? RBS 00008 A ~ IE41mFS003 HPCI PUt!P DISCHARGE BARTON m3027 001 DYS E41-N006 Cft;ERAL ELEC IE G-01 289A *IJ ALL 310010 003 RBS 00008 A
.lfilvLT000A RNR HX ShELL BART0ti m3144 180 DYS *.5% SPAN E11-N008A GEN PAL ELEC IE G-01 368 mRR ALL 310010 003 RBS 8 B C .1E11mLT0028 RHR HX SHELL BARTON *3144 180 DYS *.5% SPAN E11-N0088 GENERAL ELEC IE G-01 368 mRR ALL 310010 003 RBS 8 8 I
O O O
. . _ . . . . _ _ _ .m__. _ _ _ _ _ _ . _ __ __ _ _ _ . . ,
( O C O 1821mLIT007A REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIRONHENTAL QUALIFICATION STATUS REPORT I STONE AND HEBSTER ENGINEERING CORPORATION REPORT PC. PES-800 i JOB NUttBER- 1160002 PROJECT EQUIPHEN' SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 22 1 JCB HAME SHOREHAH - UN ENVIR0tatENTAL QUALIFICATION STATUS REPORT RESET NO. 003 , i JOB CLIENT LILCO SCRTED BY - HAM / It0D / SPEC RESET DATE 07/01/81 i EQUIPHENT ID EQUIPMENT DESCRIPTION HAKE / NAtAJFACTURER EQ SHEET OP TIME ACC / PERF. NU-CAT vet 00R ID VENDOR NAME QAC ZONE NODEL / CATALOG NO QUAL STAT EHG Ctc PO NL*lTER SPEC BLDG ELEV SUBHG OP CD mummmmmmmmmmmmme mammmmmmmmmmmmmmmmmmmmm* men *** *me***mannen asummmmmmmmm*****mme nummmmmen* monumam* **menemans *mm*
.1B21mLIT007A FUEL ZON2 BARTON 3129 180 DYS
- mRG I B21-N037A GENERAL ELEC IE G-09 760 mRR ALL 4 310010 403 RBS 00078 A
.1821mLIT0078 FUEL ZONC BARTON 3129 180 DYS
- mRG I B21-N037B GENERAL ELEr 1E G-11 760 mRR ALL I 003 00078 A 310010 RBS
- .1821*PT004A REACTDR PRESSURE BARTON 3129 180 DYS
- mRG B21-N055A GENERAL ELEC IE G-10 760 mRR ALL '
310010 003 JoS 00078 A
- l
.1821mPT0006 REACTCR PRESSURE BARTON 3129 ISO DYS * *RG B21-N0553 GENERAL ELEC IE G-Ib 760 mRR ALL 310010 003 RBS 00078 A h
l i i 1 i i i i l 1 8 4 4 -
= ,
t i
1E41tPCV142 REPORT liO. PES-800 JCB 1160002 01/18/82 EtNIRONNENTAL QUALIFICATI0H STATUS REPORT CEPORT NO. PES-800 STONE AND HEBSTER EtlGIt4EERIttC CORPORATION JOB tlUMBER 1160002 FROJECT EQUIPHENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 23 JOB flat!E SHOREHAM - UNIT 1 EtWIRotC! ENTAL QUALIFICATIGN STATUS REPORT RESET F40. 003 jot 1 C* IENT LILCO SORTED BY - HAR / H00 / SPEC RESET DATE 07/01/81 ECUIFMENT It' ECUIPt1EliT DESCRIPTION HAME / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENCC. ID VENDOR NAHE QAC ZONE HODEL / CATALOG NO QUAL STAT EHG CND PO NUMOER SPEC BLOG ELEV SUBMG OP CD
**4**manns****me ****mam******me**mensen*me*mme mammamannum* ummmmmmmmmm**mammuun ********** *mensmem ammmmmmm** umm*
REP)RT GPOUP HAM = BECH
.1E11.PCV142 TO LUBE OIL COOLER BECH *310-01 001 DYS WA E41-F035 FISHER CONTRL 3E G-01 14-101-023645(ES) *IJ ALL 310736 310 RBS 16 Ai .1ES1mPCV142 TO LUBE CIL COOLER BECH *310-01 001 DYS N/A E51-F015 FISHER CotiTRL 1E G-01 14-101-023645(ES) *IJ ALL 310736 310 RBS 00('08 A .lT46*TCV022A RB STAtOBY VENT UC 2A 3ECH *310-01 180 DYS N/A FISHER cot 4TRL lE G-01 14-101-023645(ESI *IJ ALL 310736 310 RBS 00008 A .lT46mTCV0223 RB STA?CBY VENT UC 2B BECH m310-01 180 DYS N/A f! SHER CONTRL 1E G-01 14-101-023645(ES) mIJ ALL 310136 310 RBS 00040 A .1T46mTCV023A RB STAf0BY VENT UC 3A BECH *310-01 180 DYS N/A FISHER C0tiTRL 1E G-01 14-101-023645(ES) mIJ ALL 310736 310 RBS 00008 A .1T46mTCV0238 RB STAtCBY VENT UC 3B CECH m310-01 180 DYS N/A FISiiER Cot 4TRL lE G-02 14-101-023645(ES) *IJ ALL 310736 310 RBS CE040 A .lT46mTCV024A RB STAtCBY VENT UC-4A BECH *310-01 180 DYS N/A FISHER C0t1TRL 1E H-20 14-101-023645(ES) *IJ ALL 310736 310 RBS 175 A .1T46*TC'M 4B RB STA!CBY VENT UC-4B BECH v310-01 180 DYS F4/A FISHER Cor1TRL lE H-20 14-101-023645(ES) *IJ ALL 310736 310 RBS 175 A
~
.1T46*TCV025A RB STANDBY VENT UC-5A BECH *310-01 180 DYS N/A FISHE7 CONTRL lE H-20 14-101-023645(ES) *IJ ALL 310736 310 RBS 175 A .1T46*TCV0258 PB STAtiDBY VENT UC-5B RECH *310-01 180 DYS N/A FISHER CCNTRL 1E H-20 14-101-023645(ES) *IJ ALL 310736 310 RBS 175 A 5 .lT46mTCV026A RB STAT:D3Y VENT UC.6A BECH m310-01 180 DYS N/A FISHER CONTRL IE H-IS 14-101-023645(ES) *IJ ALL 310736 310 RBS 00112 A O O O
i
.[ } ' ^ %./
IT46mTCV006B REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIRONNENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-8,0 ST0ttE AND HEBSTER ENGINEERItG CORPORATION JOB NUtfBER 1160002 PROJECT EQUIPttENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 24 JCB NAPfE SHOREHAM - UNIT 1 ENVIROtDtENTAL QUALIFICATION STATUS REPORT RESET NO. 003 JOB CLIENT LILCO SORTED BY - M M / HOD / SPEC RESET DATE 07/01/81 OUIPHENT ID EQUIPitENT DESCRIPTION HAKE / HANUFACTURER EQ SHEET OP TIHE ACC / PERF NU-CAT ZONE H00EL / CATALOG NO QUAL STAT EHG CND vet 00R ID VEtCOR NAHF QAC POFU GER SPEC BLDG ELEV SUBitG OP Ctl mammannemanee um mamama.nenemummmmmmmmmemamen** mannenamen** mame*mmemamen**mma** *eemme**me nummmmmm *****mmen* **me
.1T46*TCV02(B RB STANDBY VENT UC-6B CECH m310-01 180 OYS WA FISHER CONTRL 1E H-15 14-101-023645tES) *IJ ALL 310736 310 RBS 00112 A .1T46*TCV028A HCC Rtl UNIT COOLER BECH .310-01 180 DYS WA FISHER CONTRL 1E N-16 14-101-023645(ES) *IJ ALL 310736 310 RBS 00112 A .1T46mTCV028B ttCC Rlf UNIT COOLER BECH *310-01 180 DYS WA FISHER CONTRL 1E H-15 14-101-023645(ES) *IJ ALL 310736 310 RBS 00112 A .1T46mTCV059 A UC-21A LHIT CLEAR BECH *310-01 180 DYS WA FISHER CONTRL 1E H-19 14-101-023645(ES) *IJ ALL 310736 310 RBS 00150 A .1T46mTCV059B UC-21B UNIT CLEAR BECH *310-01 180 DYS WA FISHER CONT. 1E H-19 14-101-023645( ES ) mIJ ALL 310736 310 RBS 00150 A .1T4deTCV060A UC-22A UNIT CLEAR BEtr( *310-01 180 DYS WA FISHER CONT. IE H-19 14-101-023645(ES) mIJ ALL 310736 310 RBS 00150 A .1T46mTCV0608 UC-220 UNIT CLEAR EECH m310-01 180 DYS WA FISHER CONT. 1E H-19 14-101-023645tES) mIJ ALL 310736 310 RBS 00150 A
1R30tr4FP-63 REPORT tc. PES-800 JOB 1160002 01/18/C2 EtiVIR0t41 ENTAL QUALIFICATION STATUS REPORT ' REPCET NO. PES-800 ST0r4E AFC HEBSTER ENGIffEERIti3 CORPORATION JOB NUttGER 1160002 PROJECT EQUIPMENT SYSTEH - (IS-129) REPORT DATE 01/18/82 PAGE 25 JOB NAttE SHOREHAll - LTIIT 1 ENVIROfiHENTAL QUALIFICATICN STATUS REPORT RESET NO. 003 JOB CLIEtiT LILCO SCRTED BY - HAM / HCD / SPEC RESET DATE 07/01/81 EQUIPitENT ID EQUIPMENT DESCRIPTION HAME / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDCR ID VEtCO2 14AttE QAC ZONE HODEL / CATALOG HO QUAL STAT EHG CND PO F10lf3ER SPEC BLDG ELEV SUBMG CP CD gammes**mmmmmmen ammmmmamammanummmmmmmmmmmmmmma ***mmammme** ***me**mmmmmmmmmmmme ammmmm**** maammmme ***munumme man
- REPORT GROUP ltAM = BEATO REX
.1R 32mtiFP-63 mIllST CABLE BRAT 0 REX e455 fl1 180 DYS N/A BRAto REX IE ALL LOH CAP INST CABLE EQ alt.
310965 455 RB eSPR A REPRESENTS ALL CABLE PURCHASED Ut0ER SH1-455 O O O
4 9 O O O 1G33mTE071A REPORT NO. PES-800 JOB 1160002 01/18/82 EtNIRotC1 ENTAL QUALIFICATION STAlUS REPORT REPORT NO. PES-800 SToriE AND HEBSTER ENGINEERING CORPORATION JOB HUtBER 1160002 FROJECT EQUIPMENT SYSTEH - TIS-129) REPORT DATE 01/18/82 PAGE 26 JOS tlAttE SHOREHAN - UNIT I ENVIRONitENTAL QUALIFICATION STATUS REPORT RESET NO. 003 , JOB CLIEHi LILCO SORTED BY - HAH / HOO / SPEC RESET DATE 07/01/81 EQUIPt'ENT ID EQUIPMENT DESCRIPTION HAHE / HANUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT a VEtOOR ID VENDOR HAHE QAC ZONE HODEL / CATALUG NO QUAL STAT EH3 CND PO t;UtISER SPEC BLOG ELEV SUBMG OP CD amen *munnenummma **umummmmmmmm**mmmmmmmuummuuan woman **manne mammmmmmmmmmmmmmm*** men ***m*** mammmmum ammmmmmame
- mum REPORT GROUP HAN = CALIF. ALLOY
.1G33mTE071A RX HTR CLN UP A!B CALIF. ALLOY 3110 m001 *DYS mANSI C96.1 G33-H016A GENERAL ELEC 1E P-14 s145C3224P2 *IJ *H 310010 003 RBS 112 A .1G33*TE0718 RX HTR CLN UP AMB CALIF. ALLOY 3110 *001 *DYS mANSI C96.1 G33-N016B GENERAL ELEC IE P-13 145C3224P2 mIJ *H 310010 003 RBS 112 A .1G33mTE071C RX HTR CLN UP afb CALIF. ALLOY 3110 070 HIN mANSI C96.1 G33-N016C GENERAL ELEC 1E H-15 145C3224P2 mIJ H.H i 310010 003 RBS 140 A l .1G33mTE071D RX HTR CLN UP AFB CALIF. ALLOY 3110 070 HIN mANSI C96.1 4 G33-H0160 GENERAL ELEC IE H-16 145C3224P2 mIJ H.H . 310010 003 RBS 140 A .1G33mTE071E RX HTR CLN UP AFB CALIF. ALLOY 3110 070 HIN mANSI C96.1 G33-H016E GENERAL ELEC IE H-18 145C3224P2 mIJ H.H 310010 003 RBS 173 A 4 .1G33mTE071F RX HTR CLN UP AHB CALIF. ALLOY 3110 070 HIN mANSI C96.1 C33-N016F GENERAL ELEC IE H-19 145C3224P2 mIJ H.H 310010 003 RBS 173 A 4
I l M i 4 i __ m
1821 ATE 43AX REPORT tio. PES-800 JOB 1160002 01/18/82 ErNIRotiHENTAL QUALIFICATION STATUS REPORT REPORT tiO . PES-800 STOfiE Ato HEBSTER ENGINEERIrlG CORPCRATION JCB NUtfDER 1160002 PRO, LECT EQUIPHENT SYSTEM - (IS-129) REPORT DATE 01/18/82 PAGE 27 JC3 NA!!E SHCREHAH - UtiIT 1 EtWIRotutENTAL QUALIFICATICH STATUS REPORT RESET NO. 003 JCB CLIENT LILCO SORTED BY - HAK / HOD / SPEC RESET DATE 01/01/81 EQUIPMENT ID EQUIP 6fEtiT DESCRIPTION liAME / HAtiUFACTURER EQ SHEET OP TIME ACC / PERF NU-CAT VENDOR ID VEtiDCA flAHE QAC ZOtlE HCDEL / CATALOG NO QUAL STAT EHG Cic PO titrBER SPEC BLDG ELEV SUSitG OP CD m***********mene **********=me=*******u******** **mennennen* **manemm**mmmmmmmmme nummannamm *****mme naammmunne **** REPCRT GROUP ltAH = CALIFCRNIA ALLOY
.1021*TE43AX HAIN STH TUttiEL ItLET
- CALIFORNIA ALLOY m3110 m70 *HIN mANSI C96.1 B21-N016A GEriERAL ELEC IE ST *145C3224P001 mDR H 310010 003 ST 00078 A OP CODE C FOR REHAINDER OF HELB
.1B21mTE43BX ttAIN STH TUttiEL ItLET aCALIFORNIA ALLOY m3110 m70 *HIN mANSI C96.1 B21-N016B GENEPAL ELEC IE ST v145C3224P001 *DR H 310010 003 ST 00078 A OP CODE C FOR REHAINDER OF HELB .1B21mTE43CX HAIN STM TUNNEL INLET mCALIFORNIA ALLOY m3110 m70 mHIH mANSI C96.1 B21-tt016C GEtiE2AL ELEC IE ST v14SC3224P001 *DR H 310010 003 ST 00078 A OP CODE C FOR REttAIt0ER OF HELB .1821mTE43DX HAIN STH TuttiEL ItLET m2ALIFORNIA ALLOY m3110 m70 *HIN
- ANSI C96.1 B21-N0160 GENERAL ELEC IE ST m145C3224P001 mDR H 310010 003 ST 00078 A OP CCDE C FOR PEHAINDER OF HELB 9
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[ r v ( IT46sA00040A REPORT NO. PES-800 JOB 1160002 01/18/82 ENVIR0rtiENTAL QUALIFICATION STATUS REPORT REPORT NO. PES-800 STONE -AND HEBSTER ENGINEERING CORPORATIOtt PROJECT EQUIPHENT SYSTEtt - (IS-129 ) REPORT DATE 01/18/82 PAGE 28 J03 FUtfBER 116:002 JOB NAME SHOREHAft - Ui4IT 1 ENVIRot#fENTAL QUALIFICATI0ft STATUS REPORT RESET NO. 003 JOS CLIENT LILCO SORTED BY - HAM / H00 / SPEC RESET DATE 07/01/81 EQUIPMENT ID EQUIP!:ENT DESCRIPTION H WE / hat 0FACTURER EQ !)iEET OP TIHE ACC / PERF NU CAT QAC ZONE hCDEL / CATALOG NO -QUAL STAT Ef1G Cte vet 00R ID vet 0CR NAME PO tel3ER SPEC. BLDG ELEV SUBitG OP CD num***** **mmmm*mem **mm esummmmmmmmmmmen.mammmmm******mmmmmmmmmmm****** mummmmmmmmme mummmmmmmmmmmmmmmmme mummmmm**u REPORT GROUP HAN = CENTERL1tif
.1T46mA00040A RB REFUEL LEVEL EXHAUST CENTERLINE m319-01 070 MIN POWERS REGUL 1E H-18 32046-6 mEQ ALL 319 RBS 00150 A 310738 .1T46mAOD040B RB REFUEL LEVEL EXHAUST CENTF.RLINE m319-01 070 HIff POWERS REGUL 1E H-18 32046-6 mEQ ALL 319 RBS 00150 A 310738 l
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IT48:H2Z115A REPCRT ttJ. PES-800 JCB 1160002 01/18/82 Etr/IR0tefENTAL QUALIFICATION STATUS REPORT REPORT tiO. PES-800 STCNE Ato HEBSTER ENGINEERING CORPORATION JCB tlUHEER 1160002 PROJECT EQUIPitENT SYSTEH - (IS-129 ) REPORT DATE 01/18/82 PAGE 29 JOB NAltE SHOREHAH - L74IT 1 Err /IRotittENTAL QUALIFICATION STATUS REPORT RESET tiO. 003 JOB CLIENT LILCO SORTED BY - HAM / HOD / SPEC RESET DATE 07/01/81 EQUIPt!Et4T ID EQUIP! ENT DESCRIPTION HARE / HANUFACTURER EQ SHEET VEf0CR ID OP TIME ACC / PERF ifU-CAT VENDOR NAttE QAC ZONE HODEL / CATALOG tic QUAL STAT ENG Cie PO NUI'EER SPEC BLDG ELEV SUBt1G OP CD commen===**mamum maman***m*mmmmmmmmmmmmmmmmmm** mamm* man *==* *munnemummmm** mens ** ********me ***menas mammmmmm** **** REPORT GROUP HAM = CCitOIP INC
.1748*H2Zll5A DRYNELL HYDROGEN ANALYZER CCHSIP INC m344-01 180 DYS m2%FS AE/1 DELPHI It00ST IE J-15 B *EQ L 310737 344 RBS 00112 A .lT48*H22115D DRYHELL HYDROGEN ANALYZER CCHSIP INC m344-01 180 DYS m2%FS AE/l DELPHI It0UST 1E J-16 B *EQ L 310737 344 RBS 00112 A .lT48mH2Zll6A SUPP CHBR/RECOH DISCH ANALYZER CCHSIP INC *344-01 163 DYS m2%FS AE/1 DELFHI ItCUST 1E J -15 8 mEQ L 310737 344 RBS 00112 A .lT48mH2Zll6B SUPP CHBR/ REC 0ft DISCH ANALYZER COHSIP INC *344-01 180 DYS m2%FS AE DELPHI It0UST 1E J-16 B *EQ L 310737 344 RBS 00112 A .1748*02Z123A PRIttARY CONT OXYGEN CCHSIP INC *3 M-01 180 DYS m2%FS DELPHI It0UST. IE J-16 J mEQ L 310737 344 RBS 00112 A .1T48m02Z123B PRIttARY CONT OXYGEN COffSIP INC m344-01 180 DYS *2%FS DELPHI INDUST. 1E J-15 J mEQ L 310737 344 RBS 00112 A .lT48mPtL68A GAS AffALYZER DRYHELL *COttSIP INC m344-01 180 DYS N/A mRG DELPHI ItOUST. IE J-15 H-IV *EQ L 310737 344 RBS 112 A SAttPLE PUtP BEARItGS REQUIRE REPLACEMENT.SAttPLE PU!!P IS BEING RETESTED. ALL OTHER CO!!PONENTS ARE EQ. .lT48mPFL688 GAS ANALYZER DRYHELL *C0ftSIP INC *344-01 180 DYS N/A mRG DELPHI It10UST. IE J-16 H-IV *EQ L
~ 310737 344 RBS 112 A SAtfPLE PUttP BEARIt4GS REQUIRE REPLACEMENT. SAMPLE PUttP IS BEING RETESTED. ALL OTHER CCHPONENTS ARE EQ.
.lT48*PtL69A GAS ANALYZER SUPPR CHA!!3ER aCOMSIP ItiC m344-01 180 DYS N/A mRG DELPHI It0UST. IE J-15 H-IV mEQ L 310737 344 PBS 112 A SAMPLE PUllP BEARINGS REQUIRE REPLACEHENT. SAMPLE PUip IS BEING RETESTED.ALL OTHER CottPONENTS ARE EQ.
_ .lT48*PtL698 GAS ANALYZER SUPPR CHAffBER *CollSIP INC m344-01 180 DYS N/A mRG DELPitI It0UST. IE J-16 H-IV *EQ L 310737 344 RBS 112 A SAttPLE PUt!P BEARIttGS REQUIRE REPLACEMENT. sat 1PLE PiftP IS BEIttG RETESTED. ALL OTHER C0!!PONENTS ARE EQ. O O}}