ML19250G929
| ML19250G929 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/30/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19250G930 | List: |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 IEB-79-016, IEB-79-16, NUDOCS 8106090319 | |
| Download: ML19250G929 (420) | |
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,y s APPENDIX M <, p ENVIRONMENTAL QUALIFICATION OF ELECTRICAL E05 1. SIT 4:rqo TABLE OF CONTENTS NM C -Q PAGE M.1 INTRODUCTION M.1-1 M.2 QUALIFICATION EVALUATION M.2-1 M.2.1 Environmental Qualification Procedure-Balance-of-Plant Electrical Equipment M.2-1 M.2.1.1 Original Electrical Equipment Environmental Qualification Procedures M.2-1 M.2.1.2 Original Evaluation of Electrical Equipment Per DOR Guicelines M.2-1 M.2.1.3 Reevaluation of Equipment Per NUREG-0588 M.2-2 M.2.2 Environmental Qualification Procedure - Nuclear Steam Supply System Electrical Equipment M.2-2
. M. 3 SAFETY SYSTEMS AND COMPONENTS M.3-1 H.3.1 BOP Equipment - Table M. 3 -l M.3-1 M.3.2 NSSS Equipment - Table M.3-2 M.3-3 M.3.2.1 Equipment Categories - Func tional Tercs M.3-5 M.3.2.2 Location of NSSS Equipment M.3-6 M.3.2.3 Correlation of Safety Categories, Functional Times, and Environmental Zones Among the NSSS and 30P Equipment M.3-6 M.4 PLANT ENVIRONMENTAL ZONES M.4-1 M.4.1 Harsh Environment (LOCA/HELB) -
BOP Equipment M.4-1 M.4.1.1 Selection of Bounding Conditions M.4-2 M.4.1.2 Service Conditions M.4-5 M.4.2 Harsh Environment (LOCA/HELB) - NSSS Equipment P.4-6 M.4.3 Normal Equipment (Non-Safety-Related HVAC Systens) - BOP Equipment M.4-7 M.4.4 Normal Environment (Non-Safety-Related HVAC Systens) - USSS Equip:nent M.4-8 M.4.5 Controlled Environment (Redundant HVAC Systems) - BOP Equipment M.4-8 M.4.6 Cont:cIled Environment (Redundant HiAC Systems) - NSSS Equipment M.4-9
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.E 3 0 6 0'9 0 THIS DOCUMENT CONTMNS
, P0OR QUAUTY PAGES
LSCS-FSAR AMENDMENT 57 JUNE 1981 TABLE OF CONTENTS (Cont'd) PAGE M.5 OUALIFICATION METHdDS AND
SUMMARY
STATEMENTS M.5-1 M.5.1 Equipment Specification Conditions M.5-1 M.5.2 Equipment Qualification Conditions M.5-2 M.5.3 Environmentally Sensitive Component Analysis - NSSS Equipment M.5-2 M.5.3.1 Transistor and PN Junctions M.5-2 M.5,1.2 Resistor Thermal Degradation M.5-3 M.5.3.3 Ceramic Capacitors M.5-4 M.5.3.4 Bellows Failure M.5-5 M.5.3.5 E- lows Hardening M.5-5 M.5.3.6 Re; tive Element M.5-5 M.5.3.7 Ins- ation M.5-5 M.5.3.8 Microswitch M,5-6 M.5.3.9 Spri.ng M.5-8 M.5.3.10 Lubricants M.5-8 M.5.3.ll Rubberized Cloth Diaphragm M.5-9 M.5.3.12 Rectifier M.5-9 M.5.3.13 Electrolytic Capacitors M.5-10 M.5.3.14 Winding Insulation M.5-10 M.5.3.15 Coil Potting Compouns.s M.5-ll M.S.3.16 Contact Insulation Block M.5-12 M.5.3.17.A Buna Seals M.5-13 M.5.3.17.B Butadiene Rubber < M.5-13 M.5.3.17.C Nitrile Rubber (Buna A) M.5-14 M.5.3.18 Meters , M.5.14 M.5.3-19 Clock Motor Driven Timer M.5-lf M.5.3.20 Wire Insulation M.5-15 M.5.3.21 Epoxies M.5-16 M.5.3.22 Polyamides M.5-16 M.5.3 23 Teflon TFE & FER M.5-17 M.5.3.24 PVC M.5-17 M.5.3.25 Temperature Sensor. M.5-18 M.5.3.26 Pressure Sensor Diaphragm M.5-18 M.5.4 Qualification Summary Results M.5-19 M.S.4.1 Harsh Environment Tables ;?.5-19 M.5.4.2 Normal Environment Tables M.5-23 M.5.4.3 Contrclled Environment Tables M.5-24 M 5.5 References M.5 30 M.5 COMPARISON WITM NUREG-0588 M.6-1
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M.6.1 Type Testing Qualification Reports M.6-1 M.6.2 Operating History Qualification Reports M.6-4 , M.6.3 Analysis Qualification Reports M.6-5
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i 1 j" ~ LSCS-FSAR AMENDMENT 57 JUNE 1981 a TABLE OF CONTENTS (Cont'd) i l
, PAGE 1 M.7 CONCLUSIONS M.7-1 \
M.7.1 Harsh Environment Qualification Results M.7-1
, M.7.1.1 BOP Equipment M.7-2 i M.7.1.2 NSSS Equipment M.7-3 4 ! M.8 REQUALIFICATION PROGRAM M.8-1 i
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LSCS-FSAR AMENDMENT 57 JUNE 1981 LIST OF TABLES (Cont'd) NUMBER TITLE PAGE M.4-14 BOP - Normal Environment Zone T2 M.4-28 M.4-15 BOP - Controlled Environment "one 'l M.4-30 M.4-16 BOP - Controlled Environment Zone L2 M.4-31 M.4.17 BOP - Controlled Environment Zone C3 M.4-32 M.4-18 BOP - Controlled Environment Zone C4 M.4-34 M.5-1 Harsh Environment - BOP Equipment Qualification M.5-1.1 M.5-2 Ilarsh Environment - NSSS Equipment Qual'lication M.5-2.1 M.5-3 Normal Environment - BOP Equi *wo"*. Cualification M.5-3.1 M.5-4 Iorcial Environment - NSSS Equ'.pment Qualifica tion M.5-4.1 M.5-5 Controlled Environment - BOP Equipment Ouelification M.5-5.1 M.5-6 Controlled Environment - NSSS Equipment Qualification M.5-6.1 O tb M iv
LSCS-FSA't AMENDMEN.' 57 JUNE 198J t APPENDIX M ENVIRONMENTAL OUALIFICATION OF ELECTRICAL EOUIPMENT LIST OF FIGURES NUMBER TITLE H.4-1 BOP - Harsh Environment Zones M.4-2 Primary Containment Zones for NSSS Equipment Qualification H.4-3 Normal and Controlled Enviornment Zones T O P H-v e
LSCS-FSAR AMENDMENT 57 JUNE 1981 APPENDIX M ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT H.1 INTRODUCTION The La Salle County Station (LSCS), owned by the Commonwealth Edison Company, was awarded a construction permit by the Atomic Energy Commission (AEC) in September 1973. The construction permit was issued based upon AEC and the Advisory Committee on Reactor Safety (ACRS) acceptance of the compliance and referenced criteria information provided in the Preliminary Safety Analysis Report (PSAR). The Commonwealth Edison Company provided assurances, documented in the PSIR, that the LSCS would be conctructed pursuant to Regulations (General Design Criteria) and NRC accepted and/or endorsed industry standards. Regulatory Guide 1.89 was issued in November 1974 to establish a method whereby a design verification for Class lE equipment was to be made against IEEE 323-1971 and IEEE 344-1971. These were the NRC accepted industry standards applicable to La Salle during Jhe period when the Class lE equipment was purchased.
.The FSAR was submitted in August 1975 in the format of Regulatory Guide 1.70, Revision 2 to enable the NRC to make a review in the context of their evolving Regulatory Guides and internal standardized review plans. At that point in time, the environmental qualification of safety-related equipment was routinely specified with purchase orders and functional performance specifications.
During the period 1976 through 1978, the applicant worked with the staff to refine the seismic (and hydrodynamic load) qualification of safety-related equipment separately from other aspects of '.nvironmental qualification. That seismic evaluation, seismic qualification, and seismic requalification program proceeded separately from the consideration of thermal, radiation, aging, and humidity factors to assure that structural and pressure environments were fully met during a period when emphasis was primarily directed toward containment adequacy. During 1979 and 1980 these Seismic Qualification Summaries and Reports were and still are being reviewed by the staff. Concurrently with the closure phases of the seismic analification effort, the NRC definition of Environmental Qualification requirements became more explicit via issuance of IE Bulletin
- 79-OlB to operating stations. An Environmental Qualification program fcr La Salle was therefore defined after the pattern of the SORT effort. The Environmental Qualification program for La Salle enecmpasses three phases: a) the assessment phase which defined , the equipment and environmental conditions which must be considered; b) the evaluation phase which appraised the actual e) qualification basis for the equipment against the NRC criteria , (DOR Guidelines initially, and subsequent re-evaluation against H.1-1
LSCS-FSAR AMENDMENT 57 JUNE 1981 the NUREG-0588 criteria); and c) the requalification phase which includes reanalyses, retest, or replacement of equipment that does not adequately qualify per the original NRC criteria. Assessment Phase The assessment phase included the definition of which equiprent was important to safety in terms of the function of the device (s) during accidents and operational transients. For those instances where the same device (a pressure switch, for example) was used in several systems throughout the plant, the most demanding safety function and the most harsh environment were accepted as the con-ditions to which the particular device was assessed. Other uses of that same device, including uses in other subsyste.s, were also tabulated for completeness to assist in the appraisal of all safety equipment, whether in the harch environment or a more benign environment. Each piece of equipment which was important to safety was identified specifically by manufacturer, model number and unique part number. Additionally, for active safety equipment the functional time-frame for its safety funotion was noted. For passive safety equipment which generally provides containment boundary integrity or pressure boundary integrity, the functional time was not a dominant requirement but considerations were given to potential failure mechanisms in its appraisal. The appraisal extended beyond safety equipment and safety-related equipment. For case of compilation,- equipment numbers follow the NSSS master parts list and master equipment list for BOP; these are subgrouped by system categories. Separate equipment lists were originated for the NSSS equipment and for the BOP equipment to enable parallel efforts in an attempt to meet the NRC milestone dates. These separate equipment lists with separate equipment numbering schemes are in common use for La Salle. The output of this first phase of effort was essentially two compilations or Environmental Qualification Lists, Tables M.3-1 and M.3-2 of this repcrt, and two sets of Environmental Qualifi-caticn Summaries, Tables M.5-1 and M.5-2 of the first issue of Appendix M which was submitted to NRC in November 1980. Equipment qualification records were searched and Environment Qualification Summaries were compiled to serve as a precis of the qualification records and operational experience. These Environmental Qualifi-cation Summaries were backed up by the EQ folders temporarily kept at the offices of the Architect Engineer (Sargent & Lundy) and at GE (San Jose) . Later permanent filing is planned at the station. The Environmental Qualification (EO) folders include the test reports, analyses, and other design documentation that substantiate the conclusion stated in the EQ Summaries. The initial assessment with DOR Guidelines as standards utilized engineering judgments and design records files wnerein the appli-cable environmental specifications in the purchase ordere were M.1-2
LSCS-FSAR AMENDMENT 57 June 1981 the governing articles as pertained to equipment qualificatien for the general plant specifications. That initial assessment used subsets of the plant environmental specification for various areas of the plant; however, the requirements were intentionally generic and ofttimes ultra-conservative. The second assessment with NUREG-0588 Category II Guidelines, based on ISEE 323-1971 as augmented by NRC makes more explicit references to documentation. In this follow-on appraisal the definition of plant environments for particular zones is unique to La Sa?.le. These environmental zones are explicitly defined in Section M.4 for the Harsh Environments, Normal Environments, and Controlled Environments. The earlier versions of Appendix M were reworked into this NUREG-0588 Category II revision following the February 1981 refusal of the Commission to review the DOR Guideline submittal and the decision to require La Salle to meet the NUREG-C388 Category II s+.ndard. Evaluation Phase The evaluation phase included detailed appraisals of equipment capability to perform the safety function in the abnormal environ-ment a-sociated with a LOCA or HELB inside and outside containment.
'Such events are assumed to occur once during the lifetime of the plant. High energy lines are those lines which normally process fluid at pressures above 200 psi and temperatures above 275 F.
Examples include reactor system steamlines, feedwater piping and recirculating system piping. In 9 . D M.1-2a
LSCS-FSAR AMENDMENT 57 JUNE 1981 the unlikely event of such an oC~Jrrence, plant protection systems are designed to automatically initiate to shut down the reactor. The Nuclear System is depressurized and placed in the cold shutdown mode by manual initiation of the shutdown cooling mode of the Residual Heat Removal System. The environments associated with the postulated abnormal events have a time-presistence dependent upon time to detect, to transmit, and to initiate isolation action which closes off the source of fluid being released. Approximately 6 seconds are required to affect an isolation of a breached high energy line. This time approximation characterizes the interval of the break which sets the quantity of radioactaive fluid leaked into the containment. Because flow attenuation begins as the valve begins to close (approximately 600 millisecor;ds af ter detection), the assumption of full flow until isolation valve closure is conservative. The environmental test standard outlined in the DDR guidelines as provided by IE Bulletin 79-01B ensumed that the entire containment volume instantaneously fills with steam at rated containment pressure. That ultra-conservative assumption overestimates the ambi- ' temperature in the vicinity of safety-related equipment loca. inside primary containment by 1000F to 2000F because condens, .on effects of the containment surface and equipment surfaces should reduce the heat transfer rate during the expansion process. Dutung the transition where the equipment surface temperature increases beyond the condensation temperature at constant containment pressure, evaporation efforts would also reduce the rate of heat transfer. This condition accompanied by the gradual ambient heat reduction of the containment results in calculated equipment temperatures well below 3000F. The environmental zones used for the NUREG-0588 evaluations were defined from the LOCA analyses, the HELB analyses, and MELB analyses included in the PSAR. The specific delineation of con-ditions for each zone is discussed in Section M.4. Again, because concurrent BOP and NSSS evaluations were made, it became necessary to cross-correlate the designations of environmental zones. This correlation is shown in Section M.3.2.3 for harsh, non-harsh, and controlled environmental zones. In the reevaluation to NUREG-0588 standards, the La Salle specific environments are utilized to the maximum extent. In some situations, recourse was made to the BWR generic specification for La Salle (GE No. 22A3008 Rev.5) for certain NSSS equipments where La Salle specific definitions were not available. The environments are cited in the EQ Summaries for each type of equipment as a procurement reference because that basis is already reported in FSAR Tables 3.11-1 through 3.11-6 as a documented basis. The designation of equipment locations for NSSS equipment at LSCS took the approach that segmented the primary containment into M.1-3
LSLS-FSAR MIEN 1 MENT 57 JUNE 1981
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subzones as was done in the GE basis ior Environmentaa ll) Specificatior. 22A3008. Similarly, for BOP equipment wilere the emphasis is en the ECCS equipment, control systems, anc power sources, the 3ocation designations were made compatible with the design approach uncad on plant systems d2visionalization (HPCS Division III, for excmple). This divisionalization of systems with accompanying physical and electrical separation of equipment, cablino, controls, power, etc., results in less complexity in considering postulated failures because the M.1-3a
LSC'S-FSAR AMENDMENT 57 JUNE 1981 environment controlling equipment-(coolers, fans, etc.) are in . (llh the same division. Equipment qualification status acknowledges the location within these cubicles having dual redundant environmental apparatus. , The final evaluation step compared the environmental qualification summaries against the NRC's acceptance criteria promulgated by NUREG-0588. This evaluation step employed Criteria Check Sheets to record the judgment basis for the conclusion entered on the EO Summaries. Section M.6 discusses the engineering review performed in this evaluation step. Requalification Phase The requalification scope became apparent from the evaluation phase. The general approach has been to sequentially define test plans for a group of non-qualified equipments, then release such equipment for environmental testing in sequential test rounds. For example, the following items of equipment are included in the first test round for La Salle: Electric Heater CVI Model Radiation Detector General Atomics /RD-23 Switch Gear Gould/ITE/7.5HK-500
, Limit Switch GPE Controls /LICON 65-430140 Relay -
Love Controls /56-91115 glll Penetration Amphenol/varje Power Supply Cabinet Systems Cont: il A detailed test plan is being written for each of the above items of equipment. That plan includes test procedures, test data formatting, test conditions 'and sequences, etc., to meet NUREG-0588 ategory I for those items which need a full test plan to claim qualified status, en some tems where only one parameter was not fully tested, seg.nented testing is designed to fulfill the full test objective and thus qualify the item to NUREG-0588 Categoty II standards. Teet plans are grouped into similar baskets of like items for maximum use of test facilities and conservation of test schedules. A four-round set of tests are projected for the current qualifi-cation effort. - The schedule for the requalification program is outlined in Section M.8.
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LSCS-FSAR AMENDMENT 57 JUNE 19 . M.2 OUALIFICATION EVALUATION M.2.1 Environmental Oualification Procedure - Balance-of-Plant Electrical Eaulpment M.2.1.1 Oriainal Electrical Eauioment Environmental pualification Procedures Original environmental qualifications for electrical equipment were specified in appropriate project specifications. These specifications were prepared in accordance with applicable Sargent & Lundy Quality Assurance Procedures in effect at the time of the preparation of the specification. They specified the applicable environmenta' qualification and documentation requirements in accordar e with industry standards in effect.at the time of contract award for this equipment. Environmental qualification envelopes were determined utilizing the General Electric Company Generic Environmental Specification (22A3008), general calculated environmental conditions defined by Sargent & Lundy analysis in accordance with the Quality Assurance Procedures in effect at the time of the work. Upon receipt of equipment, or shortly thereafter as vendors provide it, the environmental qualification documentation was reviewed in accordance with Ouality Assurance Procedure in effect at the time of the receipt of the documentation. lh Current Sargent & Lundy General Quality Assurance Procedures that are applicable to establishing environmental qualification requirements, specifying environmental requirements, and reviewing environmental qualification documentation are as follows:
- a. GO-3.08 Design Calculations
- b. GO-3.09 ,
Foreign Design Documents
- c. GO-4.01 Procurement Specifications M.2.1.2 Original Evaluation of Electrical Equipment Per DOR Guidelines Equipment requiring environmental qualification documentation and the current status of review and approval of environmental qualification documentation for BOP equipment are included as part of this appendix to the LSCS-FSAR. All the work contained in this appendix has been performed in accordance with Sargent &
Lundy Ouality Assurance Procedure GO-3.05 entitled " Safety Analysis Reports (PS'.d's and FSAR's)." Qualification envelopes included in this appendix are based on approved manufacturers' inform cion particularly from the NSSS supplier, General Electrie Company, and/or calcular. ions performed at Sargent & Lundy in
@ accordance with Sargent & Lundy General Quality Assurance Procedure GO-3.08 entitled " Design Calculations." .
M.2-1
LSCS-FSAR AMENDMENT 57 JUNE 1981 M.2.1.3 Reevaluation of Equipment Per NUREG-0588 All environmental qualification documentation documentation for equipment identified on environmental qualification tables included in Section M.5 of this revised Appendix M has been rereviewed against the criteria of the NRC Document NUREG-C 588 entitled
" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," issued December 1979 for comment.
Revipw to these requirements has been documented via appropriate checklists for the requirements of either Category I or II of NUREG- 0 5 t ' 8. The checklists have been completed and documentaticn rereviewed in accordance with a special La Salle County Station Project Instruction PI-LS-29 entitled "Rereview of Environmental Qualification Documentation of Electrical Equipment." The qualifi-cation documentation for which checklists have been completed shall be available for audit initially at the offices of Sargent
& Lundy (Chicago) and later at the La Salle County Station. Section M.6 describes the review which the checklists facilitated.
M.2.2 Environmental Qualification Procedure - Nuclear Steam Supply System Electrical Equipment
- a. Original Appraisal The assessment of the environmental qualification status of NSSS equipment important to safety was initiated in November 1979.
The prior IE Bulletin 79-01B effort was used to outline the review including coverage or scope and the definition of environments applicable for the equipment. In February 1980 the NRC guidance letter established more specific documentation requirements for each item of safety-related equipment. The exclusion of seismic qualifications from this assessment was acknowledged because the SORT program was on-going. The DOR guidelines were accepted as applicable for LSCS based upon thin NRC letter. The guidelines had been circulated as an addendum to IE Bulletin 79-01B during Janaury 1980. The coverage addressed Class 1E electrical equipment and the electrical controls on mechanical equipment. The assessment of the mechanical control components appeared to be reasonable and necessary for assurance of safety function of the mechanical systems which are important to safety. The General Design Criteria relating to environmental qualifications are General Design Criteria 1, 2, 4 and 23. In the design and procurement of La Salle NSSS equipment there criteria were met via utilization of industry standards IE2E 323-1971, "lEEE Trial Use Standard: General Guide for Ounlifying Class 1E Equipment for Nuclear Power Generating Stations" and IEEE 344-1971, "lEEE Recommended Practices for Seismic Oualification of Class IE Equipment for Nuclear Power Generating Stations." These standards provided acceptable methods for design and procurement of Class 1E electrical equipment important ! M.2-2 i
LSCS-PSAR AMENDMENT 57 JUNE 1981 to safety based upon the intended function of that equipment during the time period when the . limiting environmental condition would exist. The abnormal environment was the main focus because normal plant surveillance and maintenance programs are employed to detect failures and/or to replace deficient equipment (out of technical specification limits). M.2-2a
LSCS-FSAR AMENDMENT 57 JUNE 1981
- b. Present Assessment The present EQ ascessment acknowledged these General Criteria and the industry standards. In addition, recognition was given to possible time-aggravation of the limiting environments on Class 1E equipment and appurtenances. The possibility of functional de-gradation resulting from the sequence of exposure to natural events and design basis accidents and transients, as endorsed by NRC's Regulatory Guide 1.89, was also recognized. In this appraisal of NSSS equipment to NUREG-0588 criteria, this factor was acknowledged by focusing on equipment whose materials of construction or operating fluids were questionable or suspected to be sensitive to the time integrals o# radiation or thermal environments. The General Electric Materials Handbook, which is a collection of industry data on the sensitivity thresholds of materials to these two aging factors, and a large no:aber of material publications provided the basis for evaluating the time-capability of that equipment. The Arrhenius aging model is one basis for interpretations of thermal aging phenomenon.
In the physical layout of the LSCS plant equipment, specific attention was given to locate Class lE equipment and appurtenances outside primary containment, to compartmentalize into cubicles the individual ECCS systems, to provide control room environment for control panels, auxiliary equipment panels, cable spreading areas, and primary electrical switchgear. These measures resulted i.. locating components which are sensitive to extreme environmental conditions in areas controlled by redundant safety-related cooling systems. The airconditioning equipment and associated components are also designed to Seismic Category I requirements; the heat sink side of these cooling systems is also seismically designed to the same criteria and meet ASME Section III standards. Emergency power is provided from on-site diesel generators to assure con-tinuity of service upon Jors of o-f-site power. These are single-failure proof designs for these controlled environmental zones where the majority of the control and instrumentation equipment is located, the control rooms and the auxiliary electric equipment rooms. Many sensors, signal cables, solenoid operators for valves and valve actuators are located inside the containment but the system logics, interlocks, controllers, indicators, recorders, annunciators, relays, etc., which comprise the control circuitry are located in the controlled environment areas as much as possible. The LSCS Class IE equipment is not subject to chemical sprays. In addition, all LSCS Class lE equipment is located above the flood elevation (flood protection is discussed in Subsection 3.4.1 of the FSAR). The BWR does not require special chemical treatment of reactor feed flow for reactor control not the pH need to be M.2-3
LSCS-FSAR AMENDMENT 57 JUNE 1981 controlled. BWR water quality is monitored by on-line glll conductivity elements that indicate when water quality improvements are required needed to restore the conductivity to an acceptable level.
- During this latter assessment phase, recognition was given to the
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fact that no specific accelerated aging method is applicable for
- all C&I equipments. The accumulation of an experimental data
- base for Class lE devices required considerable time to authen-ticate, therefore, only minimal recourse was made to BWR operational experience as a qualification method. Reference is made in the EO Summary Tables to experience with identical or generically equivalent (materials and function) equipment which has accumulated significant operational exposure to natural aging phenomena in operating BWR plants.
This report acknowledges the on-going upgrading of EO data via analysis and test results from vendors and contemporary qualification programs such as the generic BWR owners' group assessment. It is anticipated that such upgrading will continue. Additionally, this report acknowledges the need for a general analytical effort and a general test program to upgrade the qualification status of specific equipments. The revised EQ list and in the revised EQ summaries were verified under the standard QA program. The assessment of LSCS equipment S. . qualification for the non-harsh or benign environments is also continuing; it is anticipated that the Requalification Plan (Phase three) will be available for discussion with the NRC staff. That requalification plan must necessarily address the availability of test equipment from vendors and the extensive testing load being imposed on available EO test laboratories. Nevertheless, the completion date of June 1982'for LSCS EQ work is incorporated into the first version of this Requalifiation Plan. H.2-4
LSCS-FSAR AMENDMENT 57 JUNE-1981 i M.3 SAFETY SYSTEMS AND COMPONENTS -
- This section provides the identification of all the safety-1 related electrical components utilized in the various systems of the plant. This identification is provided through two lists in
- tabular form, one for the balance-of-plant (BOP) equipment (Table M.3-1) and one for the nuclear steam supply system (MSSS) equipment (Table M.3-2).
2 The tables list all the electrical equipment regardless of their
- environmental zone locations, grouped first by system, then by
- equipment type (name), and then (as far as is possible) by
- manufacturer and model number. Empty entries in the tables imply
- that data directly above are applicable. The information
. presented in these tables is as follows:
- a. Specification Number: Identifies the document where the original environmental conditions for equipment purchase and installation are specified.
- b. Eauipment Number - Name: Provides the specific plant numbers of the equipment (for ease of reference and correlation with other documents and drawings) and the generi name (type) of the equipment.
- c. Equipment Manufacturer: Identifies the manufacturer gll or vendor of the egetpment.
- d. Model Number: Provides the equipment catalog number.
- e. EC = Eauioment Cateaorv: Provides a classification of the equipment according to their required function. -
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- f. E2 = Environmental Zone: Identifies the environment
.in which the equipment is located.
- g. Qualification Table - Item: Provides a referen e to the qualification table and item number (within he table) where the environmental qualification summary data are presented for each equipment.
M.3.1 BOP Eauipment - Table M.3-1
- The listing of all BOP safety-related electrical components
- presented in Table M.3-1 identifies all the equipment which might
- be exposed to adverse environments and which have some safety-
- related function or some protective function that is important to safety.
This list was produced after careful examination of every (ll) component comprising each system (provided in various design documents such as equipment and instrument lists), upon M.3-1
LSCS-FSAR AMENDMENT 57 JUNE 1981 consideration of the postulated events which result in the $ environmental conditions described in Section M.4. This subsection provides some additional clarification for the entries of Table H.3-1.
- a. The equipment have been categorized in Equipment
- Categories (EC) under the following functional scheme:
O f a G H.3-2
13C'S-FSAR AMENDMENT 57 JUNE 1981 CATEGORY FUNCTION I DBA, Active: Must function II DBA, Passive: Must not fail III DBA, No Action: Failure allowed even for passive items IV non-DBA, non-safety-related or safety-related but exist to protect barrier (back-up)
- b. The equipment location is designated as HX, NX, CX for harsh, normal, and controlled environments according to definitions provided in Section M.4.
M.3.2 NSSS Ecuipment - Table M.3-2 The equipment listed in Table M.3-2 has been identified as required to function under postulated LOCA and HELB events both inside and outside of primary containment. This table covers equipment potentially exposed to a Harsh Environment and con-trolled or normal environments. It includes plant protection system components (at device level) which by location are assumed to be exposed to the Harsh Environments and which have some llll safety-related function or some protection function (barrier integrity) that is important to safety. This list of NSSS equipment was derived from a consideration of the above-mentioned postulated events. The LOCA's are treated in Chapt.ers 6.0 and 15.0 of this FSAR. HELB is treated in Section 3.6 and Chapter 15.0 for breaks inside primary containment and in FSAR Appendix C for HELB outside primary containment. This list also identifies the plant equipment that is available
. to mitigate the consequences of these above mentioned abnormal events. It includes the equipment which acts to isolate the affected systems, safely shut down the reactor, ensure containment integrity, provide adequate core heat removal, and preclude release of radioactivity (passive barrier protection).
Included in the list is the equipment location, its safety function whether active (signal provided, action performed) or passive. The specific EO Summary is also ref erenced to indicate
. where in the tables of Section M.5 the summary qualification data can be found.
H.3-3
LSCS-FSAR AMENDMENT 57 JUNE 1981 , The following HELB events were covered in deriving this EO List gh of Equipment for LSCS: Reactor Core Isolation Cooling Steamline Main Steamlines Reactor Recirculation Lines Feedwater Lines
- The following NSSS systems are designed to mitigate LOCA and/or
- HELB events both inside and outside primary containment:
Reactor Protection System (RPS) . Residual Heat Removal System (RHR), including LPCI modes Low Pressure Core Spray System (LPCS) High Pressure Core Spray System (HPCS) Auto Depressurization System (ADS) Primary Containment and Reactor Vessel Isolation Control System (PCICS) Reactor Core Isolation Cooling System (RCIC) The reactor protection system is designed to cause rapid insertion of control rods (SCRAM) to shut down the reactor when specific variables exceed predetermined limits. The residual heat removal (RHR) system has several modes of h operation during and post-LOCA and HELB: g
- a. The low pressure coolant injection (LPCI) mode provides reactor coolant makeup following a LOCA when the reactor system has been depressurized and vessel water level is not restored by the hign pressure core spray system. -
- b. Suppression pool cooling mode is designed to prevent suppression pool temperature from exceeding predetermined limits following a LOCA or HELB.
- c. Reactor shutdown cooling mode is used during a normal reactor shutdown or for long-term cooling after vessel water level has been restored following a LOCA or HELB.
- The low pressure core spray system is designed to provide reactor core spray following a LOCA when the vessel has been
- depressurized and vessel water level has not been restored by the HPCS.
- The high pressure core spray system is designed to provide high pressure reactor vessel core spray for small line breaks which do not depressurize the reactor vessel.
H.3-4
LSCS-FSAR AMENDMENT 57 JUNE 1981 The automatic depressurization system is designed to provide
@ automatic depressurization of the reactor vessel by activating safety / relief valves that vent steam to the suppression pool in the event that the HPCS cannot maintain the reactor water level following a LOCA.
The primary containment and reactor vessel isolation contre 1 system includes the Class IE instrumentations that automatically initiate valve closure providing isolation of the primary containment and/or reactor vessel, and initiation of systems provided to limit the release of radioactive materials. . The reactor core isolation cooling system (RCIC) is designed to maintain or supplement reactor vessel water inventory during normal operation when the reactor vessel'is isolated from either its primary heat sink or its normal coolant flow from the feedwater system. Also during plant shutdown, prior to depressurization, the RCIC system maintains vessel water level. M.3.2.1 Eauipment Cateaories - Functional Times The NSSS equipment has been categorized into Equipment Categories (Column EC of Table M.3-2) according to whether the device performs: 1) an active (A) safety function such as providing or transmitting a signal related to same safety parameter or such as providing control or motive power to actuate a safety valve, turn W on a safety motor, operate a solenoid, etc.; and 2) a passive (P) safety function such as ensure a pressure boundary in an ASME Class I, II, or III system, or retain a position or status of some safety equipment. Active safety devices must function in the abnormal event; passive safety devices must not fail their particular need in the event. Most active safety devices are automatically activated by safety circuitry; however, one is manually activated when time is of no significance in the safety action. That device is listed with an M in the EC column of Table M.3-2. Where device action time is important to the safety function being performed, the pertinent time interval was considered ir, the re-evaluation of the NSSS equipment. These time intervals were coded according to the following scheme. M.3-5
LSCS-TSAR AMENDMENT 57 JLINE 1981 Code , Functional Time (FT) A 0 to 45 see B 0 to 10 min C 0 to I hr D 0 to 6 hr E O to 12 hr F 0 to 24 hr G 0 to 2 dayn H 0 to 30 days 1 0 to 100 uayc J Steady-state (always available) Hote that the qualification summary tables of Section M.5 provide the " operability" requirements for the equipment. This term has been defined by the NRC ctaff to be the time that the equipment is required to operate during and subsequent. to a design basin event consistent with the plant safety analysis. Therefore operability requirement and functional _2mc are terms providing the same information. H.3.2.2 Location of NSSS Enuir> ment Equipment locations throughout the plant are designated by the ncheme represented in the correlation tabulation of Subnection M.3.2.3. The cubconen in the primary containment were created to e distinguish between various radiat.fon levels depending upon ceparation dictance from the reactor and to recognize locations where fluid filled lines are concentrated. The subconen within the reactor building dictinguishes cont. rolled environmental zones or non-controlled zones, by elevation differences with local concentrations of similar equipment., and by the compartmentalization of ECCS cystems. The cubicles for llPCS and RilR equipment are environmentally controlled wi th single-f ailure capable !!VAC systems. The majority of the control and instrumen-tation in concentrated into the controlled environment zone den-ignated CR-1 which includen the control room, the auxiliary elec-tric equipment room, and the cable spreading room, plus some ancillary arean. M.3.2.3 Correlation of Safety Cateoorden, runctional Timen, and S Wfronmental Zones Among the NSSS and'~ BOP 1qu2pment The categorization scheme used ta record the cafety function of the 110P equipment was outlined in NRC's February 4, 1980 quidance letter to OL applicanto. That scheme in shown in Section M.3.1 with Roman numeral designatorn indicating the safety function without reference to time of act. ion or interval of availability. The following matrix indicates the correlation of these safety categorien for LSCS equipment. H.3-6
LSCS-FSAR AMENDMENT 57
. JUNE 1981 BOP Eauipment . NSSS Eauinment NRC Catetory I (must function) GE designation A (or M) . II (must not fail) P III (failure allowed)
IV (protects barrier) P - The following matrix indicates the correlation of the environmental zone designation for LSCS equipment. 2 BOP 2ONE DESCRIPTION NSSS 2ONE DESCRIPTICN H1 Figure M.4-1 RPV (Same as BOP) H2 Figure M.4-1 PCI Figure M.4-2 PC2 Figure M.4-2 PC3 Figure M 4-2 PC4 Figure M.4-2 PCS Figure M.4-2 H3 Figure M.4-1 PC6 (Same as BOP)
- H4 Figure M.4-1 RB-1 Annular region outside
-primary containment Reactor Building at eleva-tion 694' 6" and 673' 4".
RB-2 Standby Liquid Control equipment area RB-8 General floor area of Reactor Building H5 Figure M.4-1 RB-3 RCIC/LPCS Cubicle RB-6 Main steam tunnel RB-7 RWCU equipment areas N1 Figure M.4-3 - N2 Figure M.4-3 - T1 Figure M.4-3 TB1 Turbine Building Area T2 Figure M.4-3 TB2 Turbine Building Area C1 Figure M.4-3 CR1 Control Room, Aux. electric equipment room, and cable spreading areas
~]) C2 Figure M.44-3 -
H.3-7 O
LSdS-FSAR AMENDMENT 57 JUNE 1981 C3 Figure M.4-3 DG1 Diesel generator equipment area C4 Figure M.4-3 RB4 HPCS cubicle RB5 RHR cubicle
. s e
O W H.3-8
TADtt M.3 1 (NviccY'f4?At CunttrtCAttcN LIST 00r _ t t t C t k'IC AL ECUtevlNT QUAT.1FICATION Setc. EculewENT , uaNUFACTUREp EC EZ TABLE (! TEM) NawE uCDE t. P.a.;w9 t g v>vota AUvit!aRv PCvEn SYSTEM 7 . 55M-500 IV C2 M.5-5 (1) J-2543 182apofE rectua voltege Goutd/ITE Swttc5 gene tS2APO2E MM-350 I M.5-5 (2) 942Ar04E t&2AucGE 7.5>M-500 IV H4 M.5-1 (1) 1&2ArOeE Switchgese General Electric AMD-5 1 C2 M.5-5 (3) J-234G 1821Pf9E 982AP2CE . 18 2 A P 21E 1&2AP22E
- I H4 M.5-1 (2) M J-2547 182AP7tE Motoe-Control Miockner-Mootter Series 170 M 3
w l'8 1&2Ar72E Cent 9e C2 M.5-5 (a) *hI t&2Ar73E M h t&2Ar75E H4 M.5-1 (2) M W 182Ar76E 182Ar78E C3 M.5-5 (4) t&2Ar79E C2 162ArROE ' 1& 2 At'8 t E HA M.5-1 (2) t&2APR2E 18 2 A r 8 3fi Electrical Con 8M Cu? ton I H2 M.5-1 (4) J-2552-1 1&P96E Penetretion
- 1Ar97E ,
C.4 f 1Ar99E $ .5 t1 1AP99E A= phenol Custon I H2 M.5-1 (45) h 2Ar90E Electrient w3 Panatrattoo e t1 2Ar97E 03y g 2Ar9PE 2Ar99E ' Ut General Efectric AB-40 !! C1 M.5-5 (44) -J J-2524 142El-Ar039A Electetent Indicetor if.2F I- Ar03"O 1& 2 f I A PO"*2 142F1-APO77 14 21 l A t't r.16 1%2$l-AP122 g r,; t 3 . A s.1 j n a 152EI-Ar12nu
" * = + _ . . . . .
. TA9LE M.3-1 (Cont'd)
SPEC. EOUIPPENT OUALIFICATION NUvcER NUptER NAME MANUFACTURE # kCDEt s EC E_Z, TABLE (ITEM) J-2524 182EL-APC5! Indicating Light Genere1 E l ec '.r i c ET-tG 11 Ct M.5-5 (41) 1&2EL-APO71 182il-APO78 1&2EL-APO97 1&2EL-AP12; 1&2EL-AP123 d-2524 1&2H5-APQ41 Control switch General E1cetric 50% II C1 M.5-5 (25) '~ 1&2HS-APO42 1&2H5-APO43 1&2H5-APO44 182H5-APO45 , 182HS-APO4G , 182H3-APOS2 142H3-APOGO 18 2HS - A POG 1 1 182H5-ADOG2 182H3-APO77 13 2H3- At'085 16 2fis- APO86 1&2HS-APO87 162HS-APOR8
- 18 2} 45- APO89 ,
w 182H5-APO9( l 182HS-A"O?d V 1b 2H5- AP 1 )?. 1&2HS-APit5 152H5-AP1CG , 182H5-AP122 J-2524 182!!-APO50 Electrical Generet Electetc AB-40 II Ut M.5-5 (44) 18211-APO51 it2II-APO75 182]I-APO7G 18211-APO94 152II-APO95 . 18211-AP120 ' 182!!-AP121 18251-APO38 1%251-AP128 g C' d-2524 1&25t-APO18 Synchrontzing trestinghouse 5-14 II C1 M.5-5 (40) Zt Light M* 1&25L-AP128 g. J-2514 182*S-AP139 Ammet?r Test Switch Westinghouse FT-1 II C1 M.5-5 (35) $ H* 1&2XS-AP140 1 & 2 x ", - A P t .12 1&2RS-AP?OO
% e TABLE M.3-1 (Cont'd) e9 SDEC. EOUIPMENT OUALIF ICATIO'#
NU"3ER NUv3E0 _Naug vaNurACTU*tER PODEL G EZ TABLE (ITEM) 152X5-AP202 NUCLEAD BOILER SYSTEM d-2938-1 1&2B21-FC16 Valve Motor. Limitorese SMB-OOO I H2 M.5-t (34) Cperate-152B21-F019 HSC , 1&2B21-FOG 7A V-2950-1 142B21-FOG 78 162821-FUG7C 182B21-F067D J+2938-1 1& 28 21 - F U65 A SMB-4 M.5-1 (39) 182821-FCGSB d-2937 162821-F032A Solenoid Valve ASCO NP-20G-180-70 I H5C M.5 1 (29) 16 2 B 21 - F O3 2'3 d-2939 1&2821-FO32A Limit Switch NAMCO EA-1BO !! HSC M.5-1 (33) , 182B21-F032B 238736 162B21-Re84A Recorder Westronics D4E I ?- M.5-5 (45)
- EC 182821-R8948 d-2524 182B29-5500 Cont r :1 Swttch General Electric CR2940 I H4 M.5-1 (43) -
~ + REeSIOR DECIRCULATION SYSTEM W d-2937 t&2B33-FO11 Solenoto Valve ASCO HVA-2OG-832-3F I H2 M 5-1 (27) H4 1&2833-FO2O d-2937 182833-FO19 Limit Switch NAMCO EA-180 !! H2 M.5-1 (33) 16;B33-F020 H4 d-2943-1 162831-F338A Solenoid Valve Valcor V526-57EO-2 I H2 M.5-1 (31) 182633-F3388
- H4 t&2833-F333A -
142B33-F339B 15;B33-F3tCA V52G-5760-4 H2 182033-F3JCB g H4 C 162033-F341A 2
*&2033-F3418 1&20 33- F 312 A H2 E'1 1&2831-F3128 18 29 3 3-F 313 A H4 $
162H33 r3138 cc VS26-5760-2 H2 H 152013-F344A 1&;Oa3-r3110 H4 15 203 3- F 34 S A
TABLE M.3-1 (Cont'd) SPEC. EOUIPMENT OUALIFICAT*CN NUVBER NUVBER NAME MANUFACTURER M00: g (C, C EZ TABLE (! TEM) 182033-F345B d-2551-1 '1B33-5301 Electrical Conaw Lostom !! H2 M.5-1 (5) Penetration 1833-53OL d-2551 2B33-5301 Electrical Amphenol Custom I H2 M.5-1 (45) . Penetration 2B33-5302 , CONTROL C00 DRIVE SYSTEM d-2552-1 1C11-5301 Electrical Conax Custom I H2 M.5-1 (4) Penetration 1C11-5302 ~ 1C11-5303 1C11-5304 d-2552 2C11-5301 Electrical Amphenol Custom I H2 M.5-1 (45) Penetratton 2Ci1-5302 ,,. 2C11-5303 * ." 2C11-5304 ta 1 STANDBv LICulD CONTROL SYSTEM H d-2950-1 182C41-FOO1A Valve Motor Lir*toroue SMB-OOO I H4 M.5-1 (34) ^ Operator 182C41-FOO18 d-2950-1 182C41-FOOB Limit Switch NAMCO EA-tBO !! H2 M.5-1 (33) 1&2C41 '031 H4 NEUTRON MCNITORING (TIP) SYSTEM d-2552-1 1C51-%'Of Electrical Conax Custom I H2 M.5-1 (4) Penetration t C 51 - 5 30.7 1C51-5303 1CS1-5304 q.. C* d-2552 2C51-5301 Electrical Amphenol Custom ! H2 M.5-t (45) Lc Penetrat1on t2 2C51 5302 2C51-5303 2C51-5304 $ cu H
TABLE M.3-1 (Cont *d) SDEC. EQUIPMENT CUALIFICATICN vgvg tig wav3ER NAVE MAvJFACTURER MODEt. EC EZ TABLE (ITEU)_ CONTAIN9ENT MONITCQ!NG SYSTEM d-2943-1 182CM017A Solenoid V8lve V81Cor VS2600-5292-5 I H4 F.5-1 (31) v&2C"Ot78 1&2C"Ot8A 182CPOtB8 162CVO19A 142C90t?8 1&2C"O20A 152C"O208 162CUO2'B 162C"O22A
. 182CM02'8 J
- 152C"O24A 1&2C"O25A 15 20'Q 268 1&2CM727 182C9728 1 & 2 C P.*0 2 9 182C"930 1&2CHO31 VS2600-5292-6 ,
1&2CYO32 *M 3 16 2C f?O33 k 162C"O34 y i , hI kJ 238736 152A!9-CM012 Recorder Westronics DdE I C1 M.5-5 (45) M 1&2 AIR-CM018 UI U' 182 AIR-CMO47 > 182 AIR-CMO48 N d-2591 1&2Ef-CMO82 Power Supply kepco PCX72-0.3 I Ct M.5-5 (47) 182EY-CMO83 d-2524 142H3-CMOOt Contro1 Switch General Electric 588 I C1 M.5-5 (25) 14 2:;;- C"CO2
- 182H5-CMOO4 1&2H5-C"OO5 162HS-CMOO8 18 2 H5 - C P'013 1 & 2185 -CM019 15 2515 - C M'320 UU 1&2H5-CMO25 16 2 H',- C Mo2 6 h$
MZ 1&2H5-CM114 CR2940 M.5-5 (36) U 1&2H5-CM115 *M 1 & 2 t '5 - C" 1 16 w t1 S P. 2 f t's C H 1 17 Co '.: H '3 15 Ol I5 - C f.11 18 182HS-CM110 (11
-1
m 6
% e TADLE M.3-1 (Cont'd)
O SPEC. EQUIPMENT NUM0ER NUMBER Nave OUALIFICATION MANUFACTURER MODEL EC EZ TABLE (ITEM) g 182HS-CM120 4 i 1&2H5-CMt21 f d-2530 9P;LT-CMO30 Level Rosemount 1152 I H4 u,5 1 (:$)
! Transmitter 182LT-CMO3' t&2LT-CMO62 d-2591 t&2LY-CMO30 Love Controis 56-8tf5-8174-851 I C1 M.5-5 (32)
J-2524 t&2PI-CMO55 Electrical Generet tiectric 180 t Indicator I C1 M.5-5 (42) i t&2PI-CMO5G 1 238736 182PR-CMO27 Recorder l; t&2PR-CMO28 Westronics 04E I Ci M 5-5 (45) - 7 d-2530 t&2PT-CMO27 Pressure Rosemount 1152 Transmitte" I H4 M.5-1 (12)' t&2PT CMO28 182PT-CMO29 Og 1&2PT-CMO31 * , 182PT-CMO55 LJ 142PT-CMO56
, t&2PT-CMO81 cn . J-2591 t&2PY-CMO55 Cur.ent delay Love Controts 48-8115-8174 !! C1 M.5-5 (33) t&2PY-CMO5G d-2972 1&2RE-CM011 Radiction Get7ral Atonics RD-23 I H2 M.5-1 (40)
Detector t&2RC-CM017 18 2 r. ! T -CMo t t hedtation General Atonics RP-2C Monttor I C1 M.5-5 (52) 1&2RIT-CM017 .
, 238736 1824R-CMOtt Recorder Westeonics S4E t&2RR-CM017 I C1 M.5-5 (45) d-2530 t&2TE-CMO37 Therrocouple Weed Type E4B 1&2TE-CMO38
!! H2 M.5-1 (14) Ca 1A2TE-CM019 E3 1&2TE-CM010 P"2 18 2 T E -C t'05 8 bd 182TE-CMO59 t&2TE-C"OGO y]
t&21E-CM961 P--
TABLE M.3-1 (Ovnt'd) SPEC. ECUIPMENT QUALIFi4ATION NUMBER NLWBER NAME MANUFACTUREtt MOOEL EC EZ tam t (ITEM) d-2530 1&2TE-CuC57A Resistem e Te*D. Weed Git II H2 M.5-1 ( iS ) Detector 182TE-CMO57C 1&2fE-CMO57D 1& 2 f E -CP'057E 1&2iE-CMO57' 18 2 f E - C t.'F G 1&2TE-CPUS7d 1& 2 T E -CP'05 74 1&2iE-C"O57M 18 2 T E - C *'05 7 PJ 142TE-C"O57P
'42fE-CMO57R
.. 18 2 f E -Ct'05 7U 1A21E-CMO579 23373G 162fR-CMO37 Recorder Westronics M11E I C1 M.5-5 (46) 1&2fR-CMO38 d-2591 162TY-CMO57AA Te=perature Love controls 541-8114-8108-8174 I H4 M.5-1 (16)
, Controller . , 152TV-CMO57AB w 1&27Y-CMO57CA i 162TV-CMO57CB M 18 2 7 Y -CP'057 D A q 1827Y-CMO5708 1&2TY-CMJ57EA E 16 2 T Y -C P'05 7 E G '
182TY-C"357FA s 1627Y-CM357r8 1527Y-CMO57GA 162iY-CMOSTGB i P. 2 7 Y -C MO5 7 d A 18 2 T V -CMO5 7s)G . 1527Y-CMO57KA . 182iY-CMO57KB 182YY-C"O57MA 1&27Y-CMO57M8 *
- 16 2 T v - C M'J5 7 PJ A 16 2 T V - CMO5 7PJG U 182TY-CMO57PA h *'*
18 2 f Y -CMO5 7 8'8 1821Y-CMO57PA [fhD 1 & 2 T Y -Ct'05 7 PB H ** 1 A2 T Y-COO 5 704 WM 16 2 f Y -CM')S 7UU
~
18 21 Y - C MG'.s I V A 1 % 21 Y ~ t M:Ys 7 40 t.n s
9 TABLE M.3-1 (Cont'd) SPEC. EQUIPMENT NUveER QUALIFICATION NUvGER NAME MAVJrACTURER MODEL EC EZ TABLE (ITEM) 23873G t&2UR-C*029 Recorder Westronics I Ct 1&20R-CMO31 D4E M.5-5 (45) d-2524 t&2>t-CM122 Indtcating Light General Electric ET-16 I C1 M.5-5 (41) t&2xt-CM123 1&2*L-CM124 t&2XL-CMt25 1&2xt-CM126 162tt-CM127 152xt-CM128 182*L-CMl29 PROCESS RADIATION MONITORING SYSTEM sf-2972 1820t8-N451A Radiation Genere1 Atomtes RD-1
- Detector 1 M.5-5 (39) ..
162018-N4518
- 132018-N45tC
- 182D18-N4510 *
(* located on Aux. Biog. roof)
% 238736 OD18-R800 decorder Westrontes D4E I ODt8-R801 Ct M.5-5 (45) y 00t8-4003 .
t; I g ODt8-R804 cm U-2524 0018-5805 Control Switch Ger.eral Electric SBM I 0018 580G Ct M.5-5 (25) b BATTERY & O!STRIBUTION SYSTEM d-2551 1820CO2E Distributtua Bus System Control Custom I C2 18 2 DCOC '. M.5-5 (5) 1&20C 1 SE d-2551 t&2DCOGL Motor Control System Control Custom I Center H4 M.5-1 (3) J-2551 1820C1fE Distrit tton System control Custom I C2 M.5-5 (G) Panel ys 1&2DC13E c{ 1A2DC39E II [3 D L 162DC40E P; d-2554 1820C01E Dattery Gould FPS-13 I 10"a7E C2 M.5-5 (7) co ; FPS-15 M.5-5 (8) H* i L't)C 14 E F/L-2019 2DCO7E FPS-25 M.5-5 (9) O
TABLE M.0-1 (Cont'd) O OVA 1,IFICATION SPEC. EOUIPMENT T A91.E (ITEn#) NAME M AN'UF ACTU2E R FCDEL EC EZ PJ'JYE E R f?JVSER 1&2DCO3E Battery Charger Power Conversion 350-2G0-50 I C2 M.5-5 (10) d-2555 CDC04E M.5-5 (11) 1DCO3E 350-130-75 1420CtGE DDC17E 35-130-75 M.5-5 (12) F/L-2820 20CO3E DIESEL GENERATDR SYSTEM d-2544 COG 01K Diesel Generator Stewart & Stevenson EMD:20-645-E4 I C3 M.5-5 (15) 182DG01K ODG01P PUFP Motor Re11eNe Horizontal I C3 M.5-5 (17) ., d-2944 DP, NEMA 40STS 182DG01P ODGO15 DG Air Starting Stewart & Stevensen I C3 M.5-5 (1G) d-2544 . Unit 1&2DG015 DG Air Stseting Unit E d-2544 ODGO2dA Control Penet Stewart & Stevenson I CJ M.5-5 (53) . y 182DGO2dA 4 ODGO2dB H t&2DGD2dB
- ODGO3J W 1A2DGO3J Tre.isformer Stewart & Stevenson I C3 M.5-5 (53) 0-2544 CDGO4J Penet 1520GO4J Terninal Bow Stewart & Stevenson ! C3 M.5-5 (53) 0-2544 ODGO5J 1&2DGO5J ODGOGJ ,
162DGOGJ < ODGO7J 1820GO7J J-2939-2 142DGO35 Velve Motor Linttercue SMS-OO
!! H5A M.5-1 (35) hg Doerator M
Electrical General Electric AB-40 II C1 M.5-5 (44) P d-2524 OEl-DGO27A Indicator e OEI-DGO275 m p 182EI-DGO27
Eb e TABLE M.3-1 (Cent'd) e 5"EC. EOUse .NT OVALIFICATION NU'?BER Na)VSER NAME NAYpACTURER MOCEL EC EZ TABLE (ITEw) d-2524 OEL-DGO27A Indicating Light ET-16 OEL-DGO278 General Electric II C1 M.5-5 (41) 18 2 F t.-i GO2 7 d-2524 CH5 DGOO1A CcNtrOf Switch General Electric I Ous.DGOO18 SBM C1 M.5-5 (25) 162H5-DGOO1 OS*5-DG013A O*85-OG013G 142H5 DG013 045-DGO14A OH5-DG0148 162H5-DG014 0"5-DG015A CHS-DG0158 18295-DG015 O"5-DGO27A ' OSIS-DGO278 162H5-DGO27 OH5-DGO37A OH5-DGO379 182H5-DGO37 *
- E
. CH5 -DGO353 A 0" 5-C'GO 38 G 1&2HS-DGO38 y 152H5-DGO53 . t W V-2524 Olt-DG019A Electrical O Gene.67 F%ctric 08-40 II C1 M.5-5 (43) Indicator 011-DG019B 18 2 ! ! - DG019 OJ1 OGO22A OJ I - t, J 72 2 B 1&201-D0022 OJI-DGO24A Od!-DGO240 , t&201-DGO24 d-2524 05!-DGO2RA Elect
- test Geneest Electric AB-40 Indicator
!! C) M.5-5 (44) 05!-DGO2c8 Q C,
1&251-DGO28 Z I'!
- J-2524 Dx5-DCO35A Ammete' Test Switch Westinghouse FT-1 II Cf M.5-5 (35) p-Or5-DGO350 et 1&2x5-DGO35 0) '
- p. .
I
% TABLE M.3-1 (Cont'd)
SDEC. EOUIPMEntf OUAt.!FICATION PU'B E 9 SUvUER NAME MANUFACTURER MOOEL EC EZ TABLE (ITEw) DE 3EL FUEL cit. SYSTEM d-2908 0000tP Pu-p Motor westinghouse SeJfreet Cage F C3 M 5-5 (18) Inductton TEFC. NEMA 184T. CL. H 1820001P , i.* 20CO2P d-2943-1 0000')4 Solenoid Vet e Valcor V526CO-5840-1 I C1 'A.5-5 (19) t&200004 16200014 1&200024 d-25d4 OH3-D0001 Control Switch General Electric CR2940UB203B I C3 M.5-5 (36) - 182HS-DCOO1 162H3-000C7 d-2530 OLS-DOOO3 Level Switch Magnetrol A-tS3-F 1 C3 M.5-5 (34) t&2LS-D0003 g OLS-00004 .
, t&2LS-00004 w 1&2LS-00010 1 152L5-00011 W
g d-2544 OZL-00001 Indicating Light General Electric ET-16 fl C. M.5-5 (41) w 1822L-D0001 1522L-00007 CESIOUAL HEAT REMOVAL SYSTEM d-2944 182E12-COO 3 Pump Motor Reliance Horizontal 1 C4 M.5-5 (17) OP. NFMA 184T 182E12-C3OOA Hertzontet C3 M.5-5 (17) DP NEMA 445T5 1&2E12-C3OOD 182E12-C3 OOC Cd 182E12-C3OOD b d-2939 182E12-FO41A Solenoid velve ASCO NP-20s-380-3F II H2 M.5-1 (30) @; 182E12-FO41B 1&2E12-F04tC P' t F,2 E 12 - r ono A WI t P. 2 012 - f 0500 d 2927 IS/E12-f05tA HVA-20G-832-3F I C4 M.5-5 (58) 18 2 E 12 - F 0510 ,
. TAPLE 4.3-1 (Cont'd)
SPEC. EQUIPvENT CUALIFIC2 TION PPSB ER NUvBER NAME MA$fJFACTURER MODEL EC EZ TABLE (17E i 1&2E12-FOG 5A 182E12-FOG 5B 1&2E12-F327A H2 M.5-1 (27) 1&2E12-F3270 1&2E12-F317C - d-2943-1 182E12-FOGOA Valcer V52 GOO-5292-2 !! C4 M.5-5 (19) 1&2Et2-FOGOB 1&2E12-FO75A 182E12-F0758 1&2E12-F097 V52600-5292-1 0-29?8-1 1&2E12-F020 Limit Switch NAMCO EA-180 II H2 M.5-1 (33) d-2919 182E12-F041A III 1&2E12-F0418 1&2E12-roa1C 1&2E12-F05CA 18 2E t 2 -FO503 - d-2937 1&2E12-F05ta II C4 M.5-5 (57) 152E12-FO51B 15 2E 12 -F OG5 A 1&2E12-FOG 58 , DC d-2938-1 1&2E12-rO90A !! H2 M.5-1 (33) t&2E12-FO908 182E12-F0924
,, 1AiE12-F0928 . f82E12-FO920 (
se d-2937 1&2I12-r327A bJ 1&2E12-F327B ; 1&2E12 '327C d-2938-1 1&2E12-FOO3A Valve Motor Limitorque SMS-1 - 04 M.5-5 23) Operator 142E12-FOO3B 142E12-FO42A H4 M.5 1 (37) 182E12-F0428 - 1&2E12-FO42C ' 1&2E12-F027A C4 M.5-5 (23) 18 2 E 12-F O 178 162E12-FO1RA 1&2E12-FO48B Ca 18 2 E 12-F O2 t SMS-3 C4 M.5-5 (24) C; 1&2E12-F024A ** 1&2E12-F024B c' d-2938-1 162f12-F052A p: 182! 12-FOS 20 V3 ( 1&2E 12 -FO53 A H4 M.5-1 (38) 00 ** h"
- 1&2E 12-F O53G 1&2E12-FOB 7A C4 M.5-5 (24) g
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1 1 1 UA S 5 5 - - - QT MM 5 5 5 $S M M M M MM M MA Z 4 424 4 4 E 4 A C HHH C H C 4 2 4 5 22 C H H H HH C I I E II I r ! 1 !I F F3 3 - A - 2 l i M 03 t sE 80 0 O O tN 3 - 0 O O 7 - G 9 - O O n.4 O G0 B g 2P8 C2
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JUNE 1981 1
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TABLE M.3-1 (Cont'd) i SPEC. EQUIPMENT QUALIFICATION d NU'.*B E R NUV8ER NAME MANUFACTURER MODEL EC FZ T AB1.E (ITEM) 182E32-FC09 i REACTOR CORE ISOLATION COOLING SYSTEM 4 J-2944 182E51-COO 3 Pu o Motor Reliance Hoe 12 ental I H5A M.5-1 (25) DP, NEMA 184T , J -293 F 182E51-FOO4 Solenoid Valve ASCO WPHV-20G-381-3F II H4 M.5-1 (28) 182E51-roc 5 3 1&2E51-F025 3 18 2 E 51 - F 02 G d-2939 182E51-FCGS N"-20G-380-3F II H2 M.5-1 (30)
.. 18 2 E 51 - F Cr.6 J-2937 18 2E 51-F 354 HVA-2OG-832-3F I M.5-1 (27) 1&2E51-F355 d-2937 182E51 FOO4 Limit Switch NAMCO EA-180 11 MSA M.5-1 (33) 162 L 51 F OO5 142E5'-F025 1& 2 E 51-F O26 1 0-2939 182E'1-FOG 5 !! H2 3
i& 2E 31 -FOG 6 y d-2937 182E51-F354 I g 1&2E51-F 355 H d-2938-1 182E51-FOC3 Valve Motor Limitorque S98-1 1 H2 M.5-1 (37) i g Operator I d-2938-2 142E51-FO45 SMS-O H5A M.5-1 (3G) d-2933-1 152E51-FOG 4 H4 182E51-FOOB SMB-OO H5B M.5-1 (35) 182E51-FO13 H4 f d-2938-2 1&2T51-F019 H5A 16 2 E 51 - F O46 d-2938-1 1&2E51-FO59 . 1& 2 E 51 - F OG8 , e d-2938-2 1&2E51-FOG 9 II H4 1&2E51-FOBO I l 162E51-F08G g 4 d-2950-1 182E51-FOtO SYB-OW M.5-1 (34) [ 182E51-FO22 HSA l 1 d-2938-1 182F51-F031 H4 d-2950-1 1&2E5t-rO7G H2 FUEL POOL COOLING & C1.E AN 'Je SYSTEM d-2744 182FCO3PA Pu*p Motor Reliance Horizontal I C3 M.5-5 (17) 1&2FCO3PO DP. NEMA 3G4TS
e TABLE k.,-t (Cont'd) CUALIFICAYION SPEC. EQUIPMENT FANUFACTURER MODEL EC EZ TADLE (ITE*) NUVBER NUVUER NAVE REACTC# WATER CLEAN-Up SYSTEM Valve potee Limitorque SMB-OO 7 H2 M.5-1 (35) d-2938-1 t&2G'3-FOOT HSD 1&2G33-FOO4 Operator HSC t&2G33-F040
- SVB-f H2 M.5-1 (37) d-2930-2 1&2G33-F102 CC"BUSTIBLE GAS CONTROL SYSTEM Hydrogen Atomics Interna- I H4 M.5-1 (26) d-2969 182HGOtA Reccebtner tione!
Unit Valve Motor Limitorque SVB-COO I H4 M.5-1 (34) d-2938-1 1&2HGOO1A Operator 1&2HGOO18 J-293*- 1&2HGOO2A 152HGOO2B d-2'38-1 1&2" GOO 3 t&2H3OO5A 1G2HOOO50 1& 2HriOCG A . . 182HGOCGG ^ 162HGOO3 bI d-2950-1 162HGot8 182H5-HGOO1 Contr51 Switch Generet Electric SSM I C1 M 5-5 (25? , l* '-2524 162H5-HGOO2 y 162H5-HGOO3 m 182H5-HOOO4 INSTRUVENT NITDOGEN SYSTEM 18 21tJOO t A Solenoid valve ASCO HVA-206-832-3F ! H4 M.5-1 (27) d-2937 1&21NOOtB 1821*:317 182tNO74 . 1& 2 ! tJO75 t&2iNO3t Valcor V526-5292-tG M.5-1 (31) d-2943-1 V52 GOO-5890-1 1821N100 y 1& 21tJ 101 C EA-180 H4 M.5-1 (33) Z d-2937 162:NOOiA Lintt Switch NAMCO I M t&2tNOO18 g 1521NO17 e 1&21N774 m 16 21 f1075 H I
9; TABLE M.3-1 (Cont't) e SPEC. EQUIPMENT CUALIFICATION NUMBER NUVBER NAVE PANUFACTUREf1 MODEL EC EZ TABLE (ITEM) d-2524 162HS-INOO3 Control Switch General Electric SBM I C1 M.5-5 (25) 182H3-INOO4 18 21iS - ! NOO5 1&2HS-]NGOG 1 & 2885 - I NOO 7 162H3-INQ16 1&2HS-!Not? , t&2HS-INO34 LOW VOLTAGE AUXILIARY POWER d-2552-1 1LV94E Electrical Conse Custom I H2 M.5-1 (d) Penetration 1LV95E SLV96E , ILV97E 1LV98E 1LV39E d-2552 2LV94E Electrical Amphenot Custom I H2 M.5-1 (45) Penetration 2LV95E *
,E 2LV"GE y 2LV97E t l 2LV9BE P 2LV99E . E P AUXILIARY EL. EQUIPMENT & 'J COWUTCR ROOM PANELS d-2551 182PA13J Auxiliary Relay System Control I C1 M.5-5 (13)
Panet 182PA14d PRIMARY CONT A !P. MENT & VESSEL IsotATION 0-2909.1 162PCOO1A Limit Switch GPE Controls LICONG5-430140 I M2 M.5-1 (32) 182PCOOiB 182PC 162PCOO10 g C. J-2500 1522L-PCOO1A Indicating Light General Electric ET-16 I C1 M.5-5 (41) Zt 1822L-PCC01B M: 1822L-PCOO2A gf 1822L-PCOO2B wg oy ; 1822L-PCOO3A 3 H+ 1622L-PCOO3G 1622L PCOOlA 1622L-PCOO4B ,
, C 2 tlIh t=
- DbE PO[
3 I N O14 I* TE ) ) ) ) ) ) ) ) ) ) ) ) ) AT 8 6 9 3 4 5 0 4 9 7 3 5 6 CI 1 1 1 1 1 1 2 5 4 2 3 2 3 I( ( ( ( ( ( ( ( ( ( ( ( ( ( F IE 1 3 1 3 3 3 1 5 5 1 1 5 5 LL - - - - - - - - - - - - - AB 5 5 5 5 5 5 5 5 5 5 5 5 5 UA CT M 5 M MM M M M M M M M M
.Z 4 2 4 2 2 2 4 2 1 4 4 f E H N H N N N H C C H H C C I I E I 'I I I I I I I I I I 2
L 7 E D D m m R m m m 0 0 O e O o / 0 o o o 8 4 M t G V t 2 8 t t t ? 9 s - I s 5 - s s s - M 2 u D - u D M u u u A C R K B R C R R C C C E S C
)
d
't c n R l s s s s s o E o te c c c l l i
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- n o e y m e i snr a e h
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w E P z oagoc pe y M r n yt B i S S. l o el e CPnt ot un rt M d w N o t y gan aire e gR npn Si ee l E i S l r cl ona n oea ra b t n o T o o t eb RAP lpf eMrP t a r S n t r S n eC t P t Y e i t t d m d w x n S n L o e y a i fe o u o lo f m o E C D H S W M P A C N S T N L C N A I A E P R M P T D I N T U E N O V E E U 790950 R M OO1 2a3 P
C L e ? r# ;tkt'*; (, s J Cby HWO'g N O) a . Im TE ) ) ) ) ) ) ) ) ) ) AT 7 3 5 7 7 8 7 9 9 8 ) CI 2 3 2 2 1 1 1 1 2 2 9 I( ( ( ( ( ( ( ( ( ( ( ( F IE 1 1 5 3 3 3 3 3 3 3 3 LL - - - - - - - - - - - AB 5 5 5 5 5 5 5 5 5 5 5 UA OT M M M M M M M M M M M Z 4 4 1 2 2 2 2 2 2 2 2 E H H C N N N N N N N N C I I E I I I I I I I I I I I F 3 2 S 3 T T 7 T T 8 6 4 6 S 4 0 L - 2 8H 5 0H 0 E 6 5 3 2R 2 4R 4 2 D 0 0 H M O 2 8 .R . .H R m o m o s1 e-M A 1
- M D OL AC C OL
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) d t c n n R i c a o E r i n C R t r r ( U c e t e T e c i C s e T 1 A l E u l
- o E &
3 F J e h e M l c g c l r r o a n n n a e e c M .A O r e a r M O C e i t i o E C M n l t t e r r l I l s l n r r l L S A e V e e e e a a a B A N G C R W A R G C C W T g n e h i r v c t no l l h t a ot e a c i e io l n r E v t w H tM e a o i S r e r a n P U d i S w c o o o r . e ec t N l i t t t t ep P ne o o rl o o o lo M n t r t o M M M igmo r r it re E e i t cC rC e t oO T l m n e n n n f w n S o i o l a a a e o o l h Y S L C E F F R P T S F C C N C E N A M I V P A H I R U O M Q 78 78 O E 33 R OO O 00 O OO R A BA EE O 23 23 FF 0 C1
JUNE 1981 1 2 Da M S'
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TABLE M.3-1 (Cont'd) EQUIPMENT OUALIFICATION 5?EC. EZ TABLE (ITEM) NU'*D E R NUVSER NAVE fAANUFACTURER MOOEL EC OFZ-VCOO7B 0FZ-VCOO7C Or2-VCOO8 OFZ-VCOO3A OT2-VCOO3B OF2-VCOO9C
- Or2-VC010A OFZ-VC01CG O'Z-VC041A Or2-VC041B
~
Or2-VC041C OF2-VC0410 OF Z-VCO s t E OFZ-VC041F OFZ-VCOt7A Or2-VC0478 OF2-VC04TC OFZ-VC048 OF2-VC049A Or2-VC0490 . OFZ-VCO49C Or2-VC050A . OC OFZ-VCOLOG
- OFZ-VC101 .
OFZ-VC102 ps OF2-VC141
. OFZ-VC142 M
FJ d-2524 OHS-VCOO1 Control Switch General Electric SUM ! C1 M.5-5 (25) CHS-VCOO7 Cel5 -VCOOB OH5-VCOO9 O'is - VC010 OH5-VCO33 . CH5-VC041
- ONS-VC047 OH5-VC048 Ot is - VCO 19
- CHS-VCO50 OHS-VCO73 Ca C:
OH5-VC093A OH3-VC0938 2 t1 OH5-VC095A OH5-VC005G OH5-vCtit CR2940 M.5-5 (36) ([ co ohs-Vr:t12 F' 0885 VC151 Ol t% - V C 1 $ 7
t e TABLE M.3-1 (Cont'd) e SPEC. EQUIPMENT NU'?SER NUMBER NA*E OUALIFICATION MANUFACTURER. MODEL EC EZ TABLE (ITEM) d-2524 OKO-VC010 Elasped Time Eagle HK Peter II Cf M.5-5 (51) OKO-VC050 d-2591 OKY-VCOO1 Time Deley' Agastat 7012AD I N2 M.5-3 (7) sietay - OKY-VC011 OKY-VC041 OKY-VC051 d-2524 OPDI-VCu24A Electetcal General 180 Indicator Electetc
!! C1 M.5-5 (42)
OPDI-VCOG4A CPDI-VCITO OPD'-VC'21 OPDI-VC1GO OPDI-VC1G1 J-2524 OPDR-VCO27 Recorder Bailey 732 OPDR-VCOGT II Cl M.5-5 (50) J-2591 OPD5-VCOI1X Control Relay General Electric HFA 51A49 , OPD5-VCO51X I N2 M.5-3 (3)
- 6 t.n)
I d-2591 OPD5-VCOt1 Dtff. Pressure Solon 7P511AO N I WR M.S.3 ( g} '
- Switch OPD5-VC051 N
OPD5-VC095A 3 OPD5-VCO958 d-2591 OPDT-VC120 Flow Transmitter Hays T-OO252A OPDT-VC121 III C1 M 5-5 (31) OPDT-VCtGO OP0f-VCtG1 d-2588 OPS-VC13G Pressure Switch Penn Control P70AA-45 OPS-VC176 I N2 M.5-3 (26) OPS-VCt38 P70CA-42 OPS-VCi?8 OPS-VCt37 P45NCA-tG OPS-VC177 M.5-3 (25) D OP5-VC139 Allen Deadley 836-CG OPS-VC179 M.5-3 (24) h *r M: d-2591 OREY-VCOtoX Control Relay General Electric HMA 11011 OREY-VC050X I N2 M.5-3 (4) "I OREY-VC000XA 'O g . OREY-VCOROVD OWEY-VCOBOxC '
8b 4 TABLC M.3-1 (Cont'd) SPEC. EOUIPMENT OUALIFICATION Pn."rB E R PCv9ER NAVE MANUFACTURER MODEL EC EZ TABLE (ITEM) OREV-VCOBOXD OREY-VCC81XA CREV-VCO81xB OREV-VCO81xC OREY-VCOB1XD d-2591 OTE-VCOO2 Resistance Weed GO1-1-A-3-C- 1 C1 M.5-5 (27) + Te=p. De- 6-2-1 tector OTL VCOO3 OTE-VCOO4 OTE-VCOO5 , OTE-VCOOG OTE-VCO82 OTE-VCO13 - OTE-VCO84 , OTE-VC045 OTE-VC046 d-2524 OTI-VC105 Electrical General Electric 180 II C1 M.5-5 (42) Indicator OTI-VC10G
- f OTI-VC145 OTI-VC146 w
1 . hd d-2591 OTIC-VCOO2 Temperature Love Centrols 54-838-8134- II N2 M.5-3 (5) Controller -8187-81T4 [ OTIC-VCOO3 , OTIC-VCOO4 OTIC-VCOO5 OTIC-VCOOG OTIC-VC042 OfIC-VC943 OT IC-VUnd 4 . OTIC-VLO45 OTIC-VC046 . d-2591 OTS-VCO33X Control Relay General Electric te4A 11011 !!! N2 M.5-3 (4) OTS-VC-73x
- OTS-VC093AX C4 OTS-VCO33AX1 C.
OTS-VC093BX UI
- 015-VC0930X1 H.
V-2588 OTZ-VC132 Temperature Honeywe11 TG54 I N2 M.5-3 (23) u) t Switch Mi OT2-VC'72 W* t
% 1ABLE M.3-1 (Cont'd)
SPEC. EOUIPMENT OUALIFICATION NUvaER NUVBER NAME MANUFACTURER MCCEL EC EZ TABLE (tTEM)_ d-2588 OTS-VC140 Temperature Texas Instruments 20425L86 I N2 M.5-3 (22) Switch Of5-VCiBO J-2591 OTZ-VCOO2 Valve Actuator ITT Gen. Controls Series AH91 I C1 M.5-5 (29) OTZ-VCOO3 OTZ-VCOO4 OTZ-VCOOS OTZ-VCOOG OTZ-VC042 OTZ-VC043 OTZ-VCot3 OTZ-VC044 OTZ-VCO45 OTZ-VC046 J-2591 O*V-VCO8GXA Control Relay General Electric HMA 11811 II N2 M.5-3 (4) Oxv-VCO8Gxs OXY-VCC87XA OxV-VCOB7XB oxy-VCO30XA OXY-VCO88x8
- M LA 3
oxy-VCO80x1A oxy-VC000Xti? 9 oxy-VCO89xA g l M w oxy-VCC8M B to
- oxy-VCO89x1A oxy-VCG89x93 N
oxy-VC125XA oxy-VC12*xB , Ox Y -VC 1'_5 x 1 A oxy-VCi25x18 OXY-Vr,125x2A oxy-VC125x2B OXY-VC175x3A oxy-VC1?5x38 . oxy-VCtG5xA OMY-VC16528 O*Y-VC1G5x1A OYx-VCtG5x18 U oxy-VC165x2A oxy-VCtG5x2B b* OXY-VC16543A , ty oxy-VC165x3B HM 24154 oxy-VC125A oxy-VC1258 Ammonia Detector MDA Scientiffc 70GO:'AN II N2 M.5-3 (30) $yU g oxy-VCtG5A (A OX Y -VC 10 5 ft N
- TABLE M.3-1 (Cont'd)
SDEC. EOUIPMENT OUALIFICATION NU**EER frJVBER NAVE MANUFACTURER MODEL EC E2 TABLE (ITEM) 0-2591 OxV-VCOBGA Iontration Pyrotronics CDA-2 II N2 M.5-3 (10) Detector OXV-VC0968 OtV-VCO87A Oxv-VCO87B OxV-VCO88A OtV-VCO2BB OxV-VCO89A . oxy-VCO893 d-2524 OZL-VCOO7AA Indicating Light Generet Electric ET-16 II C1 M.5-5 (41) OZL-VCOO7AB O2L-VCOO7BA
- OZL-VCOO7GB OZL-VCOO7CA OZL-VCOO7CB OZL-VC047AA OZL-VC047AB OZL-VC047BA 02L-VC047CB OZL-VC047CA U OZL-VC047CB
- N OIL-VC111 g 02L-VC*12 tn g i 3 CZL-VC151 W OZL-VC152 d-2584 OZ5-VC111A Limit Switch NAwCO EA-750 II N2 M.5-3 (21)
OZ5-VC1118 OZ5-VC111C 025-VC1110 OZ5-VC112A OZ5-VC1128 OZ5-VC112C ' O Z 5 - VC 112L'
- OZ5-VC151A -
OZ5-VC151B OZ5-VC151C 025-VC1510 025-VC152A C.4 p 025-VC152B C .:C 025-VC152C M OZ5-VC1520 g HM DIESEt, GENE R A TOR ROOM VENTILATICN wM CO Z J-2505 o' ' 71C Fen Meter Re11ance YEAO. 324T I C3 M.5-5 (49) Hd Insul. CL, RH 1&2V001C 7trC. 102T $
% TABLE M.3-1 (Cont'd) 4 SDEC. EQUIPMENT OUALIFICATION NUvSER NUVBER NAME MANUFACTURER MFDEL EC EZ TABLE (ITEM)
Insul. CL. RH Insul. CL. RH 1&2VDO2C 1&2VDO3C TEAD. 324T Insul. CL. RH 1&2VDO4C TEAC. 182T Insul. CL. RH 1&2VDO5C TEAD. 254T Insul. CL. RH 1&2VDOGC TEFC. 182T Insul, CL. RH 182VD07C TEAO, 254T
, Insul. CL. RH J-2591 OHS-VDOct control Switch General Electric SBM I C3 M.5-5 (25) _
1&2HS-VDOO1 OHS-VDOO2 182HS-VDOO2 162HS-VDOOG 182HS-VDOO7 . 1& 2545 -VD011 i&2HS-VDO12
- 5 182HS-VD016 O
Y d-2591 OTCU-VDOO3 Temperature Love Controls 54-838-8134- I C ".J M.5-5 (28) . I se Controller -8187-8174 M 182TCU-VDOO3 O 162TCU-VD013 d-2591 OTE-vDeu3 Resistance Temp. Weed 601-1-A-3-C- I C3 M.5-5 (27) Detector 6-2-1 152TE-VDOO3 1&2iE-VDOO8 ' 162TE-VDO13 d-2524 OTI-VDOO5A Electrical General Electric 180 II C1 M.5-5 (42) Indicator OfI-VDOO50 1827I-VD010 q C .- V-2591 OTS-VDOO1 Temperature United Electric C302P-103 I C3 M.5-5 (30) Zr
'41tch Mi 1&2TS-VDOO5 162TS-VDOOG $m:
[ . d-2591 01Y-VDOO3 Control Retey General Electric HFA 51A49 I C3 M.5-5 (26) Fs
- 1527Y-VDOO3 152iY-VUOOG {
LSCS-FSI$R AME!!DME! T 57
- JUNE 1981
- 2 On w2 ew at >
U ** a an an a m tw e av aa De N t2 e a b e a c) e a m tu to rw a n ame w w w w ww w w w w w as.
** w sn an f4 to f9 89 e4 n n n
.a : e e a e a e e e e e e in an an an an pg an. 40 - en. an. an. an.
OF E E E EE *- E E E E E O O L D D NI f4 69 O 83 F4 N e4 N N ml U U eeeeeUe Z Z 2 2 Z h 3 Ut 4 tul w _*e se *e ** ** C O V
+*
e T T T w U In u u b e O LL e Os e- > . > e- en * (D I e in J (D .J nn .J > .J CD J e at w OO NO OU ** O v w ED w fJ w 0 4 O > m - - - w F F - C. -
@ ** +- ** X~ O O an E ED -
03 03 03 3 ** ** e L <m em e an e e an s w @ wC wC wC OC 3 3 su en en F ** F ** > ** O ** O U 1 a m V O
- L
** ** U U C & C e -
O w 0 L L U tr p p ** ** w D ~ U U e- 0 - @ @ e U L e e- e 4 ** L sas hs e u. C @ @ n % O C U e L L e I U @ C e GA @ e E- at O e L e - L k @ o- @ L L @ W > > e C L L C
.J O > @ @ e e @
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- L L
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- O ** @ e LU e -- 3 - C -
+* C L 3 ** 1 @ e @
w Cm@ ** L e C L tr 1 OVI U O L e at U@ U e ** @Q L ~ ~ Z Q ** F 0 DI O O
- E 80 Se O E -O L L L Q ** E > O LU @ ** **
E - tr C e- 3 C C
@ e e @ O O O
& > > ns, u L U U V 2 2 w w E E a (L s-*
s= D D f9 EU n at to o < to O < D D O
. TABLE V.3-1 (Cont'd)
SPEC. EQUIPMP t NUveER NUVU E tc NAME OUAl1FICATION MANUFACTURER MOOEL EC EZ TABLE (ITEM) d-2591 OFT-VE027 Flow Transmitter Hays T-CO2524 !! N2 M.5-3 (2) OFT-VEOG7 d-2591 07Y-VE027 Current Relay Love Controls OrY-VE067 48-8115-8174 !!! N2 M.5-3 (6)
- d-2591 OFZ-VEOO7x control Retey General Flectric HFA 41A49 I N2 M.5-3 (3)
OFZ-VEOO9X . OFZ-VE047X OFZ-VE049K J-2591 OFZ-VEOO18 Valve Actuator ITT General Electric Series AH91 I N2 M.5-3 (11) OFZ-VEOO1C OF2-VECOtD OFZ-VECO7A Ort-VrCo7n OFZ-VEOO7C OF2-VECOB O?Z-VE009AA OF2-VE009AH OF2-VEOO7B OF2-VE009C M 3
- Orl-VE032 (h
g OF2-VE04fB O g OF2-VE041C w OF2-VE041D . f ej OF2-VE047A tn N CD OFZ-V!O17B > OF 2- VE 04 7C N OF2-VEOSB OF2-VE049AA OFZ-VEOl9AB Orz-Vroa99-CFZ-VE040C Ort-VEO72 J-2591 OH3-VEOO1 Control Switch General Electric SOM CHS-VEOO2
!! N2 M.5-3 (1)
OH3-VEOO7 OH5-VE008 OH5-VE009 C4 OH3-VE030 $ *fC OMS-VEO41 *N CHS-VE042 OH3-VEO17 pN 6 CH5-VEC48 T l'! ONS-VEO.i? OJ *
- OHS-VE070 Pd U1 4
. TABLE M.3-1 (Cent'd)
SPEC. EOUtrPENT CUALIFICATION ' Y"JVU E R NUvUEQ N)VE PAVJFACTURER PODEL EC EZ TABLE (ITEM) d-2591 Cxv-VEOOt Ttwe Detey Agostet 7012AD I N2 M.5-3 (7) 2elay Cxv-VEOS1 OKY-VE041 Oxv-VE051 d 2591 CPDS-VEOC2 Diff. Pressure Solon 7PDitAD I N2 M.5-3 (8) - St* Itch OrDS-VEOt1 7P511AD CrDS-VE042 OrD5-VE051
- d-2591 OrDS-VE011x Control Retey General Electric HFA 51A49 I N2 M.5-3 (3)
CPDS-VEC5tX 4-2591 OrDT-VEO 8 Flow Transmitter Heys 232A III N2 M.5-3 (2) OrDT-VEC29 OrDT-VE068 OrDf-VEC69 d-2598 Or5-VE105 Pressure Switch Penn Control P70AA-45 I N2 M.5-3 (26) m Cr5-VE145 , t
- Ors-vt107 P70CA-42 CPS-VE147 0 w
I Or%-VE106 P45-NCA-14 M.6-3 (25) H cr5-vE146 t CPS-VE108 Allen Bradley 836-CG M 5-3 (24) w" Or5-VE148 J-2588 OTC-VE101 Teaperature Honeywell T654 I N2 m.5-3 (23) Switch OfC-VE149 d-2591 OTE-VEOO2 Resistence Te=p. Weed 601-1-A-3-C- I C1 M.5 3 (27) Detectee 6-2-1 OYE-VEOO2 OTE-VECC4 OTE-VE042 UTE-VEO43 Ott-Vt044 C., ', C J-2591 OTIC-VEOO2 Temp. Indicating 1.ove Controls 54-838-8134 !! N2 M.5-3 (5) Z! OfIC-VECO3 Controller -8107-8174 U{ p; O?!C-VEC04 et 07IC-VE042 W '- H* OfIC-VE043 OfIC-VEU44
, TABLE M.3-1 (Cont'd)
SPEC. EOUIPMENT QVaLIFICATION NUvDER NUVSEE NAWE MANJFACTUDEp uCDEL EC EZ TABLE (fTtM). J-2588 OTS-VETO? Te-Derature Tewes Ins t rw-en t s 20425 LEG ! N2 M.5-3 (22) Switch OT5-VE149 J-2591 OtS-VE03Ox contrc1 Relay . Gene *ol Electric HMA t '811 !!! N2 M.?-3 (4) OTS-VEO70X J-2531 Of2-VE90'; Ve l ve A c +'sa '.oe ITT General Controls Series AH91 I N2 M.5-3 % tt) OTF-VEOO.4 O T Z - V E O'.' - Oil-VT042 OTZ-VE043 OtZ-VE04/ J-2591 O*Y-VECBGXA Control Rdley Generst Electric HMA 11811 II N2 M.5-3 td) oxy-VEO9GXS O(Y-VECBTXA OX Y -V E '38 7) B . J-2591 oxy-VEO866 Ientraitor. Pyrotronics CDA-2 II N2 M.5-3 (10) Detector Oxy-VEC860 D g Oxy-vEca7A ORV-VECRTB
*$m W I EANOB) GAT TPEATMEvi Sv5fE'4 ]
w v-2940 t&2vcOO' valve Motor Limiterque ses-OOO I Ho M.5-1 (34) y o Cperetar 1&2VGOO3 J-2583 1&2VGOtA Electric Heating CVI - I h: N.5-1 (24) Coil t&2VGoic Fen wtor westinghouse TEFC, 286T I H4 M.5-1 (21) *
, Insut. CL. H t&2VGO2C TEFC. 1827 Insul. CL. H .
C.e N 0-2551 182VG01J Aux 111ery Rett.,r Systens Control I C1 M.5-5 (54) ch Pre 31 % t-j hZ J-2524 1&2EL-VGOtt Indichtfr2 Ger.eral Elect'ic ET-16 11 01 M.5-5 (41) E
- t. %h t $Q ma J-2551 182rc-VGOO3 Fiow Controller L>ve Control) 54-8115- ! H4 M.5-1 (16) HH B1?1-8174 (P
W
% e TAPLE M.3-1 (Cent'd)
-e 58EC. E7JIPMENT COALIFICATIC*4 vJvete NUvaER Nave MAvarACTUnER W EL Et EZ TABLE (ITEM) d-2524 1&2F1-VGOO3 Electaient Ganeral Electric 180 II Ct M.5-5 (42)
Indicator 23873G 1&2FR-VGOO9 Recorder Vastronics D4E I C1 M.5-5 (45) d-2551 182FS-VGOO9 Relay Love Controls 56-8115 I H4 M.5-1 (1?) 9&2FS-VGO3G d-2591 gg2r;-VGOO3 Flow irensmitter Heys T-OO252A H4 M.5-1 (13) 9&2FT-VGOO9 . J-2591 182FZ-vGOO3 Valve Actuator ITT Gen. Controis set les PM91 I H4 M.5-1 (22) d-2524 t&2HS-VGOOt Controt Switch General Electric 584 I C1 M.5-5 (25) t&2w5-VGOO3 152HS-VGO*G 152H5-VG010 182H5-VGOt3 152H5-VGO2G t&2H5-VGO27 Control Switch Cutter-Hemmer 1D250T I C1 M.5-5 (37)
- C 1&2HS-VGO28 Control Switch Generet Electric CR2940 ! C1 M.5-5 (36)
C y d-2524 1MO-VGOOS Elepsed 79*e Meter Eagle FK !! C1 M.5-5 (51) ' s t d-2524 1&2PDR-VG016 Recorder "atley 732 !! C1 M.5-5 (50) d-2524 1&2ZL-vGOO4 Indicating Generet Electric ET-iG II C1 M.5-5 (41) L i g'i t d-2D91 125-VGOO4A Positten Switch Na-co EA-700-50tOO !! H4 M.5-1 (44) SZ5-vGOO4s CCNTAINVENT VENTILATION SYSTEM . i-2939-1 '52VPC53A Va lve n'otor Limitorque SMS -C% I H4 M.5-f (34) Cperator 1&2Vpd533 g 152VPCG3A C. 162VrOG3G Z d-2940 162VP1134 Mi 1&2VP1133 g.,
* & 2 V P t t ,t A wg 1&2VP114B Cu * ,j-2524 t&2H5-VroO1 Control Switch Generet Electeic SBU ! C1 M.5-5 (25) 962H5-VPOO2 h 9
- TABLE M.3-1 (Cont'd)
SPEC. EOUIPMENT QUALIFICATION NUVEER NUv3ER NAME NJ' NUF ACTURER 900EL EC EZ T ABLE (ITE*.1) 1&2H5-VPOO3 t&2HS-VrOO4 , CONTA!NurNT VENT & PURGE SYSTEM d-2940 1&2VUO26 Valve Motor Limitorque SMS-OOO II H4 M.5-1 (34) Operator , 152VOO27 I 182VQO29 1&2VCO30 152VOO31 0-2950-1 t&2VCO32 II e d-2940 1&2VCO34 I d-2950-1 1&lVQO3" II d-2940 1&2VOC3G I 182VCO37 II 1&2VQO38 1&2VQO40 1&2VyO11 152VOO42 I 1&2VCOJ3 d-2950-1 18 2 V'.'04 7 II ,
*T. 1&2VQO48 1&2VQO50 t&2VQO51 p 1&2VQOG8 b d-2524 182H5-VQO21 Control Switch General Electric 5BM I C1 M.5-5 (25) .
M 1 & 2585 -VOO2 2 182H5-VOO23 182H5-VQO24 1&2H5-VQO25 152HS-VQO2G 152HS-VQO27 1T.2H5-VQO20 162H5-VQO29 15 2185 - VQO30 1&2515-VQO31
- 14 2 8 I". - V90 3 2 1 & 26 '5 - VQO 3 3 .
182H3-VQO34 U 1& 2195 - VQO 35 182HS-VQO3G ' M 142H5-VQO37 187H5-V9039 . H 1 A 2t IS -\ 003'3 1&2H5-vuo10 . f 1 & 2 HS - V u( 62 1& 2HS - vv%3 58-1 M.5-3(38)
. addii Yssi '
2 i e O e ^3 ew = a - 4> ~ ~ O ~ ~ e u ** gr .- w rv w so w v w v w Mw w a6
** w an n n n n an s .J e a e e e e 4 c) an an 74 an. an. an. an.
D ei K E 1 E E E N1 =~ N ev e N .- wl u 2 2 2 2 O U e.e ** ad += e.e w we .4 ** O Y *
.J sn .-
w p D ED CD 4 ** t3 @ ED.
. - o- Ep 5 .- n .-
0 F EO to 4 8 t- En et at E e W th 2 f*- 1 Ld n V
** C O O ' g- gr .O -
w e e
.O w L L L L p tr e* ** ** +*
w D D D D D e- @ @ @ @ v e e e e
.- e ad ad ad w e 36 n Q ~ e e e
. E E E G E+ C L L C L L 1 @ @ O O @* @
W C C U - C C
.J @ @ in 0 @ @
an O O 4 en C C 4 6-r D I @ 0*
- . U > L >
J ++ - > e
.- e m
- D 3 > an @ D w C en @E tr C.
1 e V L U e *' at e* e - tu e - ** C 2 e O O *- O 2 O U L r 3 L U*
- so 7 @ & sn ** .- .,2 V O C - & C C M O O - O "D
** >- O nn O U M N 4 2
w .J.
. *- re n E >- ef (3 XX X s 2 m tn @@m
+= w w .r g *r v 7 > .- N w an O O OOO b g .- et n v tn LD 8 m De 0 - N r7 es in to s e th O rw .- rw g in OOe -
cm tr tr a er - N w an
TABLE M. (Cont'd)
$PEC. ECUIPMENT OUAL2FICATION PrJYGER VJVUER NAME PAvJFACTURER MCOEL C
[,C, {,Z, TABLE (ITEM) i d-2591 1822L-VROOtA N2 -
- t & 2 2 '. - VROO t B 4 % 2L-VROO2A 1727L-VCOO28 t&22L-VROtaA 4 1&22L-VCO148
? 1&22L-V4015A 1&22L-VRO150
- d-2584 1822$-VQOOtA I.fmit Switch NAMCO EA-750 I N2 M.5-3 (21) 18225-VROOtB q 15225-VROO2A t&225-VROO2B 1&225-VROt4A 18225-VRO148 1&225-VD015A 15221-VRO15G Sv!TCHGEaa HEAT ret *0 VAL SYSTEM 0-2585 182VyOtC Fan Motor Reliance TEAO, 284T I C2 M.5-5 (48)
Insul. CL. RH *
% 152VXO2C TEFC, 182T
- Insul. CL, RH g
- 182VXO3C H
- 182V404C TEFC, 784T LJ Insut. CL. RH
- % TEFC, 182T t&2VXOSC Insul. CL. RH i 182VxOGC j 1&2VxO7C TEFC, 25GT Insul. CL. FH t&2VXO8C TEFC, 182T Insul. CL. RH d-2591 t&2H5-VXOO4 Controd Switch General Electric 5BM I C2 M.5-5 (25) 1&2H5-VXOOS g t&2H5-VXOOG C 162H5-Vr033 M 1&2H5-vv034 (1 t&2H5-Vt035 152H5-VsO3G 1 & 2 H*. - V X O3 7
'[m w
d-2591 1&2TE-ViOO7 Resistnace Temp. Weed 601-1-A-3-C' I C2 M.5-5 (27) Detector G-2-1 1
. ~ . . . -... . . . . . - .. - - . .
TABLE M.3 * (Cont'd) SPEC. EOUIPMENe OUALIFICATION NUYBER NUVUER Nave yLNUFACTURER VOOEL EC EZ TABLE (ITEM) 142TE-VFOO8 1&2TE-VXOO9 d-2591 182 TIC-VxOO7 Temperature Love Controts 54-838-8134 I C2 M.5-5 (28) Controller -8187-8174 162 TIC-VxOC8 d-2591 1&272-VXOO7A Valve Actuator ITT General Controls Series AH91 ! C2 M.5-5 (29) 1&2TZ-VxOO78 1&2TZ-VXOO8A 1&2TZ-VXOORG 1&27Z-VXOO9A . 1&2TZ-VxOO9G C5CS - EWC5 ., 0-2585 1&2VYOIC Fan Motor Reliance TEAO, 2567 I C4 M.5-5 (49) Insul CL. PH 1&2VYO2C 1&2VYO3C
- TEAO, 284T Insul. CL. RH E5 1&2VYO4C TEAO, 1847 HSA M.5-1 (23) t, Insul. CL. RH I
FJ 1&2VYO5C C3 M.5-5 (49) 182VYOGC LJ 1&2VYO7C U1 d-2591 1&2HS-VYOOi Contro1 Switch General Electric SBM J H4 M 5-1 (41) 152HS-VYOO2 1&2H5-VYOO3
$42H3-VY004 HSA 1&2H3-VYOO3 C3 M.5-5 (25) 162H5-VYOOG d-2591 1&2TE-VYO23 Resistance Temp. Weed 601-1-A-3-C- I C3 M.5-5 (27)
Oetector G-2-1 182TE-VYO2.' C d-259; 1&2 TIC-VYO23 Temp. Indicat- Love Controls 54-8178-8174 I C3 M.5-5 (55) cj ing Controller Z 1&2 TIC-VYO24 M' d-2531 1&2TS-VYOO1 Temperature United Electric C302P-103 I C4 M.5-5 (30) (y Switch 03 1&2TS-VYOO2 Fs 1&2ts-vvool ' 142f5-V)OO4 H5A M.5-1 (42)
.ADLE N 3-1 (Cont'd)
SPEC. EOUlPvENT CVALIFICATIOM NUVUER NUwGFR NAME MANUFACTURER MODEL EC El TABLE (ITEM) 182TVC-VYO23 Temp. Controller Love Controls ",4-836-851 1 C3 M.5-5 (SG) d-2591 1&2TYC-VYO24 -8134-8174 d-2591 fB2TZ-VYO23A Valve Actuator ITT General Controis Series AH91 1 C3 M 5-5 (23) 1&272-VYO230 . 1&2TZ-Vv023C 162f2-VYO24A , 162TZ-Vv024B 1&272-VYO24C DEACTOR BLOG CLOSED COOLING WATE7 SYSTEM .. J-2938-1 1&2WRO29 Valve Motor Limitarque SMB-000 I H4 M.5-1 (34) Osa.:. tor 1&2WQO40 1&2WA179 H2 182WR180 . CABLE 8 CUS DUCT d-2965 - 5-kV Power Cable Kerfte - I HSA M.5-1 (6) , [a 0-29GG - Low Voltage Okonite - I H2 M.5-1 (7) Power & Con- , he trol Cable
$ d-29G7-1 - Instrumentation Cerro/Rockbestos -
I H2 M.5-1 (8) Coble d-29G7-2 - Raychem - M.5-1 (101 0-2967 3 - Samuel Moore - M.5-1 (9) d-2543-2 - Non-Segregated Bus H.K. Porter - I C & C3 M.5-5 tid) , Ouct D C Z M' Fs : W CO ' H t
- _ , . . . - . . ~ _ _ . . . . . . .- . _ . _ . __ __ G E F' Env. Qual. ITLf. Descric119.n C I Zgnit Iable f Mfr. Model f IDf. B13-t191 Dry Tube P M/A RPV M. 5 - 2 (4 t) GE N/S 886D380 B13-0193 Power Range Detector A N/A RPV u, S - % (Zo) GE NA200 lb3C115A
.N/A FC-3 GE N/S 32814%9 B13-D194 PRH Installation liardware P et. 5 (4D B21 0002 Condensing Chaeber P N/A PCI & 3 2,(43) GE N/5 136B2798 B21-D004 Condens ng Chamber i
P N/A FC1 M.r- a (A 3) G P. N/3 136B2798 B21-D006 Condensing Chaeber P N/A PCI M.g 2,(44) GE N/3 136B2798 B21-D007 Condenstrig Chamber P N/A FCI M. S .1, C4 )) GE 4/5 136B2798 B21 D008 Condensing Chamber P N/A PC1 u . 5 2 (.4 5 ) GE st/3 136B2798 B21-D009 Ct.ndensing Chamber P N/A PC1 M 5-2 (4 h GE N/3 136B2798 B21-N004 Temp. Element P N/A PC4 M.5-Z(.25) Fyco N/3 133D9679 B21-N015 Press. Switch A C 781 M. 5 - 4. C r) Barksdale BIT 164C5359 ,,, B21-N020 Pre ss. Switch A A RB2 gg - g /,3) Barkedale BIT 16tC5359 g B21-N023 Press. Switch A A RB2 g3 2 (3) Barksdale BIT 164C5359 iz B21-N024 Level Ind. Switch A A RB2 g 5.2 (S) Barton 288A 159Cb 384 $@ B21-N026 Level Ind. Intr. Switch A C RB2 spe,-g,(.7) Barton 760 159C4383 m 3 N/A BB. Fosemount 1151 163C1560 ,7, B21-N02/ Level Istr. P g , .3 - g ( g B21-NO31 *evel Ind. Switch A I RB2 pt. g - 7, ( g Barton 288A 159C43R% [ $ .d B21-h032 iff. Fress. Intr. P N/A LB8 g, cg . g ( g Rosemount 1151 163C15 0 qg g m 3 B21-NL33 ? low Intr. P N/A RB8 M,5 - L( 5) Rosenount 1151 '63Cino a r- 1 (J B2'-N03% iT1 uw Intr. P N/A RD8 M.5 - Z (s Rosemount 1151 16 % t*60 K @ , yy E 1 B21-N036 Level Ind. Switch A A RB2 01.'5 '2. ( 6)) Yarway 4418C 159C4445 p M B21-NO37 Level Ind. Switch A I RB2 P1. 5 - '.- M Ba r'.on 288A 159C4384 - W W H D21-NO33 Level Ind. Switch A I RB2 4(g - 2. (S) Barton 288A 959C4384 33 E B21-NO39 Fress Switch A C RD2 rr. g . 2. ( 3) Ba rk sd ale BIT 164C5359 C. O B21-N044 f.evel Ind. Intr. Shitch A I RBS M g A. ( ?) Barton 760 159C4383 3 4 B21-N045 fress. Switch A A RD2 /v15 - R (3) Barksdale BIT 164C5359 45 B21-N047 Press. Switch A I RB2 M.s . 2 (4) Static-O-Ring 12N 145C3012 54 B21 N048 ?ress. Switch & I RB2 K 5- 2 (4) Static-0-Bing 12N 145C3012 [ B21 N05! Press. Intr. A A RB2 gg.g (g Bailey 556 163C1292 o d B21-Nn's Facuum Switch A C TB1 g.g.4 Barksdale DIT 163C1855 B21. 060 Press. Switch 1 C RUS e1 5 - Z ((3 Barksdale BIT 16%C5359 B21-N061 B21-R00% Fress. Switch Press. Ind. A P C N/A RD8 RB2 et. p . rj5 . g,- (.) Rg(3) ) Barksdale Robert Shaw BIT 613B 16%C5359 163C1184 h2 gh B21-R005 riff. Fress. Ind. P N/A RB8 M.5- Z (34) Barton 227 163C1181 MZ C B33-N01% riow Intr. A 4 RBB M. 5 - 2. C.30 '; Rosemount 1152 169C8392 [fj B33-N015 Diff. Press. Intr. P N/A BB2 M. 5 - F- (S) Rosemount 1151 163C1560 mu B33 N018 Press Switch A G PBS n. 5 - C (14) Static-0 Ring $N 145C3011 w F3 B33-N023 Teep. Element P N/A FC4 M. 5 - R (4 9 Rosemount N/3 159C4520 B33.N02% F17w Intr. A A RDS M.5 -2. L 4t) Rosemo mt 1152 169C8392 $ B33-NO35 Temp. Element P N/A PC4 M. 5 - 2, (.3 h Cal. Alloy /Pyeo N/S 159C4313 C11-N012 L.evel Inte. A C RBI M.5- 2 C4c Could Inc.,14SD PD3018 163C1973 C11-N013 1.evel Switch A C RBI M.5 -2 (.18 Hagnetrol 751 159Cb 361 C34 N003 Diff. Fress. Intr. P N/A RB8 4. 5 - Z ( 8) Rosemount 1151 163C1560 C34.N004 Diff. Press. Istr. P N/A RU2 g *. . g ( g) Rosenmunt 1151 16 3C1560 C3bNdOS Fress. htr. P N/A RE2 Ba!!ey 556 163C1186 q,5-g (g
-.....-mmm. ..-u.- - _ - - . . . . . - _ . _ - _ . . - -- . . . _ , _ . - - . ._ ._ . . _ -- . . .
E P8 Env. Qual. . 1%1 reserietion R I Inna Table f M.fr. Model f II1 C34-N008 rress. Iste. P. N/A RB2 M.5-R(g) Bailey 556 163C1185 C34-N017 Diff. Prets. Istr. P N/A RB2 e t e; - g (g Statham PD2000 133D9404 C41-N003 Temp. Switch P N/A RB2 g. 5 - 2 (3'7 Weed Instr. 22810 157C4629 C41-N004 Press. Inte. P N/A RB2 H. 5- R (9)) Balley 556 163C1186 C41-N006 Terp. Element P N/A RB2 sq.5-g(3r) Weed Instr. H/3 158B7072 C41-R003 Pre s s. Ind. P N/A BB2 p. g. R (,4q ) Robert Shaw 6138 16301184 C51-J003 Plonge Drywell Pene. P W/A PCI et. 5 - R (4 b ) CE N/3 112C2398 C51-J004 Valve, Guide Tube A N/A PC1 M. S (. ZS) CE N/S 136B1302 C51-J008 Guide Tube & Fittinge P N/A PC1 M.5 -R (d Handy & Harmon, N/3 328I448 , !'ymouth Tube C51-J003 Valve, Check P N/A P01 M. 5 -Z (4T Matheson Co. Inc.N/3 225A5958 C51-K002 Voltage Pre- Amp A A BBS M.5-E (14)) CE N/3 163C1263AA C51 N002 9etector A N/A RPY P1. 5 - Z (4 5) CE N/5 112C3144 C61-N001 Plow Istr. P N/A RB8 Rosemount Y C61-N006 N/A M. 5 - E (s) 1151 163C1560 Press. Istr. P RB8 H. 5 - E Ce c) Rosemount 1151 163C1563 % m Z C71-k002 Press. Switch A A RB2 45- R C4) Static-0-Ring 12N 145C3012 x { C71-k003 Press. Switch A A TB1 q .g. 4 ( f) Barkscala BIT 164C5359 O y C71-N004 Diff. Press. Switch P N/A RB2 M. 5 - R, (q) Barton 288 158B7054 u 4 t,1 PJ D18-N003 D18-N009 Insulated Detector A A RD6 H.5-2b7) CE MAC5 2371731 - Ser.sor, Converter A & RB2 H. 5 - R (a s ) CE N/3 1941927 @ g y D18-N015 Sensor, Converter A A RB2 M . 5 'P, ( 3 3) CE N/3 194I927 *a 3 E12-N004 Temp. Element P N/A RB5 M.,5 - G ( 2 3) Cal. Alloy /Pyeo N/3 15904313 h. E12-N005 Temp. Elemer' P N/A RBS M 5 - c. C 23) Cal. Alloy /Pyco N/3 159C4313 E12-N008 Level Inte. P N/A RBS u. 5- C C Barton 352/368 145C3156 E12-N009 Diff. Press. Ind. Switch A I RB5 M. 5 - G('l'. 47)t ) Barton 288 145C3009 E12-N010 Diff. Press. Switch A I RD5 M.s-G Cm) Barton 289 145C3005 E12-N013 Plow Intr. P N/A RB5 M. S .- c. C ze) Rosemount 1151 16301560 E12-h015 Plow Intr. P I RBS H. 5 - G ( 2 0') Rosemount 1151 16301560 E12-N016 Press. Switch C Static-O-Rins SM/6N E12 N018 Press. Switch A RB5 m. 5 -. 6 ( ) 145C3011 P N/A FB4 et.5-c (t4) Static-0-Rins SN/6N 209A5127 E12-N019 Press. InJ. Switch A c RD5 M. =; - C. . ( e 4 ) Static-o-Ring 5N/6N 145C3011 C.: y E12-N022 Press. Ind. Switch P 4/A RB5 p.a . 5- 6 O c) L0bert Shaw SP-222-R 163C1185 Cp E12-h026 E12-N027 Press. Letr. Teep. Element P 1/A RD% y 5. G t m") Bailey
- g. r2 .i.' ( 23) Cal. Alloy /Pyco N/5 556 162C1186 g:3 P r/t ?BS 159C4313 6 E12 N028 E12-N029 Press. Intr. P :4/A RD; R* 1 (S) Bi
- ley
. 556 16301185 w LI Diff. Press. Switch P N/A RB5 :5-c(ig Barton rets 145C3009 e tg E12-h032 Press. Ind. Switch P N/A RB5 "t s-G Ctc)
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- - ..---n - . _ -.... . . . . - . - . . - ~ . - . - . - ... .. . - . . ~ . . . . . . . -.. ... . E F' rne. Qual. 115L Descrintion E I Icm Table f Mfr. Mortel f IM. E21-N004 Flow Ind. Switch A I RB3 M,5- Z (2.2) Barton 289 145C3008 E21-N005 Pre s s . Ind. Switch P N/A RB3 M.5 -E C23) Robert Shaw S P-222-C 163C1185 E'21-h006 Diff. Press. Switch A I RB3 M ,5 - Z D 1) Barton 288 145C3009 E21-N008 Press. Istr. P N/A RB3 Bailey 556 163C1186 E21-N009 Press. Switch A C RB3 M. M. 55- -G'R, ( S)) ( E4 earksdale P1H 159C4606 E21-B001 Press. Ind. P N/A RB) H. 5 2 ( 49 ) Robert Shaw (13B 163C1184 E21-R002 Press. Ind. P N/A BB) M. 'j - a GM ) Pobert Shaw 613B 163C1184 E22-N001 1.evel S atch A I TB1 s8.5-4 C4 Magnetrol 751 159C4294 E22-N002 Level Switch A I RB1 M 5-R Os Magnetrol 751 159C4294 E22-N003 Press. Switch P N/A BB4 p . 5 -G (,g g,} Robert Shaw SP-222-C 163C1*85 E22-N004 Press. Intr. P N/A RP4 Bailey 556 163C1 d6 E22 N005 Flow Istr. H I rat M.5-G
- u. 3 G (Cao g) Rosemount 1151 145C32 1 E22-N006 Flow Switch A I ftD4 M. 5-G Q 9) Parton 289 145C300t>
E22-!!009 Diff. Press. Ind. Switch P N/A RB4 M. 5- G C er) Barton reb 145c3009 E22-N012 Press. " witch A I RB4 St. g - g ( g ) Static-O-Hing SN/6N ' ICJ3011 E22-N013 Press. Ind. Switch P N/A BB4 k1 5- c. C 1} Barton 288 145C3009 g E22-R001 Press. Ind. P N/A RB4 g.g.G(gy) Robert Shaw 613B 163C1184 cs E22-RU02 Press. Ind. P N/A BB4 m ,5 G ( z2-) Robert Shaw 6139 163C1184 7, E22-P003 P eas. Ind. P N/A Auz Bldg. M. 5-G ( a t) Robert Shaw 6139 163C1184 g E31-N001 E31-NCO2 Temp. Element Teep. Element A A F F RB3,4 RB3,4 A1. 5 -R, (2*l) m.s-Z (.27) Pyco Pyco N/S W/S 145C3224 145C3224 Y h
- E31-N003 Temp. Element A F RB3,4 M. 5-E ( 27) Pyeo N/S 145C3224 M y E31 N004 Temp. Elemet'. A F RB4 /w. 5 - g (2 2.) Pyco N/S 195C3224 2 PJ 3 E31-N005 E31-N00f, Temp. Element Temp. Element A
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W E31 N007 Diff. Press. Ind. L itch A J RB3 H. 5 -E b i) ) Barton Darton PBS 145C3009 o. E31-N006 Diff. Press. Ind. Switch A J ED8 . . 5 - 2, (4 4 ) 288 145C3009 E31-N009 Diff. Press. Ind. Switch A J RBB ,v,. 5 -2 (4 A) Barton 288 145C3009 E31-N010 Diff. Press. Ind. Switch A J RB8 M. 5 * -23 Barton 288 1'l5C3009 E31-fl011 Diff. Press. Ind. Switch A J RD8 M 7- R C4 $)' Barton 288 145C3009 E31-N012 Diff. Press. Ind. Switch A J DG1 ks. 5 -6 (153 Barton 288 145C3009 E31-N013 Diff. Press. Ind. Switch A J BB3 45 -R 4j) Barton 288 145C3009 E31-N015 Flow Intr. A B R92 M.5-E CT) Rosemount 1151 163C1561 E31-N018 Temp. Element A F RB4 g. 3.C- ( 7.2) Pyco sf/S 145C3224 E31-N022 Press. Switch A F RB3 H. 5 - R, ( l 3) Static-0-Ring SN/6N 145C3011 E31-N024 E31-N025* Teep. Element Temp. E.eeent A A F F RB3 BB4 M N .5 5 --;'G ((.2E7)) 2, Pyco Pyco N/S N/S 145C3224 145C3224 hD gy E31 N026 Teep. Element A F RB4 As .5 - G ( 2t) Pyco N/S 145C3224 to n r.3 -N027 Temp. Element A F BB3,4 M.r.R(E7 Pyco N/S 145C3224 O E31-N028 Teep. Ele-ent A F RP6 H.3-R (27 Pyco N/S 145C3224 HN E31-N02? E31-4030 Terp. !!ecent Temp. Element A A F F RB6 RB6 re.s.R C n ) p.5 '2.(17) Pyco Pyco h/S N/S 145C3224 145C3224 [h e -3 E31-NO31 Temp. Ele =ent A F RD6 p. 5 - A (T Pyco N/S 145C W 4 E 31-N'. 35 Flow Ietr. A B BB2 M. 5 - 2. ( 8)I) Rosemount 1151 163c1561 m E31-h036 Flow Imtr. B ELS Rosemount 115' 145C3240 A r.j. e3 - R ( g}
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E F* Env. Qual. C T Zene Table i g Model i _ID # M?L i Description itB65-BP VPr 6115-(1),(2),(3),(4) B21-FC13 Saf1ty Relief Valve A 1 'FC-2 AS R ( d Crosby N/A B21-F022 Isolation Valve A A PC-5 M.5-2 ( 2) NAMCO (limit switch) EA740 RB-6 NMtCO (limit switch) EA740 N/A B21-F028 Isolation Valve A A ft S % C f.) PC-4 Liettorque SMB-2-25 N/A B33-F023 Cate Valve M0 P N/A H. 5 7. (se) N/A N/A PC-4 g. s. 2. C5 c) Limitorque SMD-3-60 B33-FUb7 Cate Valve. MO P 5K6 339xC109A 21A9243CL E12-C002 RitR rump Motor A I HB-5 m.5 -G (45) General Electric
" B-5 5K6347XC59A 21A9143CM E24-C001 LPCS rump tutor ? I H.5-G (4() General Electric 5K6357XC85 21A?222DA E22-C001 ItPCS Fump Motor A I RB-4 M.5-C (.47) General Electric SMB-00-25 N/A E22-LOOL Cate Valve. M0 A I RB-4 p . 5- G L49) Limitorque SM B 2 00 N/A E22-FOO4 Cate Valve, N A I RB-4 p .5-(, C4 9} Limftorque SMH-3-100 N/A E22-t010 Clube Valv M A C RB-4 p . 5.G (re) Limitorque N/A SMB-3-89 E22-1011 Clube '
've. M0 A C RB-4 M 5 -(, (11) 1.imitorque SP,.0-25 N/A 4 E22-1012 Cate L ive, M0 A I NB-4 p,5,,4 cg,,,) 1.imitorque N/A g SMB-2-60 E22-iU15 Cate Valve, M0 A I HB-4 M . 5 7. C 5 A Limitorque g SMB-4-150 N/A E22-t023 Clube Valve, M0 A 1 RB-4 M. 5 - c, Wiq Limitorque 3
RB-4 p.*.;- G C45") General Electric 4 71 518673 21A3581
!!ea t e r M y E32-B001 1 E32-C091 Blower M I
I HB-4 14 5-6 (44) Siemens 2C116 (Modified) 21A3762
'fM 2Cil6 (Modified) 21A3762 f E32-C002 Blower M 1 R B-4 p.g .4 (44) Siemens tr A E RB-3 H.5 2.(Sy Terry CS-2 21A9201 3 E51-C002 Aux. Steam Turbine (RCIC) $
*Functitn Tires (FT). Each piece of essential equipment on the table has been specified to provide its active function during a minimum period of time coder *be environe ntal limit conditions. The alphanumeric codes in columns FT of table have been used to designatt the function times.
The alpha codes a~ defined as follows: Code Function Time (FT) A 0 to 45 see B 0 to 10 min C 0 to I hr D 0 to 6 hre E O to 12 hrs F 0 to 24 hrs C 0 to 2 days il O to 30 days I If to 100 d.iyg J AIW 'Y8 Ad.silable (steady state operation) e t P e
LSCS-FSAR AMENDMENT 57 JUNE 1981 i M.4 PLANT ENVIRONMENTAL 2ONES 7t e plant areas containing safety-related electrical equipment ate divided into three types of zones. These zone c:assifications are the harsh environment, normal environment and cc 7 trolled environment, and are further described and delinea,^d in this section. M.4.1 Harsh Environment '?CA/HELB) - BOP Eauioment Harsh environments are defineds as: 1) those areas of the plant inside primary containment that are sub;ected to environmental conditions resulting from a postulated 17ss-of-coolant accident
. (LOCA) or a high energy line break (BELB), and 2) those areas of
, the plant outside primary ccntainment houring safety-related
- - equipment that are subjected to environmen'.a1 conditions resulting from a postulated HELB.
There are five areas of the plant that can ne considered harsh ! env i rcr ..ents . Each of these areas has beer. assigned a zcne number, and the boundaries are defined in Figures M.4-1 cad H.4-2. A general description of these zones is provided in the i following tabulation: Zone Hi - Inside the reactor pressure vessel (RPV) h Zone H2 - Inside primary containment (drywell) i Zone H3 - Inside primary containment (wetwell) 3 Zone H4 - Reactor Building,. excluding ECCS equipment I cubicles and HELB local ~ areas Zone H5 - HELE local areas, including main steam
- pipe tunnel, RCIC pipe chase, RCIC equip-ment cubicle, Rh'CU equipment areas (pump,
- valve, and heat exchanger rooms and pipe chases).
- Each of these zones experiences normal anF. may experience abnormal environmental conditions. Norral conditions or service r conditions are defined as those conditirns s that exist durino routine plant operations. In some cases- these service -
conditions may extend over a range of conditions which could be expected to occur at various times during the operating life of the plant. Abnormal or bounding conditions are defined as those conditions that can occur as the result of postu.'ated failures, such as LOCA and HELB. Since the bounding conditions usually I present the most difficult challenge to equipment operation, they will be discussed first. Note that to determine the total potential radiation exposure, the normal and abnormal values must h be added. i M.4-1
LSCS-FSAR AMENDMENT 57 JUNE 1981 H.4.1.1 Selection of Boundina Ccnditions 2one H1 For this zone, the operating conditions inside the RPV, excluding radiation exposure, present the most limiting environmental conditions for equipment qualification. These conditions are summarized in Table M.4-1. 2one H2 The bounding conditions for the drywell are determined from an enyelope of the conditions resulting from a LOCA or HELB inside containment. These conditions are presented in Table M.4-2.
- a. Pressure As discussed in FSAR Section 5.2, the maximum pressure response inside the containment occurs as a result of the postulated instantaneous guillotine break of the reactor recirculation line (LOCA). This peak calculated pressure is 32.5 psig (FSAR Figure 6.2-2). The maximum pressure chosen for the bounofog condition (45 psig) is thus very conservative. Mail.
steamline breaks were evaluated, cnd the resultant peak calculated pressures were bounded by the g) recirculation break case.
- b. Temoerature Again referring to the analysis results presented in FSAR Section 6.2, the peak calculated drywell temperature occurs for the main steamline break case, and is 3300 F (Figure 6.2-10). The bounding condition selection of 3400 F represents a conservative value for-equipment qualification.
- c. Relative Humiditv An all steam environment, followed by 100% relative humidity, represents a very conservative approach.
- d. Duration The durations indicated for the bounding conditions were based on generic information supplied by General Electric in their interface documents. The plant specific analysis presented in Saction 6.2 is bounded by this generic information. Therefore, the plant specific information is utilized rather than the design profiles presented in NUREG-0588 ?.ppendix C.
H.4-2
LSGS-FSAR AMENDMENT 57 JUNE 1981
- e. Radiation l The integrated accident dose is based on GE interface information, and is based or. the assumption that 100t l-of the noble gases, 50% of the halogens, and 1% of
. the solid fission products were released from the . core as a result of the postulated LOCA.
- f. Submeraence The maximum flood level in the drywell following a LOCA is determined by the projection of the
, suppression vent downcomers above the dryweil floor. These vents project 6 inches above the floor elevation of 736 feet 7-1/2 inches. Zone H3 The bounding corditions for the wetwell (suppression chamber) are presented in Table M.4-3. The analytical basis for these conditions is also presented in FSAR Section 6.2.
- a. Pressure The peak calculated suppression chamber pressure represented in Figure 6.2-2 is bounded by the
{g selected value of 45 psig. i b. Temperature The peak calculated suppression chamber temperature occurs on the long-term basis, rather than in th? first few moments following a LOCA, The 2120 F value
- selected as bounding can be seen to be conservative
- when compared to the analytical results presented in Figure 6.2-7.
- c. Relat ive Humidity The basis for the assumption of 100% relative humidity above the pool is based on examination of the normal and abnormal pool vapor conditions and 1
requires no further comment.
- d. Duration
, The durations presented are based on the worst case analytical results as presented in Figure 6.2-7. j e. Radiation 3# The name basis as that of 2one H2 (item e) applies here. M.4-3 i
* + .
LSCS-FSAR AMENDMENT 57 JUNE 1981
- f. Submeroence The maximum pool level is elevation 700 feet 3 inches.
Zone H4 The maximum conditions in the general reactor building area result from HELB events in equipment cubicles venting to the general floor area. The most limiting case, selected from the analytical evaluation of all the HELB cases, was c'osen for these bounding conditions. These conditions are listet .n Table M.4-4.
- a. Pressure No significant pressurization of the reactor building volume occurs during any postulated event.
f therefore, atmospheric pressure was chosen as the upper bound. i b. Temoerature The temperatures associated with this zcae actually occur at only one location in the reactor building,
' but were selected as the design basis since they
. bound the other locations.
' ]h c. Relative Humidity
- The 95% relative humidity represents a conservative limit abose and beyond that which was actually 1 determined to occur by analysis.
- d. Duration i The durations were based on actual time histories 1 -determined from the bounding analysis.
i e. Radiation
- The same basis as that of Zone H2 (item e) applies here.
l f. Submeroence i i No significant flooding of the reactor building i occurs during HELB conditions. The drainage and sump i systems prevent any water buildup. t i 2 ore H5 The conditions for local areas subjected to HELB's are based on
. ll() ! bounding conditions selected from GE interface documents compared H.4-4 i
1 e
LSdS-FSAR AMENDMENT 57 JUNE 1981 with the analytical results in the tpecific line break cases. Table H.4-5 lists these conditions, gllh
- a. Pressure The initial transient pressure cor.ditions were selected from the bounding analysis and represent the peak pressure in the main steam tunnel. Subsequent pressure values bound the analytical results,
- b. Temperature The assumption of saturation temperature for the first 6 hours represents a conservative approach when compared with actual results. The subsequent temperatures also bound the analytical results.
- c. Relative Humiditv The saturated steam environment for 6 hours followed by 100% relative humidity for another 6 hours, then 100 days at 90% relative humidity bound all analytical results.
- d. Duration As discussed in the previous sections, the durations bound the analytical results.
- e. Radiation The same basis as that of Zone H2 (item e) applies here.
Submerae,ce , .f. The same basis as that of 2one H4 (item f) applies here. H.4.1.2 Service Conditions The normal service conditions of the plant represent those conditions actually expected to occur during the normal operation , of the plant. 7.one H1 1 The range of normal operating conditions inside the RPV are shown
- in Table M.4-6.
l 1 H.4-5
LSCS-FSAR AMENDMENT 57 JUNE 1981 Zone H2 Table M.4-7 presents the range of normal operating conditions that are expected to occur inside the drywell. For the BOP equipment, a bounding radiaticn exposure, as provided in Table M.4-7 was selected. Zone H3 Table M.4-8 presents the range of normal operating conditions in the wetwe?1.. Zone H4 Table M.4-9 presents the range of normal operating conditions expected in the reactor building general area. Zone H5 Table M.4-10 presents the bounding range of normal operating conditions expected in the HELB areas. Highest temperatures occur in the RWCU areas and main steam tunnel. The highest radiation exposure occurs in the RWCU heat exchanger room. M.4.2 Harsh Environment (LOCA/HELB)-NSSS Ecuicment d The definition of harsh environments is the same as that provided in Subsection M.4.1; however, the zone designations determined by the NSSS vendor (General Electric) divide the plant into additional subzones. These subzone designations are referenced in Table M.3-2 and correlate to the BOP zone as described in Subsection M.3.2.3. The abnormal and normal conditions indicated for these zones in Table M.5-2 are based on GE design specification 22A3008, "BWR Equipment Environmental Interface Data." These conditions exceed or equal those associated with the BOP harsh zones because they were determined as generic bounding onditions for all GE BWR-5 plants. Therefore, the benefits gained later by specific analysis on La Salle to determine less severe cond:.tions could not be passed on to the NSSS equipment qualification program because of the necessity to purchase the NSSS equipment early in the schedule of the project before these unique analyses were completed. Thus, the conditions specitied in Table M.5-2 may not agree with the conditions specified for the corresponding zone in Tables M.4-1 through M.4-10; however, the conditions in Table M.5-2 are usually more severe enveloping conditions than those provided in Tables M.4-1 through M.4-10 which more accurately represent the actual conditions in the plant for the specified events. In the
]) few cases where this is not true, a justification must be provided. The BOP definitions of harsh environments utilizes the t
i , M.4-6
LSCS-FSAR AMENDMENT 57 JUNE 1981 HELB analyses in FSAR Chapters 6.0 and 15.0 and Appendix C to 4 modify General Electric Company's original limiting specification 22A3008. H.4.3 Normal Environment (Non-Safetv-Related HVAC Svstems) - BOP Equipment t Normal environments are those areas in the auxiliary and turbine I buildings being maintained at room conditions by the rso-safety-I related HVAC system during routine plant operations. Abnormal I conditions may occur in these areas due to loss of the HVAC system.
- The areas considered have been assigned a zone number and boundaries as defined in Figure M.4-3. The bases for selecting
- the bounding conditions for each zone are as follows: ' Zone N1 - Areas that are served by the air conditioning system te maintain environmental conditions suitable for personnel :omfort and equipment operation. Since these areas do not contain any safety-related equipment and are occupied during normal plant operation, the environmental conditions resulting from loss of the air conditioning system were not evaluated. The normal environmental conditions are listed in Table M.4-11. ZoneN2-Areasthatarenormallyprovidedwithventilationto maintain the temperature range in conformance with the equipment
The time dependent histogram of pressure, temperature ratings.
temperature and relative humidity were determined using the historical Engineering Weather Data (compiled by the Engineering Meteorology Section of the U.S. Air Force, Manual No. AFM 88-29, dated July 1, 1978) applicable to the plant site. The environmental conditions in the areas where safety-related
- equipment are installed were selected for the analysis since only the Class 1E equipment need the qualification. The minimum, normal, and maximum conditions with the ventilation system operating and maximum cooling load were determined. Also evaluated were the transient conditions in the selected area during loss of the ventilation system. The results are as presented in Table M.4-12.
Zone T1 - Generally accessible areas in the turbine building
- wherein the temperature is limited to a maximum 1040 F by the
. operation of the turbine building ventilation system. Only the
- areas with safety-related instrumentations installed were
- selected for the analysis of enrironmental conditions during loss
- of the ventilation system due to loss of offsite power, and the results are presented in Table F.4-13.
- Zone T2 - Potentially contaminated areas in the turbine building wherein the temperature is limit (d to 1220 F by the operation of
,3y the turbine building ventilation system. Only the areas with
- safety-related instrumentations ware selected for the analysis of H.4-7
LSCS-FSAR AMENDMENT 57 JUNE 1981 environmennai conditions during loss of the ventilation system due to loss of offsite power, and the results are presented in Table M.4-14. M.4.4 Normal Environment (Non-Safety-Related HVAC Systems) - NSSS Equipment As referenced in Table M.3-2, a few NSSS equipment have been identified which are located in these Normal Environments. The qualification summaries are presented in Table M.5-4. M.4.5 Controlled Environmeat (Redundant HVAC Systems) - BOP Equipment Controlled environments are defined as:
- a. those areas of the plant housing safety-related equipment and served by redundant safety-related HVAC systems; and
- b. those areas of the plant where the safety-related equipment are redundant and each redundant part is served by a separate safety-related HVAC system that maintains the temperature and humidity in accordance with the equipment operating requirements.
There are four areas of the plant that are considered having a controlled environment. Each of these areas has been assigned a zone number and the boundaries are defined in FigJre M.4-3. A general description of these zones together with the bases for selecting the bounding conditions are as follows: Zone C1 - Inside the main control room and aux'iliary electric equipment room. The HVAC system serving these areas is designed to maintain the pressure, temperature, relative humidity and radiation as listed in Table M.4-15 during normal and accident plant' conditions. Zone C2 - Inside the Essential Switchgear Rooms. The ventilation system serving these areas is designed to maintain the pressure, temperature, and relative humidity as listed in Table M.4-16 during normai and accident plant conditions with the switchgears in use. The durations indicated were based on the Engineering Weather Data (compiled by the Engineering Section of the U.S. Air Force, Manual No. AFM 88-29, dated July 1, 1978), applicable to the plant s.ite. Zone C3 - Inside the diesel generator building including the RHR service water pump rooms and the HPCS pumps and switchgear rocms. The minimum and normal conditions were determined based on the Engineering Weather Data (USAF No. AFM 88-29), applicable to the plant site and when the equipment is not operating. The maximum condition was determined when the equipment is operating. The duration for the maximum conditions were conservatively based on M.4-8
LSdS-FSAR ' AMENDMENT 57 } JUNE 1981 1 l I the normal operating and testing of the equipment plus their l: operation during design basis accidents. Tl.e environmental conditions are as listed in Table M.4-17. 4 a Zone C4 - Incide the ECCS equipment cubicies in the reactor building except for the LPCS/RCIC cubicles. These areas are normally ventilated by the reactor building ventilation system to maintain the minimum and normal temperatures when the ECCS j equipment is not operating. The maximum conditions in these j cubicles are determiced to occur when the ECCS equipment is 4 operating. These maximum conditions were based on the normal operating and testing of the ECCS equipment plus their operation j during design basis accidents. The minimum, normal and maximum
- conditions are as listed in Table M.4-18.
i M.4.6 Controlled Environment (Redundant HVAC Systems) - NSSS Equioment The definition of controlled environments is the same as that provided in Subsection M.4.5, with a possible exception for the ECCS cubicle area (BOP Zone C4, NSSS Zones RB4, RB5). The environmental conditions indicated for these zones in Table M.5-6 are based on GE design specification 22A3008, "BWR Equipment Environmental Interface Data," and usually exceed or equal those associated with the BOP controlled zone because they were
; determined as generic bounding conditions for all GE BWR-5
) plants.
Thus, the conditions specified in Table M.5-6, which are usually s more severe enveloping conditions, may not agree with the conditions specified for the corresponding zone in Tables M.4-15 through M.4-19 which more accurately represent the actual conditions in the plant. 1 The correlation between BOP-NSSS Zone designations is provided in
. Subsection M.3.2.3.
l ^ H.4-9
LSCS-FSAR AMENDME:;T 53 DECEMBER 1980 y I TABLE M.4-1 l BOP - RARSH ENVIRONMENT 2ONE H1 AND .I NSSS - HARSH ENVIRONMENT ZONE RPV e i BOUNDING ENVIRONMENT CONDITIONS INSIDE THE RPV , e l, NORMAL DESIGN MAXIMUM
~
I 546 Temperature (*F) 575 581 ) j , Pressure (psig) 1010 1250 1340
- Relative Humidity Saturated Saturated Saturated Steam / Water Steam / Water Steam / Water
, Radiation 2.6 x 10 7 rads (accident gamma integrated)
~
!e I
1 1 . . 4 e 5 i I i
~
) . i ) i k -
- n. 4 -10 I .
I,SCS-FSAR Av2NDMENT E3
~
DECDi3ER 19 8 0 TABLE M.4-2 - BOP - HARSH E!NIRONMENT ZONE H2 AND
. NSSS - HARSH ENVIRONMENT _20NES PCl THROUGH PCS BOUNDIt'G E!NIRONMENTAL CONDITIONS INSIDE THE DRr4 ELL Temperature (*F) 340 320 250 200 Pressure (psig) -2 to 45 -2 to 45 0 to 25 0 to 20
. Relative Humidity Steam Steam 100% 100%
puration 0-3 hr 3-6 hr 6 hr to 1 day to 1 day 100 days 7 Radiation 2.6 x 10 rads ga=na (integrated) e e 9 e s P e e e e o e e 9
- M.4-11 M *.W R ""-a . .ar ia r.. r .. .
~ * " ' '
. . m **')9'"'* * A *T " ' % ' t "*'*'**"N .
* ' ' ' " " ' ' *1.
i e
- LSCS-FSAR AMn
- DMENT 53 i
DECDiBER 1980 I . L TABLE M.4-3 ", BOP - HARSH EWIRONMENT 2ONE H3 AND 1: NSSS . HARSH ENVIRONMENT ZONE PC6 - (~ BOUNDING EN'/IRONMENTAL CONDITIONS INSIDE THE WETWELL i Temperature (*F) 200 200 150 i Pressure (psig) -2 to 45 0 to 25 0 to 25 i ! Relative Humidity 100% 100% 100%
- Duration 0 to 6 hr 6 hr to 1 day to 1 day 100 days 7
. Radiation 2.6 x 10 rads gamma (integrated) o G k t i 4 I E f i 4 i 9 . M. 4- 12
as=. 2o t
- h
- TABLE M.4-4 t
I BOP - HARSH ENVIRONMENT 2ONE R4 AND L. j NSSS - HARSH ENVIRO': MENT 2ONES RBI, RB2, AND RBS ) e- B0UNDING ENVIRONMENTAL CONDITIONS IN THE REACTOR BUILDING 1-b } .
- j. Temperature (*F) 145 --
134 - - i Pressure (psig) Atmospheric Atmospheric f.
- j. Relative Humidity e 95% 95%
Duration 0 to 1 day 1 day to 100 days .l Radiation 5 1.7 x 10 rads gamma (integrated) i i e 7 I
~
o 9 i 4
- I.
3 i 1
; M.4-13 I
_ , _ , , , , se m em-o w - ~m~O..--- - -
**- LSCS-FSAR
, AMENDMENT 53
. DECEMBER 1950 i,
g TABLE M.4-5 S BOP - HARSH ENVIRONV.ENT ZONE E5 AND , -; NSSS - HARSH E!T/IRONMENT ZONET R33, RB5, AND R37 s~ BOUNDING ENVIRONMENTAL CONDITIONS FOR HEL3 AREAS i i s --
~~
- Temperature (*F) 212 150 150 i
f Pressure (psig) ? in. H 20* 7 in. H 2O Atmospt. erie l Relative Humidity Steam 100% 90%
- j. . Duration D-6 hr 6-12 hr 12 hr to 100 days 5
Radiation 1.7 x 10 rads gamma (integrated) I I a t i l a _g
- Transient peak pressure of 40 psig can occur within the J first 10 seconds of the line break event. However, venting and subsequent depressurization occurs very rapidly.
M.4- 14 h
~ ~ ' ~ '
LSCS-FSAR APJ.!;DME::T 53 DECEMBER 1980 i TABLE M.4-6 - BOP - EARSH E!NIRO : MENT ZONE H1 A!;D l NSSS - EARSH ENVIRCNME!!T 20ME RPV SERVICE CONDITIONS TNSIDE TO RPV . i .
! NORMAL DESIG3 MAXIMUM Temperature (*F) 546 575 581 i
i Pressure (psig) 1010 1250 1340
- Relative Humidity --Saturated Water / Steam--
Radiation 10 Gamma (rads)
- 2.3 x 10 16 Neutrons (neutrons /cm )
- 7.,9 x 10 5
L s
- Integrated over 40 years.
M.4-15
, um y gM s-- >- 9 g hy p***'M+** T .'.9 87 M
- M ' ' " r** 4 e *y
, M Nh T g'P -^*W"'f M 'f f WP' 9*
'**M JPr gtM = 99 =s , g = , p-o f 93 ,,9 *,=p ; q 9P - NMm 4 7 . ... Eh-, a
, , _ , , r l'
LS'CS-FSAR A!1ENDMENT 57 JUNE 1981 1
}
TABLE M.4-7 1O 7' BOP - HARSH ENVIRONMENT ZONE H2 AND j_ NSSS - HARSH ENVIRONMENT ZONES PCl THROUGH PC5 A. SERVICECONDhTIONSINSIDETHEDRYWELL (ZONES PCl, []' PC2, PC4 and PCS) 4 j NORMAL MAXIM 11'1 f 1 Temperature (*F) 135 150 i i Pressure (psig) -0.5 to 2 --- Relative Humidity 40 - 55% 90% 4 Duration
- 14,370** ***
_ Radiation:
+
Neutron - 4 (1) For BOP Equipment Gamma (rads)+ (Neutron /cm') 7 14 q . Zone H2 1.8 x 10 1.8 x 10
; (2) For NSSS Equipment ! Zone PCl (above 6 13 , core) 8.8 x 10 6.3 x 10 Zone PC2 (core 7 14 region) 1.8 x 10 1.8 x 10 i Zone PC4 (near 6 12 recirculation 8.8 x 10 2.5 x 10 Zone PC5 (15 ft 6 12 ; from recirculation) 1.4 x 10 2.5 x 10 i B. SERVICE CONDITIONS IN THE CRD PEDESTAL AREA (ZONE PC3)
NORMAL MAXIMUM l Temperature 116 175 l 4 Pressure -0.5 to 2 I i Relative Humidity 4 to 15%
) r..
f Duration
- 14,601 9 i
M.4-16
^ M .*1.tNIET*"T." ** T*. 2"*f* T '.
5 LS S-FSAR AMENDMENT .<7 3 JUNE 1981 \* ? g(g TABLE M.4-7 (Cont'd)
+
Neutron , N Endiation Gamma (rads)+ (Neutron /cm#) ! 12 ) 2.5 x 10 6 2.5 x 10 i 1 i 1 l 1 i Y l i f i, - j Number of days in 40 years life - t ** The reactor is conservatively assumed to have 120
- . ' shutdowns (averaging two days each) in the 40 years 1 normal operating life. During shutdown, the tem-
- peratore is conservatively assumed to be 104*F.
- *** 'the maximum temperature of 150*F occurs (a) in the 1 RvV annular rpace where no safety-related ecuipment i is located, (b) possibly during VP HVAC System switch- . over (assumed not to exceed a total of 10 daj s during
- the 40 years normal operating life) and (c) due to some unidentified system leakage (assumed not to exceed
- 40 days durin the 4J years normal operating life
. because unit snutdown wocld be initiated if containnent 4 temperature reached 150*F).
+
Integrated over 40 years, t i a M,4-17
LSCS-FSAR AME :DME!:T 53 DECEMEIR 1930 . i ~
. TABLE M.4-8 4 .
lh BOP - HA.1;H E!NIRO!!ME!!T 20 tie H3 A!iD
. 1:SSS - HARSH E!NIRO!!ME!;T ZO!!E PC6 I
SERVICE CO!!DIT!O!;S I!! SIDE "'HE WET 4 ELL l e ' o NORMAL MAX IM'i'4
~
~
Temperature (*F) 95 110 j . Pressure (psis) -0.5 to 2
~
i - Relative Humidity ' 95 100 i 4 i Radiation 3.5 x 10 rads gan=a (integrated) i k - 4 . O e 4 . I i ! M . 4 -- 18
15CS-FSAR ANENDMENT 57 f JUNE 1981 t TABLE M.4-9 f l - BOP - HARSH ENVIRONMENT ZONE H4 AND i NSSS - HARSil ENVIRONMENT ZONES RBI, RB2, AND RB8 f SERVICE CONDITIONS IN THE REACTOR BUILDING f (GENERAL ACCESSIBLE AREAS) ! DURATION l RELATIVE NC OF DAYS HUMIDITY IN 40 YEARS I TEMPERATURE PL7 TNT LIFE l' (*F) (t) 49 3 100 49 57
- 98
}^ 48 197 96 48 234 94 t 48 335 92 48 3291 90
' 42 116 85 -
61 40 , 9306 3 rads gamma (integrated) Radi- *. ion: 5.3 x 10 \ Pressure: -0.4" W.G. } f s J M.4-19
LSbS-FSAR AMENDMENT 57 JUNE 1981 3 TABLE M.4-10 BOP - HARSH ENVIRONMENT ZONE H5 AND N3SS HARSH ENVIRONMENT ZONES RB-3, RB-6 AND RB-7 A. SERVICE CONDITIONS IN THE LPCS/RCIC CUBICLE (SUBZONE H5a - RB3)
- 1. When the ECCS Equipment is operating:
I The maximum cubicle temperature is 148'F, 90% rels-tive humidity and at atmospheric pressure. The duration of normal operating and testing of the - ECCS equipment is approximately 41.06 hours per month or a total of 19,710 hours within 40 years plant life. Thus the total number of hours the cubicle is at 148'F will be = 22,110 hours (~ 9 21 days). The 100 days accident conditions are included.
- 2. When the ECCS Equipment is not opruating:
DURATION
. RELATIVE NO. OF DAYS TEMPERATURE HUMIDITV IN 40 YEARS
(*F) (%) PLANT LIFE
- l 106 41 3
- 104 40 54 102 40 -
186 100 40 221 i 98 40 334 1 96' 40 3106 91 35 1102 87 34 8782 6 Radiation: 8.76 x 10 rads gamma (integrated) Pressure: -0.4 inches W.G.
$h
- Note that this column does not include the 821 non-3 accident days f rom part A.
l M.4-20
AMCNDMENT 57
$ LSCS-FSAR
( JUNE 1981 i, I, TABLE M.4-10 (Cont'd) 4
._ B. S_ERVICE CONDITIOMS IN Tl!E RCIC PIPE TUNNEL __(SUBZONE H5b - ,t NONE) }
DURATION
} RELAT!vE NO. OF DAYS 5 ' TEMPERATURE HUMIDITY IN 40 YEARE i (*F) (t) ,
PLANT LIFE
\
140 16 3 { i 16 67 j 138 i j 136 16 197 1 i 134 15 234 132 15 355 l 130 15 3291 i 125 14 1;57
; 121 13 9306 6
hhh Radiation: G.76 x 10 rads gamma (inte grated)
. Pressure: -0.4 inches W.C.
1 C. SERVICE CONDITIONS IN THE MAIN STEAM TUNNEL (SUBZONE H5c - RB6) . DURATION
< . RELATIVE NO. OF DAYS I TEMPERATURE HUMIDITY IN 40 YEARS
('P) (t) PLANT LIFE 112 35 3 110 34 57
' 197 108 34 i
306 34 234 104 34 355 I 102 34 3291 97 29 1167
# 93 28 9306 +
6 ! Radiation: 8.76 x 30 rods gamma (intearated) Pressure: -0.4 inches W.G. M.4-T]
j, LSCS-FSAR AMENDMENT 57 4 t JUNE 1981 l 1_3 TABLE M.4-10 (Cent'd) I t D. SERVICE CONDI'fIONS IN THE RWCU EQUIPMENT AREAS (LL 2ONE H5d - RB7) j DURITION RELATIVE NO. OF DAYS TEMPERATURE HUMIDITY l (*F) IN 40 YEARS ) (%) PLANT LIFE } 113 23 i' 3 111 33 l 57 'I 109 1 32 197 i 107 32 234 105 32
, 355 103 32 3291 98 29 1167 , 94 27 i 9306 3 g(h Radiation: 8.76 x 10 6 rads gamma (integrated)
Pressure: -0.4 inches W.G. . O n a l i f ' e
~
M.4-22
SSCS-FSAR AMENDMENT 57 JUEN 1981 f, .-,
' l' -
TABI.E M.4-ll s1 12 BOP - NORMAL ENVIRONMENT ZONE N1 t 'i 1 MINIMUM NORMAL MAXIMUM i; 't Temperature (*F) 65 75 85 li jj Pressure (Inches H 2O) 0 0 0 i i Relative Hu:nidity 35 45 55 i . 4 j: . Radiation 1 x 10 rads gamma (integrated) i I i t e L 9 1 l i 1 1 6 } 9 f M.4-23
1 i LSCS-PSAR AMENDMENT 57 } JUNE 1981 1 .
} TABLE M.4-12 IeP i
BOP - NORMAL E!NIRONMENT ZONE N2 A. INSIDE CONDITIONS WI?H THE VENTILATION SYSTEM OPER!iTING DURATION RELATIVE NO. OF DAYS TEMPERATURE HUMIDITY IN 40 YEARE j ('F) '(%) PLANT LIFE 106 34 10 105 32 97 !! 275 100 34 l
, 95 38 540 I
90 40 812 85 46 1136 80 50 1266 75 50 1167 j 70 52 1007
; 65 50 8299 4
Radiation: 1 x 10 rads gamma (integrated). 1 Pressure: +0.4 inches E.G. t. t l l l 1 l i M.4-24
s, LSCS-FSAR AMENDMENT 57 JUNE 1981 1i ,i TABLE M.4-12 (Cont'd)
~
, s
!- 5. INSIDE CONDITIONS DURING LOSS OF VENTILATION SYSTEM 14 1, .-
Il .'J' TIME (HOURS) 144 Up l to 100 i , 0 24 48 72 96 120 days Temp. (*F) 96 95 95 95 95
- ' 1) HVAC Equip. ummer 104 95 46 46 46 46 46 l' Area at Rel. Hum. (%) 32 45 Temp. ( F) 65 51 48 46 45 45 45 Winter
' '(8 ft Rel. Hum. (%) 24 32 36 38 40 40 40 6 in. . 1 2) 4160V Swgr. Temp. (*F) 86 102 104 106 108 110 120 ummer 36 25
.' 142X/242X Rel. Hum. (%) 72 46 42 38 37 55 55 i Areas F1. Temp. (*F) 65 60 59 58 57 WiUt*# Rel. Hum. (%) 20 20 25 26 27 28 28
- El. 732 ft
) - 0 in.
- Notes: (1) The summer and winter outside air temperature of 95* F
, and -10' F, respectively, wer e assumed to occur daily
- during loss of ventilation system; represents a very conservative result. f' (2) The pressure range inside the Zone N2 area is 0 in. to
+ 0.125" W.G.
4 1 (3) Radiation 1 x 10 rads gamma (' ' grated). L O n M.4-25
LSCS-PSAR AMENDMENT 57 f ^ JUNE 1981 TABLE M.4-13 lk BOP - Normal Environ 7 ant Zone T1 CONDITIONS INSIDE THE TURBINE BUILDING (GENERAL ACCESSIBLE AREAS) i A. INSIDE CONDITIONS WITH TdE VENTILATION SYSTEM OPERATING i I DURATION REALTIVE NO. OF DAYS I TEMPERATURE HUM'OITY IN 40 YEARS
'(*F) '(%) PLANT LIFE 102 47 3 100 46 57 98 45 197 96 45 234 94 45 355
- 92 45 3288 1167 l( 87 40
. 83 39 9309 Radiation: 7.7 x 10 4
rads gamma (integrated) ' Pressure: -0.125 inches W.G. 4 i t 9 M.4-26
5 LSCS-FSAR AMENDMENT 57 l JUNE 1981 I 1 I TABLE M.4-13 (Cont'd) i t SYSTEM B, I_NSIDE CO'4DITIONS DURING LOSS OF VENTILATIOli ! AFTER LOSS OF OFFSITE POWER 1, e 6 9 1 I t 3 M,4-27
LSCS-FSAR AMENDMENT 57 JUNE 1981 4 i' '. TABLE M.4-14
- BOP - Normal Environment Zone T2
'] CONDITIONS INSIDE THE TUP.BINE BUILDING j ~(POTENTIALLY CONTAMINATED AREAS) i li. INSIDE CONDITIONS WITH THE VENTILATION SYSTEM OPERATING DURATION RELATIVE NO. OF DAYS ' TEMPERATURE HUMIDITY IN 40 YEARS l (*F)
'(%) PLANT LIFE I
121 28 3 i 119 27 57 117 27 197 115 27 234 113 26 355
- 111 26 3288 f
106 22 1167
- 102 21 9309 7
Radiation: 1 x 10 rads gamma (integrated) Pressure: -0.125 inches W.G. M.4-28
LSCS-FSAR AMENDMENT 57 l JUNE 1981 i TAU'uE M.4-14 (Cont'd) i 4 B. INSIDE CONDITION 3 DURING LOSS OF VENTILATION SYSTEM AFTER ! LOSS OF OFFSITE POWER ? I i i i i i i ) i 1 I S I i i IJ 3 2
- M.4-29
AMENDMENT 57 JUNE 1981 TABLE M.4-15 i; , BOP - CONTROLLED E!!VIRONMENT ZONE Cl CONDITIONS IMSIDE THE MAIN CONTROL ROOM & AEER t
! Minimum Normal Maximum
) Temperature (*F) 72 73' 74 l 1 Pressure (Inches H 2O) - 0 -0.125 -0.25 1 P j Relative Humidity 35 40 45 i Radiation 1 x 103 rads gamma (integrated) t y . F e e I J t 4 . I M.4-30
f t . LSCS-FSAR AMENDMENT 57 JUNE 1981 3 TABLE M.4-16 ! BOP - CONTROLLED ENVIRONMENT ZONE _C2 CONDITIONS INSIDE THE ESSENTIAL SWTICHGEAR ROOMS l DURATION l 4 REIATIVE NO. OF DAYS j TEMPERATURE HUMIDITY IN 40 YEARS I ('F)
'(%) ' PLANT LIFE l
i 104 . 36 10 l 1 103 34 99 98 36 282 i j 93 40 554 l 88 43 833 i 83 49 1164 78 53 1294 {
, 73 55 1167 > 68 58 1007 65 51 , 8300 4
J Radiation: 1 x 10 rads gamma (integrated) Pressure: +0.125 inches W.G. l i I i i
)
i . M.4-31
f LSCS-FSAR AMENDMENT 57 j JUNE 1981 } I J , TABLE M.'4-17 i BOP - CONTROLLED ENVIRONMENT ZONE C3 1 CONDITIONS INSIDE THE DIESEL GENERATOR ROOMS, RHR SERVICE WATER PUMP ROOMS & HPCS SWITCHGEAR & PUMP ROOMS 1 1 A. WHEN THE DIESEL GENER?. TOR, PUMPS, AND SWITCHGEAR ARE OPERATI!!G DURATION } RELATIVE NO. OF DAYS i TEMPERATURE HUMIDITY IN 40 YEARS 3 ('F) '(%) PLANT LIFE i i 119 - 21 10 114 25 99 f 1d9 26 180
/
104 29 109 ,' 99 30 ~74 j 94 34 90
>9 37 53 84 38 57 i 80 38 . 240 <^
4 3 Radiation: 1 x 10 rads gamma (integrated) t 3 Pressure: +0.5 inches W.G. 3 B. WHEN THE DIESEL GENERATOR, PUMPS, AND SWITCHGEAR ARE NOT OPERATING DURATION RELATIVE NO. OF DAYS TEMPERATURE HUMIDITY IN 40 7 .ARS j ('F) (%) PLANT LIF E I } 109 32 75 } j 107 32 158 i 105 32 314 ? i 103 31 3074 4 1
, M.4-32
I LSCS-FSAR T.MENDMENT 57
- JUNE 1981 3
i TABLE'M.4-17 (Cont'd) { j l DURATION RELATIVE NO. OF DAYS j TEMPERATURE HUMIDITY IN 40 YEARS j (*F) '(%) ,
, PLANT LIFE 98 29 1111 f 94 29 9056 4
Radiation: 1 x 10 rads gamIna (. integrated) i j Pressure: -0.125 inches W.G. l 4 i f I, f i i I I 4 ) l i i l ? I i i i . M.4-33
LSdS-FSAR AMENDMENT 57 l JUNE 1981 1 I TABLE M.4-18 BOP - CONTROLLED ENVIRONMENT ZONE C4 I CONDITIONS INSIDE THE ECCS CUBICLES
,(EXCLUDING LPCS/RCIC CUBICLE) IN THE REACTOR BUILDING A. WHEN THE ECCS EQUIPMENT IS OPERATING The maximum cubicle temperature is 148'F, 90% relative humidity and at atmospheric pressure. The duration of I normal operating and testing of the ECCS equipmcat is i approximately 41.06 hours per month or a total of 19, 710 i hours within 40 years plant life. Thus, the total number
- of hours the cubicle is at 148 F will be =22,110 hours
- (~921 days) . The 100 davs accident conditions are in-
, cluded. { B. WHEN THE ECCS EOUIPMENT IS NOT OPERATING 4 DURATION RELATIVE NO. OF DAYS
- TEMPERATURE HUMIDITY IN 40 YEARS ,
t (*F) '(%) PLANT LIFE 105 42 3 i 54 103 41
, 101 41 186 i 99 41 221 i
l 97 41 315 ( I 95 41 3106 i 90 36 1102 85 35 8782 f 6 f Radiation: 8.76 x 10 rads gamma (integrated) i Pressure: -0.4 inches W.G. I '* Note that this colume does not include the 821 non-accident j days from part a. I k
. M.4-34
, e a
'I* M l ,
ip@ @
. . m, ,
s -p < 1
,ma .1) . -
r 35 . ,. . _ _ _dC . -.. . _ _ L__. M. i ,.--,,,-...
*c. ,. . _ . _ . . . . .
. . <. L 3 ,- . .
.a - ~=2 .-.*C-
- _ _. . A _n J r~L - MJ 3
u4 . I
.r,-.v--
..- . s. . :
c f s,/e y* '8,yJ 4 .
.,,.g.
,. d 8 l ~ . ' ,, ffs, - - =-
..s4*y ~
q - - 4. paa s'-
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. s/ ,,
/e
/' ; -
- e. -. .. '.'s ,. y . * . . ~ . . ,- ^ ~
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/- . . 6 ., .*
, , j , ,
f ],/ ' ' *
._ ", ) *,_ .
l
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' l NOVEMBER 1980
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