ML20090J943
| ML20090J943 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/09/1984 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| References | |
| OL-A-029, OL-A-29, NUDOCS 8405230393 | |
| Download: ML20090J943 (95) | |
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k jf 5 -352 355 oLl s 000XETED l U'iNRC , W APR 24 All:26 0FFICE Of SECFt iter - 00CKETING & SE6Vl4 l BRANCH ENVIRONMENTAL QUALIFICATION REPORT FOR ELECTRICAL EQUIPMENT
'\ LIMERICK GENERATING STATION UNITS 1 AND 2
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D , PHILADELPHIA ELECTRIC COMPANY v.s. wgABR RE - UHett b. gervenor- ! Appicast -7 Shi! WenHfied AdI'C ^" hed'Rel l Date: Repeden l OCTOBER, 1983 ' l l 1 7 8405230393 840409 PDR ADOCK 05000352 C PDR _ . _ _ .j
O TABLE OF CONTENTS Page INTRODUCTION 11 + 1.0 Environmental Design Criteria for Mechanical 1.1 and Electrical Equipment 2.0 Equipment Requiring Environmental Qualification 2.1 3.0 Environmental Service Conditions 3.1 , 3.1 Environmental Conditions During Normal 3.1 Plant Operation 3.2 Accident Environmental Conditions 3.4 4.0 Qualification Testing and Analysis of Equipment 4.1 1 5.0 Methodology for Evaluating Environmental 5.1 Qualification to Service Conditions 4 6.0 Corrective Action Plans 6.1 7.0 Justification for Interim Operation 7.1 8.0 Maintenance / Surveillance Program 8.1 9.0 Replacement Parts Program 9.1 10.0 References 10.1 Appendix A: Safety-Related Systems List Appendix B: Safety-Related Electrical Equipment List Appendix C: Plant Environments Appendix D: Equipment Qualification Review Record Appendix E: Equipment-Specific EQRR's 1 . O . i 4 a
l INTRODUCTION In February 1980, the Nuclear Regulatory Commission (NRC) requested that Philadelphia Electric Company (PECo) perform a review of the Environmental Qualification (EQ) of safety-related equipment at the Limerick Generating Station (LGS) to identify the , degree to which it complies with the applicable regulatory criteria. The purpose of this report is to discuss the LGS Electric Equipment Qualification Program and to demonstrate Limerick's compliance with the requirements of 10 CFR 50.49 and other
; applicable regulatory criteria. This LGS Mechanical Equipment Qualification Program will be discussed in a separate report.
The LGS EQ Program encompasses electrical equipment important to safety which has the potential to be subject to a harsh environment. A harsh environment is defined as an area that would be exposed to a significant increase in temperature, pressure, humidity
; and/or radiation levels during and after Design Basis Accidents (DBA's).
Mild environment equipment qualification is not included in the EQ Program discussed in this report. A mild environment is an environment that would at no time be significantly more severe than the environment that would occur during normal operation. Mild
! environment EQ is a quality assurance function and as such is addressed using 10 CFR 50,- ! Appendix B and Regulatory Guide 1.33 Criteria.
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1.0 ENVIRONMENTAL DESIGN CRITERIA FOR ELECTRICAL EQUIPMENT All equipment important to safety must be capable of performing its safety function and/or remaining in a safe mode under all conditions postulated to occur during its installed life. His requirement is embodied in General Design Criteria 1,2,4 and 23 of. Appendix A to 10 CFR 50, in Criteria III and XI of Appendix B to 10 CFR 50, and in 10 CFR 50.55 a(h) which incorporates by reference IEEE Standard 279-1971, " Criteria for Protection Systems for Nuclear Power Generating Stations." In May 1980, the NRC issued a Commission Memorandum and Order (CLI 80-21) requiring nuclear utilities to demonstrate qualification of their Class IE Equipment. The memo-randum and order outlined the following specific criteria to be used in evaluating qualifi-cation of electrical equipment:
- 1. He Division of Operating Reactors', " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines)
- 2. NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment" Revision 0, Category II for plants whose Construction Permit Safety Evaluation Report (CP-SER) was issued on or before July 1,1974
- 3. NUREG-0588 Category I for plants whose CP-SER was issued following July 1, .
1974 or plants which have a licensing commitment to IEEE 323-1974. Since the LCS CP-SER was issued in June 1974, NUREG-0588 Category II requirements are applicable. In January 1983, the NRC issued 10 CFR 50.49 on environmental qualification of electrical equipment. 1 The following sections demonstrate Limerick's conformance to the applicable regulations and regulatory criteria described above. 1 O - 1.1 '
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l3 U 3.0 ENVIRONMENTAL SERVICE CONDITIONS Equipment environmental service conditions have been evaluated for normal / abnormal and accident environments. Plant rooms provide the defined boundaries for environments, and Table 1 in Appendix C provides a summary of environmental condi-tions by room number for normal and accident conditions. All areas inside containment and rooms containing high energy lines or post LOCA recirculatory fluid lines outside of containment are considered to be harsh environments. As a result harsh environments are limited to the primary containment, the Standby Gas Treatment fan room, and the reactor enclosure. l The methodology used to develop the environmental conditions is discussed below. 3.1 ENVIRONMENTAL CONDITIONS DURING NORMAL OPERATION Temperature and Humidity Temperature and humidity conditions during normal operation are maintained within the limits shown in Table 1 of Appendix C by the Heating, Ventilation and Air Conditioning (HVAC) Systems. HVAC equipment serving safety-related areas is sized for peak thermalloads at a given time consisting of one or all of the following factors: < l
- 1. Maximum piping thermal loads for the room, if applicable, using maximum operating temperatures for the pipe contents for each mode or operation
- 2. Maximum internal electrical load assuming full lighting for the room and using, if applicable, the maximum control and equipment heat rejection for each mode of operation
- 3. Maximum heat transfer from miscellaneous equipment surfaces, if applicable, using the maximum operating temperature of the contents O
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- 4. Maximum heat transfer from the surfaces of the room including walls, floor and ceiling or roof.
FSAR Section 9.4 describes the HVAC Systems that maintain the temperature and humidity in each room within normallimits. Normal Radiation Ea:h plant area has been categorized into a radiation zone according to expected radiation levels. Each room, corridor, and pipeway is evaluated for potential radiation sources during normal operation, including anticipated operational occurrences and shutdown. The total integrated radiation doses for 40 years are provided in Table 1 of Appendix C. These doses were calculated for a 100% load factor and rated power during normal operation. The doses are based on design source terms of the radiation sources within each plant area. The normal radiation design source terms are based on a noble gas O- fission product rele'ase rate of 0.35 Ci/sec (after 30 minutes of decay) and the corres-ponding fission, activation, and corrosion product concentrations in the primary coolant. Normal radiation source terms are based on conservative assumptions about system and equipment operations and characteristics to provide conservative radioactivity concen-trations. For all systems transporting radioactive materials, conservative nilowance is made for transit decay while at the same time providing for daughter product formation. Assumptions from NUREG-0016, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors", Revision 1, were also used where applicable. Therefore, the normal radiation source terms are not intended to approximate the actual system design radioactivity concentrations. A, gig, Aging effects on all electrical equipment important to safety are considered in the EQ Program _ to conform to the requirements of Section 4 of NUREG-0588. Components susceptible to aging are identified and evaluated using NRC-approved methodologies. l 3.2 _ . _ .~. _
O Several methods of evaluating the aging effects of a component have been incorporated into the LGS EQ Program. Because LGS is a NUREG-0588, Category II Plant, aging of equipment prior to a DBA Test is only required for motors and valve motor operators. As a result, other types of equipment are evaluated on the basis of their materials' susceptibility to aging if pre-aging tests were not conducted. The Arrhenius methodology is used for accelerated thermal aging. Other aging methods, such as the 100C Rule, if used, are justified. Equipment that has not been age conditioned prior to qualification testing is evaluated for its susceptibility to age-related degradation. A review of materials information and/or operating experience is used in the age susceptibility evaluation. Information derived from this evaluation is used in the Maintenance / Surveillance Program described in Section 8. Synergistic Effects Synergistic eCfects, where known, are considered in the accelerated aging program. Specifically, vihere a supplier has identified a synergism or where PECo is aware.of synergistic efkets for a particular component, it has been addressed. Appropriate documentation is included in the qualification file. To date the only affected equipment has been cable. i Non-Seismic Plant-induced Vibration j Effects of known normal vibratory loads on equipment, when significant, are considered
- in the EQ Program.
Dust Ventilation filtration ensures a relatively clean, dust-free environment. In addition, plant procedures identify the actions required to maintain the HVAC filtration capa- l bility. 3.3
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W 3.2 ACCIDENT ENVIRONMENTAL CONDITIONS Operability Duration The operability duration is the length of time during and following an accident that 4 equipment must maintain its ability to perform its safety function. The safety functions l include:
- 1. The ability to initiate short-term protective action
- 2. The ability to place the plant in a controlled condition
- 3. 1he ability to keep the plant in a stable condition after the accident and until personnel are able to enter the plant to inspect, repair, or replace equipment important to safety.
The operability duration is determined individually for each LGS piece of equipment. The longest duration an equipment type is evaluated for is 180 days. As in the generation l of the equipment list, the Component Classification Program has been utilized in the review and establishment of operability duration. Temperature, Pressure, and Humidity Conditions inside Containment - The temperature and pressure conditions inside primary containment for the spectrum of LOCA's have been calculated using approved NRC methodology. The spectrum of LOCA's include:
- 1. Recirculation line guillotine breaks
- 2. Main steam line guillotine breaks
- 3. Intermediate size breaks
- 4. Small size breaks.
Temperature and pressure profiles were developed which bound the temperature and pressure conditions resulting from the entire range of breaks. The time-dependent O . 3.4 i
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h I j pressure and temperature profiles are included in Appendix C Figures 2 and 3, l respectively. ! The following considerations were included in the analysis of post-LOCA temperature and pressure conditions: , 1. 'Ihe worst case single failure
- 2. Loss of offsite power as required
- 3. Maximum containment operating temperature
- 4. Heat load effects.
Environmental conditions inside primary containment have been evaluated for 180 days post-accident. The original analysis conducted to determine the post-accident conditions l i extended only 11.6 days post-accident. As a result, it was necessary to evaluate con-tainment conditions from 11.6 to 180 days. The pressure curve was conservatively
- assumed to remain constant after 11.6 days. A plant-specific analysis was conducted to
! determine the temperature from 11.6 to 180 days. The analysis assumed that the drywell temperature varies directly with the suppression pool temperature. I The relative humidity inside primary containment is assumed to remain at 100% for 180. days. 4 Temperature and Pressure Conditions Outside Primary Containment ) Temperature, pressure, and humidity conditions resulting from a LOCA or HELB outside of the primary containment have been evaluated for the reactor enclosure. Table 1 in 4 Appendix C provides the extremes resulting from the spectrum of accident conditions for i each of the rooms in the reactor enclosure.- The time 4 pendent temperature profile for the reactor enclosure following a LOCA is Figure 4 of Appendix C. The profile was determined by reviewing the most limiting
- occurrences following a pipe break. The following considerations were included in the LOCA analysis
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- 1. Maximum normal reactor enclosure temperature
- 2. Outdoor air temperature
- 3. Building heat sink
- 4. Equipment heat load
- 5. Operation of safeguard equipment
- 6. Loss of offsito power
- 7. 'the worst case single failure
- 8. Solar heat loading
- 9. Primary containment heat load
- 10. Temperature distribution
- 11. Cooling effects of various systems operations.
Relative humidity in the reactor enclosure was conservatively assumed to be 90% for 180 days following a LOCA. The temperature profile following a HELB for the isolation valve compartment is Figure 5 of Appendix C. The isolation valve compartment is the only compartment in the reactor enclosure which contains equipment required to operate in order to provide long- . term containment cooling and shutdown cooling following a HELB in that compartment. j Other reactor enclosure compartments contain equipment required for short-term opera-
- tion to limit the effects of the HELB (i.e., steam isolation dampers, containment isolation valves). However, the safety functions of this equipment will be completed
- once the blowdown has ceased. Equipment in this category is qualified to the peak -l temperature and pressure values given in Table 1 in Appendix C for the required dura-
' tion. I,
- Temperature and pressure conditions in the reactor enclosure were determined by reviewing the mo?.t limiting occurrences following a high energy line break. The following considerations were included in the HELB analysis
- 1. Loss of offsite power if a trip of the Turbine Generator System or Reactor Protection System is a direct consequence of the postulated piping fallare ;
- 2. The worst case single failure O
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J' i O 3. Maximum normal operating temperatures 4
- 4. Outside air temperatures
]. ] 5. Restoration of normal ventilation. I The equipment within the compartment in which the HELB was postulated to occur has been conservatively considered to be subject to an atmosphere of 100% relative humidity l until normal ventilation is restored. When offsite power is available and when access is i available to reset the steam flooding dampers which were tripped, the humid air in the 4 compartment will be dispersed by the normal ventilation system. 'Ihe relative humidity is assumed to increase only in the compartment containing the HELB because all com-partments subject to steam flooding from HELB's are protected by redundant steam 1 j flooding dampers at au HVAC supply and exhaust openings. These compartments have '
- steam tight boundaries.
Radiation ! Post-LOCA radiation doses were calculated in accordance with NUREG-0737 using i j source terms specified in NUREG-0737 Item II.B.2 and NUREG-0588. 4 The following release fractions were used as a basis for determining the concentrations j for the radiation dose calculations: j 4 } Containment atmosphere: 100% noble gases,25% halogens { Depressurized Reactor Liquid: 50% halogens,1% solids i Suppression poolliquid: 50% halogens,1% solids. )i- For components inside primary containment, the total integrated gamma doses were calculated by adding the post-LOCA primary containment cloud dose to the 40-year normal operating dose. i
- Total Integrated Doses (TID) and dose rates for the primary containment are provided in a Table 1 of Appendix C.
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f For compartments in the secondary containment, the post-LOCA gamma radiation levels were conservatively calculated by adding the maximum piping contact dose in that
- compartment to the secondary containment cloud dose. Equipment-specific doses were calculated on as-required bases accounting for distance and spatial relationships. The total integrated gamma dose was then determined by adding the post-LOCA integrated dose to the normal operating integrated dose.
l Secondary containment piping doses were calculated based on the radionuclide concentrations present in piping and components for the following systems: i
- 1. Core Spray System
- 2. HPCI System
- 3. RCIC System
- 4. RHR System ;
- 5. CRD Hydraulic System
- 6. RWCU System
- 7. Gaseous Radwaste System
- 8. Post-Accident Sampling System
- 9. Recombiner System !
- 10. Reactor Enclosure Recirculation System j 11. Standby Gas Treatment System.
i , For piping system calculations, appropriate dilution volumes, system design, operating { modes were considered in accordance with NUREG-0737 Item II.B.2. For calculation of radiation doses for the secondary contalment atmosphere, the Reactor Enclosure Recirculation System (RERS) filters, and the Standby Gas Treatment System (SGTS) filters, the primary containment design leak rate was assumed, together with I consideration of RERS and SGTS design and operating modes, in accordance with NUREG-0737 Item II B.2. j Beta doses were also calculated for the primary and secondary containment. The doses were calculated by assuming that 100% of the core noble gas inventory,50% of the core halogen inventory, and 1% of the core solid fission product inventory are released. The
. beta doses and dose rates were calculated assuming an infinite cloud geometry.
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1 i The TID's and dose rates for the reactor enclosure are in Table 1 of Appendix C. 1 4 The Radiation doses resulting from HELB's are bounded by the LOCA TID. Non-DBA event, e.g., HELB, radiation dose reduction factors that can be applied to the existing LOCA radiation doses have been determined based on the non-DBA source terms pro-j vided in NUREG-0588, Section 1.4(1). Additional radiation dose reduction factors to j account for dose attenuation due to distance, radioactive piping "deadlegs," event dura-i tion and other event-specific parameters can be determined and applied on a case-by-i case basis. > Seismic and Hydrodynamic ~ Dynamic qualification of equipment due to seismic and hydrodynamic loads from SRV and
- LOCA willbe addressed in FSAR Section 3.10 and DAR Section 7.1.7.
i e i Submergence Submergence of equipment outside containment may be caused by either a HELB or a l Moderate Energy Line Break (MELB). The impact of submergence was determined as { part of the Separation Review Program (SRP). The SRP ensures that the reactors can be i shut down and maintained in a safe shutdown condition in the event of a postulated l ruptures of a pipe, a non-pipe break generated missile, or a fire. With respect to i submergence, analyses were performed for those compartments which have a potential for flooding to determine the flood elevations. Chapter 5 of the Fire Protection Evalua-tion Report (FPER) lists the equipment in each fire zone, many of which are susceptible j to submergence. Based on a loss of all susceptible equipment in a given compartment i i and postulating the worst case single active failure, safe shutdown flowcharts were
! reviewed to determine that safe shutdown paths remain. In the cases where the loss of l susceptible equipment coincident with the single active failure cause the loss of all
] shutdown paths, appropriate protective actions are taken to quellfy the equipment for j submergence or to relocate the equipment. The Equipment Qualification Review Record
- (Appendix E) for each electrical component indicates if the component is qualified for l submergence or if qualification for submergence is not applicable.
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O Containment Spray Limerick has the capability of demineralized water spray actuation to mitigate the effects of a LOCA. Therefore, the effects of spray (i.e. spray impingement, dripping) on equipment important to safety are evaluated. I i O : 1 i O 3.10 1
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j (A 4 4.0 QUALIFICATION TESTING AND ANALYSIS OF EQUIPMENT All qualification testing and analysis of electrical equipment important to safety are being evaluated for compliance with the Category II NUREG-0588 guidelines. Equipment testing is reviewed to determine the extent to which it simulates plant conditions and provides sufficient margin. Factors considered during the review of testing include test procedure, test set-up, test sequence, margin and test anomalies. i Supplemental analyses (i.e., beta shielding, thermal degradation) are performed, as required, to support qualification. All analyses based on partial test data are completed using approved methodologies with adequate justification. Equipment-specific analyses are contained in the EQ file along with the appropriate justification. O a i
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5.0 METHODOLOGY FOR EVALUATING ENVIRONMENTAL QUALIFICATION SERVICE CONDITIONS Electrical equipment important to safety is evaluated by comparing demonstrated environmental conditions with required conditions. This evaluation includes review for both 40-year normal environments and accident environments resulting from a spectrum l of LOCA's and HELB's. The equipment qualification documentation is considered acceptable when it is demonstrated that the equipment can perform its required safety
- function under the postulated environmental conditions.
l PECo assembles, evaluates, and reviews equipment qualification documentation per PECo Electrical Engineering Procedure (UDP) EE-SES-2. An Equipment Qualification j Review Record (EQRR) is completed for each electrical component important to safety !. requiring EQ. The EQRR form with a description of its entries is provided in Appendix i j D. i i i The EQRR's demonstrate that each required parameter is enveloped by the qualified values. Additionally, the EQRR's provide the equipment's description, function, interfaces, maintenance requirements and any corrective actions required to achieve qualification. Appendix E contains the EQRR's sorted alphanumerically by system. 1 l l LO 5.1 , . l
4 6.0 CORRECTIVE ACTION PLANS ; Corrective action plans have been developed for all equipment whose documentation does not support qualification. The following corrective action plans have been developed for equipment following assessment of its qualification deficiency:
- 1. Replace equipment with quallfled equipment (Category I, NUREG-0588),
- 2. Partially retest equipment in accordance with NUREG-0588, Category II, or
- 3. Relocate equipment to a less severe environmental zone for which equipment qualification can be demonstrated.
Corrective action plans are identified on the EQRR for all equipment with qualification deficiencies. Corrective action plans are expected to be completed prior to fuel load. In the event O that completion of some actions plans are delayed, justification for interim operation will be provided. O 6.1 L
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,i t l 4 7.0 JUSTIFICATION FOR INTERIM OPERATION ~ Justification for interim operation will be provided for all equipment whose qualification can not be demonstrated prior to fuel load. Analyses will be performed to ensure that
- failum of the equipment will not impact the prescribed safety functions, affect in a I detrimental way other safety equipment or functions, or mislead an operator into taking j an action that could adversely alter the course of the accident.
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_~. -_ ._ _~ ._ . ___ . __ _ _ __ __ _ _ _ - _ _ _- . - - . - - i i ! 1 ' I 8.0 M AINTENANCE/ SURVEILLANCE PROGRAM A maintenance and surveillance program is being developed by PECo to ensure the continued environmental qualification of equipment during plant operation. The objectives of this maintenance and surveillance program are to ensure that the qualified equipment will perform its intended function in the environment in which it is expected to operate and to maintain retrievable records. The list of environmentally quallfled equipment identifies equipment to be included in l the maintenance and surveillance program. The list will be kept current to include j mechanical equipment and ensure that equipment added to the plant because of design } modifications is incorporated into the qualification program and the maintenance and
! surveillance program.
For each piece of equipment, a maintenance and surveillance program is being developed { based on information such as requirements resulting from the equipment qualification I report, manufacturers' recommendations,' material analyses, previous experience with i similar equipment, etc. The qualification-specific requirements are identified on the individual EQRR forms for each piece of equipment. 'The initially developed main-l tenance and surveillance programs will be modined during plant life if additional infor ' mation such as corrective maintenance frequency, surveillance testing, and Industry experience (e.g., NRC information notices, circulars or bulletins, manufacturers' alert, i LER's, reliability data bases, etc.) identifies any unanticipated degradation trends. In addition, the maintenance and surveillance program identifies the lubricants suitable for j- eac't application and environment. 'these maintenance and surveillance activities are performed by trained personnel using detailed procedures, as necessary. Spare and ! replacement parts are discussed in Section 9.0. The plant maintenance program willbe computerized to efficiently handle scheduling and documentation of maintenance requirements and activities. Periodic computer schedules will identify when equipment maintenance, replacement, testing, or calibration is required. Appropriate plant departments will complete the work. On completion of scheduled activities, a documented notification will be made indicating work completion which will then be entered into the computer to document completion and facilitate 8.1 4
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1 i i t I rescheduling. This computerized scheduling program will be used to alert appropriate :
- plant departments of preventive maintenance, surveillance, and replacement require-ments for environmentally qualified equipment.
Quality assurance and control programs will require inspections, verifications, and audits of activities and procedures important to safety. 'Ihese will be performed on environ-mentally qualified equipment to ensure that schedules, maintenance, proceoures,
- replacements, and documentation are completed in a correct and timely manner.
l The maintenance and surveillance program will ha consistent with NRC requirements and ! i will be implemented at the time of fuelload. ! 1 ; iO i i I i ! i i I 1 l l 1 i i I i 8.2 p g -"r me , **-v<- g e-g-,o= yw - ---ar m*------ri -. -ws'- gs+ u-w, y g - ara-* m *- + t e v -t w v*T tYwe M**sme-p"*-t--- ---?-m---P v wt ev'M*va vv"' M-"e=* "' f
9.0 REPLACEMENT PARTS PROGRAM For the purpose of this discussion the following definitions are provided: Equipment A product that is manufactured Device A piece of electrical or electronic equipment that has been qualified as a unit by test or analysis Components items from which a device is assembled (e.g., resistors,
- capacitors, wires, connectors, transistors, tubes, switches,
. springs, etc.)
l i Assembly Two or more components sharing a common mounting or support structure t Module Any assembly of interconneated components which constitutes I an identifiable unit. A module can Se disconnected, removed , as a unit, and replaced with a spare. It has definable [ performance characteristics which permit it to be tested as a . 2 unit. A module can be a card or other subassembly. Replacement components, assemblies, and modules for equipment important to safety ) are being ordered to meet the environmental requirements of original specifications or to the environmental conditions found necessary as a result of this program. A certificate of conformance is considered sufficient documentation to support qualification for , component, assembly, and module replacement parts which are in-kind replacements for
- the originally supplied equipment. However, if in-kind replacement parts are not
! available, the effect of the new part on the environmentalqualification of the equipment will be evaluated. Supplemental documentation will be included in the EQ file as appro-l priate. G 9.1
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4 t l For those equipment items important to safety upon which maintenance activities are ! normally performed by the replacement of complete devices, replacement devices will be ! i l d procured to NUREG-0588 Category I effective on the date of commercial operation l i i unless juctification for not procuring to this level is documented. i I l Spare equipment used to facilitate plant maintenance, such as transmitters, will be [ j evaluated to the generic requirements for its worst case potential application per j NUREG4588 Category II.
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r 10.0 EQRR REFERENCE LIST l 8
'x ,,/ Ref. No. Title 1 Bechtel Specification 8031-M-171 Rev. 1 " Specification for Environmental Qualification Service Conditions."
5 Electrical Calculation #6300 E20 Rev. 3 " Voltage Regulation Study." 7 Vendor Print 8031-E-53-Q3-1-2, NTS Analysis Report No. 528-1132, Rev. A, dated 5/10/83 " Nuclear Environmental Qualification of Twenty-Six (26) 480-Volt AC Motor Control Center for the LGS." 8 Vendor Print 8031-E-40-42-2 " Design Qualification for Electric Penetration Assemblies - Report No. IPS-269.1 dated 6/23/81 by Conax Corporation." l 9 Vendor Prints: l 8031-E-28-B-47-2: Rockbestos Report No. QR1801
" Qualification of Firewall III Class 1R Electric Cables Chemically Cross-Linked with Factory Insulation Rework" dated 5/18/82.
i 8031-E-28B-48-2 Rockbestos Report No. QR1802. l (~') 8031-E-31A-17-2 " Qualification of Firewall III Class 1E 8031-E-31B-45-2
\ ,) Electric Cables Irradiation Cross-Linked Insulation with Factory Insulation Rework (Instrument Cable)" dated $/18/82.
i 10 Vendor Prints: ! 8031-E-28B-70-1 Rockbestos Report No OR1812R l 8031-E-31A-22-1 " Qualification of Firewall III Class lE 8031-E-31B-49-1 Instrumentation and Control Cables f Containing Factory Splices and KXL420 ( l Rework" dated 6/24/82. 12 Vendor Prints: 8031-M-608-31-4 In seco Qualification Plan 17173-1 8031-M-60B-31-5S Qu, ification Plan 17173-1 Addendum 8031-M-60B-66-1 CCL Qualification Report A-575-83 13
- 15 LGS FSAR Table 3.11-2.
20 Vendor Prints: 8031-E-28B-68-3 Rockbestos Report No. QR1806R 8031-E-31A-20-3 " Qualification of Firewall III Class 1E 8031-E-31B-47-3 Electric Cables (Irradiation Cross-Linked Insulation)," dated 5/18/82.
*See Reference 85 10.1
I i Ref. No. Titl7 l l~\sOj
'21 Vendor print 8031-E-29-2-5 " Anaconda's Results of Cable Tests and Qualification Tests per Specification No. 8031-E-29 for
! 5 kV-and 15 kV-power cables for Limerick Generating Station" j dated 8/18/80. l 22 Vendor Prints: 8031-E-285-72-1 Rockbestos Technical Report TS1982-YJK-2 l 8031-E-31A-24-1 " Analysis of Beta-Radiation Effect," ; i 8031-E-318-52-1 dated 5/82. 8031-E-288-72-2 Aupplement to Rockbestos Technical Report ! 8031-E-31A-24-2 TS1982-YJK-2, dated 6/28/82. ! 8031-E-318-52-2 27 ** 29 ** 30 ** 36 Vendor Prints: 8031-M-123-394-4 Reliance Electric Company Summary Report NUC-9 " Nuclear Power Motor Systems Typ0 Test Support Analysis Random Wound Motors," dated 7/1/78 Reliance Electric Company Supplemental Report to NUC-9 Rev. I dated 4/14/80.
- Reliance Electric Company Supplement to Report NUC-9 for Arizona Nuclear Power Project Palo Verde and Georgia Power Company Plant Vogtle, dated 7/7/80, 8031-M-123-394-58 Reliance Electric Company Supplemental Report to NUC-9 Rev. 2, l
i dated 7/15/81. l 8031-M-123-322-11 Installation, operation, and maintenance ! instructions for fan cabinets. l 37 Vendor Print 8031-E-31A-19-2, Rockbestos Report No. QR #2805
" Qualification of Firewall III Class 1E Electric Cables
) (Irradiation Cross-Linked Insulation with 20 mil Insulation Wall)" dated 3/15/82.
**See Reference 78 V
10.2
Lof. No. Titlq 38 Vendor Prints: 8031-E-28A-1-2 Anaconda Co. Results of Qualification Tests per Specification 8031-E-28 (Rev. 10 for 600 V Power, Control and Instrumentation Caole, dated 3/25/80. 8031-E-20A-4-1 FIRL Final Report F-C4350-3, July 1976 Test of Electrical Cables Subjected to Thermal Aging, Gamma Radiation and Loss-of-Coolant-Accident Simulation. 40 Bechtel Specification 8031-E-28 Rev. 16 "600 Volt Power, Control and Instrumentation Cable." 41 Vendor Print 8031-M-1-A61-4010-L-4.3, GE 22A4947 Rev. 2 "Special Wire and Cable." 42 Vendor Print 8031-E-31B-41-4 Rockbestos Report No. QR #2806, dated 4/23/82 " Report on Qualification Tests for Second Generation Solid Dielectric Coaxial Construction and Cellular Dielectric Coaxial Construction." 47 Vendor Prints: I 8031-M-123-395-3 Joy Manufacturing Co. Report No. X-604
" Qualification Testing of Joy Axivane Fan and Reliance Electric Motor for I
Class I Service for Nuclear Containment per IEEE 334-1974" dated 3/20/80. 8031-M-123-322-11 Installation, operation, and maintenance instructions for fan cabinets. 48 Vendor Print 8031-M-164-40-2 Westinghouse MM-9112, dated
- 1/18/80 "Qualificati(n Document - Class 1E Medium A.C. Motors l (outside containment) ."
49 Bechtel General Specification 8031-G-10 Rev. 9, " General Project Requirements for Integral and Fractional Horsepower Induction Motors." 50 Vendor Prints: 8031-M-245-14-4 TRP 2375 - Rev. A Qualification Test Report, Aging, Seismic and Accident Simulation Test of Target Rock Corporation 1: Solenoid Valve, Model 77CC-001 (modified per SK4017). TRP 2302 - Rev. C Qualification Test Report, Aging, Seismic and Accident Simulation Test 1: Solenoid valve, Model 76HH-002. f% J 10.3 1 i k-( _ _ _ _ . _
Ref. No. Title X, I i CA,,) TRC-SK1062 Rev. A - Electrical Assembly.
-Valve Comparison Chart, 76EE Series.
8031-M-245-93-1 TRC-3727 DBA Humidity Values and Valve applicability agreement. 52 LGS FSAR Table 6.2-17 " Containment Penetration Data." 53 ** 55 Vendor Print 8031-E-24-2-2 Limitorque Valve Actuators dated 3/10/81. 56 Vendor Print 8031-E-24-3-1 Limitorque Report #B0003 dated 6/7/76 " Qualification Type Test Report for Limitorque Valve Actuators for Class lE Service Outside Frimary Containment." 57 Vendor Print 8031-E-24-1-1 Limitorque Report #B0009, dated 4/30/76 " Qualification Type Test Report for Limitorque dc J Valve Actuators for BWR Service." 58 Vendor-Print 8031-E-24-4-1 Limitorque. Project #600376A, dated 5/13/76 " Qualification Type Test Report for Limitorque Valve Actuators for BWR Service."
\s ,/ 59 Regulatory Guide 1.9 Rev. 2 December 1979 " Selection of Diesel Generator Set Capacity for Standby Power Supplies."
2 60 Document Control No. 116009 " LGS Auxiliary Electrial System Voltage Regulation Study" dated 12/24/81. 63 Bechtel General Specification 8031-G-ll, Rev. 13. " General Project Requirementh for Valve Motor Operators." 64 Bechtel General Specification 8031-G-12, Rev. 14. " General Project Requirements for Standard Instruments, Controls, and Local Control Boards Supplied with Station Equipment.- 65 ** 66 ** l 67 ** . l 68 ** 69 Vendor Print 8031-M-70-127-4, Paul Munroe Hydraulic,.Inc. Qualification Report PA86231 with Appendices and. Supplementary data.
' (,_j **See Reference.78
!' .-10.4
~ . .
i-Raf. No. Title 71 Electrical Calculation 6407E.09 Rev. 5 " Cable Sizing.125/250 Volt DC System." i , 72 Bechtel Specification 8031-E-17 Rev. 4 Section 6. " Battery Chargers" Design and Construction Details. 73 Document Control No. 117443. C&D Batteries letter to Bechtel, dated 1/15/82 " Cell Volts for Items 1, 2A, 3A and 5." 74 ** t , ~76 ** 4 78 Bechtel General Specification 8031-G-18 Rev. 6 " General Project Requirements for Environmental Qualification of Class lE Equipment Located in Harsh Environments." i 79 Mechanical Calculation #M-76-42 Rev. O dated 2/16/82.
" Environmental Conditions for RM202 Pipe Tunnel."-
82 Vendor Prints: 8031-E-28B-71-1 The Rockbestos Instruments Accuracy , 8031-E-31A-23-1 Document. 8031-E-31B-51-1 83 Vendor Prints:
.(
8031- F-E-3-1-1 FRC Final Report F-C5205-3 " Qualification Test Program for Terminal Blocks for Weidmuller." 8031-F-E-3-2-1 Wyle Report No. 58687, dated 6/29/82 Loss-of-Coolant Accident Testing of Five Weidmuller Terminal Blocks." 84 Vendor Prints: 8031-F-E-4-1-1 Amp Qualification Report 110-11004, Released 2-2-82.- 8031-F-E-4-2-1 Amp Engineering Evaluation Report EER-35. 8031-F-E-4-3-1 Amp Catalog Information " Design Properties"_ of KYNAR insulation. 85 Bechtel Specification 8031-M-171 Rev. 1 " Specification ~for r Environmental Qualification Service Conditions."' 86 Vendor Prints: I 8031-M-70-101-2S Bettis Nuclear Qualification Test Report. ' No. 37274 (incomplete) with Appendix FS-C: ASCO Test Report Appendix FS-D: NAMCO EA-790 Test Report. 8031-M-70-101-4S Bettis Nuclear Qualification Test Report l 8031-P-144-58-1 No. 37274 (incomplete) .
**See Reference 78 10.5 I m: ., ._ -- - - - , __ . - _ - . - . - 2_m .--- _ _. .
Ref. No.~ Title 8031-M-70-101-6S Bettis letter dated 2/7/83. 8031-P-144-58-2S 8031-M-70-7S NAMCO letter dated 2/7/83. 87 Vendor Print 8031-F-E-6-1-1 Qualification Test Report for Buchanan Terminal and Fuse Blocks. 93 Vendor Print 8031-F-E-1-1-1 "Markel Braided Fibergalss Sleeving." 94 Vender Print 8031-F-E-2-4-1 "EQ Test Report for Raychem i WCSF-N Nuclear In-Line Cable Splice Assemblies for Raychem
, Corp."
95 Vendor Print 8031-F-E-2-2-1 Raychem Report #RDR 2001 dated l 8/10/78 " Heat Aging Study of WCSF Compound." ' 97 Vendor Print 8031-M-203-31-1 " Test Report Class 1E Design Qualification Testing of Analog High Range ' Radiation Monitor (RD-23, RP-2C, RP-23 and RP-20-01) dated 12/15/80. 103 Vendor Print 8031-M-66-185-6 " Environmental Qualification Test Report on the Alison Fire Detection / Extinguishment System Report #377-82.026, Rev. O." 104 Vendor Print 8031-M-242-1-28-1 Limitorque Report-#B0003, dated 6/7/76 " Qualification Type Test Report for Limitorque Valve Actuators for Class 1E Service Outside Primary Containment." 4 105 Vendor Print 8031-M-66-217-2 MCC Powers Report #377-81-13-A j Rev. 3 dated 3/4/83 " Environmental Qualification Test Report .! on the MINCO Duct Mounted RTD Series S9322 for LGS." 106 Vendor Print 8031-M-69C-89-1, Reliance Electric Company Engineering Report " Nuclear Power Motor Systems Support-Analysis Class H Insulation Qualified Life for 4824-RY , Insulation, April 28, 1983 for' Joy-Bechtel S/O 1XF-882464." 107- Vendor Print 8031-M-31B-50-1 Rockbestos Technical Report TS-YJK-3 dated June, 1982 "Bechtel/SF Questions on COAX-Application." 108 Document Control No. 131919, Letter from Rockbestos to Bechtel dated 7/28/82 " Class 1E-Qualification of 600 Volt Rated with 20 Mils of Insulation." v. 10.6
, m .- -- -. , ,m,.-- ,- -_, - .
Rif. No. Title-
,_ . 110 Bechtel Specification 8031-E-13 Rev. 6, Section 6.1 " Batteries Types and Ratings."
113 Vendor Print 8031-F-E-5-6-1 AMP Inc. Engineering Test Report 110-11506 (released 12/12, reissued it /1/78) . Amp Lugs, EQRR 194. + 114 Vendor Print 8031-M-206-22-1 "Rosemount Qualification Test Report 108025, Rev. A." 115 Vendor Print 8031-M-235-37-1 "Comsip Delphi, Inc. H -0 2 2 Analyzer Test Plan and Report." + 116 Letter Joy to AAF, dated 8/7/79 - Enclosure to letter AAF to .; BPC dated 8/23/79, Document Control No. 06910. 117 Vendor Print 8031-M-69C-28-3S Reliance Electric Co. Instruc-tional Manual B-3645 - Duty Master Nuclear Service Class 1E Integral Horsepower Induction Motors December 1977. 119 Vendor Prints: 8031-M-70-101-5S ASCO Qualification Report No. AQR-67368 8031-P-144-67-1 Rev. O " Report on Qualification of ASCO DC #154711 Catalog NP-1 Solenoid Valves." j 120 Document Control #148279 " Lewis Control Systema Qualification 4 s_ Test of Sample Pump and Selected Pump Components under Simulated LOCA while Operational." 121 Bechtel Specification 8031-359 Rev. 1 " Valve Air Operator." 3 j 122 Vendor Print 8031-M-267-1 Vol._I, "NTS Report #548-8854-2 Rev. B Vol. 1 of 3 for Weed Instrument Co." 123 Calculation No. EQ-2, Rev. 3, Sh', 13E and 73B " Radiation Dose Calculation for H -0 Analyzer" f r P.O. #8031-M-235. 2 2 . 124 Electrical Calculation #6470E24 " Voltage Regulation." 125 Vendor Prints: 8031-M-364-1 ~" Qualification for NAMCO Control Switches ' Model EA-180" dated 3/3/78. 8031-M-113-364-5S - NAMCO Estimation of Qualified Life ci , ' Nuclear Switches" dated 4/26/79..
- 126- Vendor Prints
4 8031-F-E-9-1-1 Rockbestos Report QR #1806R dated 5/3/83
" Qualification of.Firewall III Class lE Electric Cables (Irradiation Cross-Linked Insulation)."
,,~
--(
v 10.7. 4 w + -- se - - 4 , . , .
Ref.'No. Titla 8031-F-E-9-2-1 Rockbestos Report QR #1807R dated 5/3/83
" Qualification of Firewall III Class 1E Electric Cables (Chemically Cross-Linked
. Insulation)." 127 Vendor Prints: 8031-M-ll3-364-3S NAMCO Report No. QTR105 dated 8/28/80 8031-P-144-72-1 " Qualification of EA180 Series Limit DC #154710 Switches." 128 Vendor Print 8031-E-24-6-1 Limitorque Addendum A to Report
#B0003 Rev. C dated 10/15/79.
129 Vendor Print 8031-E-24-8-1 Limitorque Addendum A to Report
#B0009 Rev. C dated 10/16/79.
130 Vendor Print 8031-E-24-9-1 Limitorque Addendum A to Project
#600376A Rev. B dated 1/23/79.
131 Vendor Prints: 8031-F-E-7-1-1 Conax Report ISP-713 dated 4/30/81
" Electric Conductor Seal Assembly Quali-fication Report."
8031-F-E-7-2-1 Conax Report IPS-725 Rev. A dated 12/2/81 () (_/
" Installation Manual for Electric Conductor Seal Assemblies with Long Body."
132 Vendor Print 8031-F-E-7-3-1 Conax Report IPS-409.1 dated 2/25/82 " Addendum to Design Qualification Report IPS-409 for Electric Conductor Seal Assemblies (ECSAs). j 133 Document Control No. 150520 dated 3/21/83 TWX from Conax to a Bechtel " Addendum to Conax Report IPS-409.1." 134 Vendor Print 8031-M-113-331-1 and 2S " Nuclear Qualification Report for NAMCO EA-740 Limit Switches NAMCO Report QTR-lli Rev. O." 135 Vednor Print 8031-E-33D-15-5 " Testing Report for P.O.
#8031-E-33D-AC."
136 Bechtel Specification 8031-M-203 Rev. U " Process / Airborne Radiation Monitoring Systems." 137 Document Control No. 154713 NAMCO Test Report No. QTR-107, Rev. O dated 3/11/83 " Qualification of EA170 Series Limit Switches." e \
/
lc.8
'Ref. No. Title
(_,/. 138 Document Control No. 154712 ASCO Test Report No. AQS-21678/TR Rev. A dated July 1979 " Report on Qualification of ASCO Catalog NP-1 Solenoid Valves." 139 Vendor Print 8031-E-7-447-4, BBC Report No. 33-55112-QSA Rev. 3, dated 5/17/83 " Class 1E Electrical Equipment Environ-mental Qualification Report." 140 Bechtel Calculation #2006 " Compartment Pressurization Due to Pipe Breaks in the Reactor Enclosure" Rev. 2. 142 Vendor Prints: 1 8031-M-113-6-2S ITT Report No. 721.77.095 "NH90 Quali-fication Report." 8031-M-113-6-3S ITT Report No. 721.77.095, Addendum #4 "HN91 and 95 Series Actuators Model B-92VAC/60HZ Input Power Tests-Summary i and Conclusion." 8031-M-113-6-4S ITT Engineering Data and Qualification Reports. 8031-M-113-6-6S ITT Qualification Reports. 8031-M-113-6-7S " Limerick ITT Model Nos." AWV Transmittal j s dated 5/2/83. 8031-M-113-6-8S Mobil Oil Co. letter to Bechtel, dated 5/6/83 " Thermal Stability of Mobil ] SHC824 011." 8031-M-113-6-9S Gulf Radiation Technology Report GULF-RT-C12494, 1/25/73 Amended 3/75
" Radiation Testing of a Hydroametor Actuator."
8031-M-113-263-2 "ITT Actuator Material and Processes l Certification". dated 2/15/79. 147 Vendor Print #F-E-12-1-1 FRC-F-C5022-1 Term. Blk. Qual. Test. 500 GE Letter T-4793 Design Report-Anticipated Transient Without Scram (ATWS) BOP Information Spec. 22A8465. 501 FSAR Section 5.4.1.1.1 Reactor Coolant System and Connected - Systems, Design Basis, Residual Heat Removal Mode (Shutdown Cooling Mode).
- /~~T - ,
\.-) :
.. .I H
10.9 i e l
~
Ref. No. Title (N '(,,) 502 FSAR Section 5.4.7.1.2 Reactor Coolant System and Connected Systems, Design Basis, Design Basis for Isolation of RHR from Reactor Coolant System. 503 FSAR Section 5.4.7.1.2 Reactor Coolant System and Connected Systems, Deisgn, Basis, Design Basis for Reliability and Operability. 504 FSAR Section 5.4.7.2.2 Reactor Coolant System and Connected Systems, System Design, Equipment and Component Description. 505 FSAR Section 5.4.7.2.6 Reactor Coolant System and Connected Systems, System Design, Manual Action. 506 FSAR Section 5.4.8 Reactor Coolant System and Connected Systems, Reactor Water Cleanup (RWCU) System. 507 FSAR Section 6.2.3.2.3 Engineered Safety Features, System Design, Containment Bypass Leakage. 508 FSAR Section 6.2.3.2.3.1 Engineered Safety Features, System Design Water Seals. 509 FSAR Section 6.2.4.3.1.3.1.5 Engineered Safety Features, Design Evaluation, RHR, RCIC, CS, and HPCI Pump Suction Lines.
\s ,- 510 FSAR Section 6.2.4.3.1.2.2.1 Engineered Safety Features, Design Evaluation, Main Steam, RCIC, and HPCI Steam Lines, and RHR Shutdown Cooling Supply Line.
511 FSAR Section 6.2.4.3.1.3.1.1 Engineered Safety Features, Design Evaluation, CS, HPCI, and RHR Test Lines and Minimum-Flow Bypass Lines. 512 .FSAR Section 6.2.4.3.1.3.1.4 Engineered Safety F.eatures, Design Evaluation, HPCI Turbine Exhaust Line. 513 FSAR Section 6.2.4.3.1.3.2.4 Engineered Safety Features, Design Evaluation, RCIC and HPCI Turbine' Exhaust Vacuum Breaker Lines.
~514 FSAR Section 6.2.5.2.1 Engineered Safety Features, Combustible Gas Control In Containment, Containment Hydrogen Recombiner Subsystem.
515 FSAR Section 6.3.2.2.1 Engineered Safety Features, . Daergency Core Cooling Systems, Equipment and. Component Descriptions, High Pressure Ccolant Injection (HPCI) System.- ! 516 FSAR Section 6.3.2.2.3 Engineered Safety Features, Emergency l Core Cooling Systems, Equipment and Component Descriptions, ( V} Core Spray (CS) System. l { 10.10l
Rsf. No. Title
.g k,_) .517- FSAR Section 6.3.2.2.4 Engineered Safety Features, Equipment and Component Descriptions, Low Pressure Coolant Injection System.
518 FSAR Table 6.2-25 ESF Containment Penetrations Compliance with 10CFR Part 50, Appendix J. 519 FSAR Table 6.2-26 ESF Remotely Actuated Valves Required for Post-Accident System Isolation. 520 FSAR Table 6.2-27 ESF Essential / Nonessential Systems. 521 FSAR Section 9.2 Auxiliary Systems, Water Systems.
. 522 FSAR Section 9.2.3.2 Auxiliary Systems, System Description.
523 FSAR Section 9.4.5.1 Auxiliary Systems, Containment Atmospheric Control (CAC) System. 524 FSAR Section 9.3.5 Auxiliary Systems, Standby Liquid Control System. 525 FSAR Section 10.4.7 Steam and Power Conversion System, Condensate and Feedwater Systems.
) 526 FSAR Section 10.4.7.2.2 Steam and Power Conversion Systems,
- %s System Description, Feedwater System.
527 FSAR Section 5.4.6.1 Reactor Coolant System and Connected Systems, Reactor Core Isolation Cooling System Design Bases. 528 FSAR Section 6.2.4.3.1.3.1.2 Engineered Safety Features, Design Evaluation, RCIC Turbine Exhaust, Vacuum Pump Discharge and RCIC Pump Minimum Flow Bypass Lines. 529 FSAR Section 7.4.1.1.3.1 Instrumentation and Control Systems, Systems required for Safe Shutdown, Reactor Core Isolation Cooling System, General. 530 BPC Memorandum (Document Control No. 154981) Radiation Dose for Rooms 502 and 576.- 532 FSAR Section 9.2.2.2 Water Systems, Engineering Service Water , System, System Description. 533 FSAR Section 6.5.1.1.2 Fission Product Removal and Control Systems, Standby Gas Treatment System, System Description. o 10.11
i Ref. No. Title
.( , 's._ / 534 FSAR Section 9.4.2.1.3 Heating, Ventilation, and Air Condi-tioning Systems, Reactor Enclosure and Refueling Area Ventilation Systems, Safety Evaluation.
535 Vendor Print 8031-M-70-101-7S NAMCO Report for EA 740, Drawing No. EA 749-20010. Limit Switches, EQRRs 145, 142. 536 FSAR Section 9.3.1.3.2 Process Auxiliaries, Primary Contain-ment Instrument Gas System, System Description. 537 FSAR Section 6.2. 538 FSAR Section 9.2.2.3 Water' Systems, Emergency Service Water System, Safety Evaluation. i . 540 Vendor Print 8031-M-206-26-1 Rosemount EQRR 1 (needs further details). 544 FSAR Section 9.4.2.2.1 Heating Ventilation, and Air Condi-tioning Systems, Reactor Enclo.ure and Refueling Area Ventilation Systems, Safety-Related Reactor unclosure Air Cooling System, Design Basis. 545 FSAR Section 9.4.1.5.1 Heating, Ventilation, and Air Condi-a tioning Sytems, Control Room and Control Structure Ventilation
/~'N Systems, SGTS Equipment Compartment HVAC Systems, Safety Evaluation.
546 FSAR Section 9.4.5.2.3 Heating, Ventilation, and Air Condi-tioning Systems, Primary Containment Ventilation System, Dry-well Air Cooling System, Design Basis. 547 FSAR Section 6.5.1.3.2 Engineered Safety Features,. Fission Product Removal and Control Systems, Reactor Enclosure Recirculation System Filter Units, System Description. 548 FSAR Section 9.4.2.1.1 Heating, Ventilation, and Air Conditioning Systems, Reactor Enclosure and Refueling Area Ventilation Systems, Design Bases. 549 FSAR Section 6.2.5.2.2 Engineered Safety Features, Combustible Gas Control in Containment, Combustible Gas Analyzer Subsystem. 550 FSAR Section 9.3.1.3.3 Process Auxiliaries, Compressed Air and Gas Systems, Primary Containment Instrument Gas: System, Safety Evaluation. 600- BPC EQG Calculation E-960-1 Rev. O dated 3/29/83. NAMCO Limit Switches, models EA180 and EA740, EQRR 150. 601 BPC EQG Calculation E-715-1 Rev. O dated 3/8/83. Weed RTDS, EQRR 179. O 10.12.
R7f. No. Titlt x,,/ 602 BPC EQG Review Notice 1084E, dated 6/1/83. Reliance Motor Temperature and Radiation Evaluation, EQRR 63. 603 BPC EQG Calculation E-1053-1 Rev. O dated 5/16/83. ITT Electro-Hydraulic Actuator, EQRR 149. 604 BPC EQG Calculation E-609-1 Rev. O dated 10/14/82. Rosemount Transmitters, EQRR 1. 605 BPC EQG Calculation E-856-2 EQRR 182 (needs further detail) . 606 BPC EQG Calculation 292 Part 3-3 dated 3/4/83. AMP Lugs, EQRR 194. f
, 607 BPC EQG Calculation E-712 Rev. O dated 1/11/83. Cutler Hammer MCCs, Champlain Cable, EQRR 16.
608 BPC EQG Calculation E-1057-1 Rev. O dated 7/15/83. Buchanan Terminal Blocks, EQRR 205.
- 609 BPC EQG Calculation E-965-1 Rev. O dated 3/29/83. ASCO NP-1 180 Days Post LOCA Requirements.
610 BPC EQG Calculation E-974-1 Rev. O dated 7/16/83. EQ Analysis for Elastimold Connectors. 611 PECO EQG Radiation Analysis Reference EPRI NP-1588, EQRR 58. i 612 BPC EQG Calculation E-109A-3 Rev. 1 dated 2/25/83. Limitorque Motor Operators, EQRRs 91, 92, 93, 96, 98, 99, 100, 101, 102, 103, 104, 105, 106, 109, 110, 111, 112, 115, 118, 120, 121, 123, 125, 127 and 207 613 BPC EQG Calculation E-557 (Part I)-2. Limitorque Motor Operators, EQRRs (Same as 612) 614 BPC EQG Calculation E-93A-2 Rev. O dated 3/29/83. Limitorque Motor.Operatores, EQRRs (Same as 613) 615 BPC EQG Calculation E-246 (Part 2)-1 Rev. 2 dated 3/22/83. Limitorque Motor Operators, EQRR 120. i 616 BPC EQG Calculation E-91-3 Rev. 1 dated 3/22/83. Limitorque Motor Operators, EQRRs 89, 90, 104, 120, 123, and 207. 617 BPC EQG Calculation E-1071-1 Rev. O dated 5/25/83. -Potter Brumfield Relay,. Littleman Fuse Holder, Bussman fuse, SIS l Wire, SSK Heater Cable, Cold Lead, and Thermocouple quali-fication EQRR 26. v 10.13
1 Ref. No. Titlo f' ( 618 BPC IOM 144933 dated 1/13/83 to W. C. McDaniel from D. T. DexSeimer. SGTS Heater temperature Detector (Thermal
- Cutouts) Radiation qualification, EQRR 184.
(19 BPC IOM 128730 dated 6/14/82 to W. C. McDaniel from D. T. Dexheimer. H2/02 Combustible Gas Analyzers Pump Motor Radiation Requirement, EQRR 59. 620 BPC EQG Calculation E-246 (Part 2)-1 Rev.1 dated 3/22/83. Limitorque Motor Operators, EQRR 120. 621 BPC EQG Calculation E-246 (Part 2)-1 Rev. I dated 3/22/83. Limitorque Motor Operators, EQRR 207. 700 BPC DCN 155779 Autcmatic Switch Company letter to BPC dated S/17/83. ASCO Pressure Differential Switch, EQRR 142. 701 Vendor Letters Westinghouse Electric dated 6/1/83 and 10/14/83, BPC Document Control Numbers 128881, and 138569, respectively. Safeguard Fill Pump Motors, EQRR 73. 800 Package 100; Rosemount Transmitters, 1151 Series: Report #37327B; Qualification of Differential Pressure Trans-mitters for General Electric, San Jose for Essential Service. O Report #127227; Nuclear Service Qualification Testing, Interim Report, Rosemount Incorporated Model 1151DP Differential Transmitter. 801 Package 200; Target Rock Corp. Report #2199; Report of Test on TRC Model 7567F S/R Valve Pneumatic Actuator Assembly. Report #2063C; Qualification Test Procedure " 3-way Solenoid Valve Assembly. Draft Technical Manual, Model 7567F. 802 Package 300; PYCO Temperature Elements Report #111275; Method of Measuring Air flow for Thermocouple - Response for PYCO. Report #122375; Report of Environmental Aging of Thermocouple Assemblies. 803 Package 400; Conax Explosive Trigger Assembly Report #TR-39; Environmental Qualification Test Report for Conax Valve P/N 1832-159-01. l 804 - Package 500; ECCS Pump Motor Report #NEDE-30125; Limerick 1 and 2, ECCS Motor Data Comparison with Qualification Data. 1 ()% 'w . 10.14
Ref. No. Title 805 Package 600; Ametek Flow Element Environmental Qualification Report for E32-N006B,F,K,P. 806 Package 700; Ametek Flow Transmitter Environmental Qualification Report for E32-N053B,F,K,P. 807 Package 800; MSIV Pilot Valve Report #2792-03-03; Rockwell Test Report Report #126-62; Environmental Testing of MSS /RV Air Control Valves. Report #2864-02-01; Rockwell Test Report. 808 Package 900; GECO Heater Environmental Qualification Report for E32-B001. 809 Package A00; Sicmens Motor Environmental Qualification Report for E32-C001 and C002. 810 Package B00; Gould Transmitter Environemntal Qualification Report for E41-N062B,F. O i o o 10.15
)
a - - wa_ a , - -, a, a .w., , - - ,,, - -.sa ., , < , m _su oa .-- see aa-_,- -e-- _ i l i 4 APPENDIX A t LIST OF SYSTEMS IMPORTANT TO SAFETY 1 l i 4 d t i i h 1 I I e i 1 I i ) i i d 1 l l
)
l 1
, ,.- .- -.+..,..,-.---.- ..- - . ., , ._,.. , -,... ,.,, , , , ,. . , _, , _ . , . , _,, , , , _,, . . _ ,, , ____ ,,,,,,... ,, . , , ..,,-. . , ,__ . .,.. , -- , ,. _ , . , , . - , -
\{ }/
j' TABLE I _C.__...____..____________._...__. D p u-g SYSTEMS It1PORTAtti TO SAFETY , _L _ LGS ELECTRICAL EQUIPMDIT _ _
+
ENVIR0tttENTAL QUALIFICATION REPORT f] b
*emeannemenesessenemmeneseenseneemaneesmenemmesamenememamennemumme SAFTEY FUNCT.
g SYSTD1 NAME __ ____._ OBJECTIVE (' CLASS IE POWER INTERFACES CONTAD2 TENT ATMOSPHERIC CCHTROL SYS. ICAC) ALL CI g CONTROL. ROD.CRIVEJ CRD L__ _ __ __ _ _ _ _SS _ _ . _ ____ _ _ _ _ _ _ _ _ ___ CORE SPRAY CC '(3 CRYWELL CHILLED WATER--ISOLATION VALVES CI / CRfMELL HVAC CI
.RHR,SS,CC.
_ECCS_FUttP_ ROOM HVAC _. _ _ _ . . _ _ _ _ . . _ - . . _ _ _ _ . _ . _ _ _ _ . . _ _ _ _ EMERGENCY SERVICE WATER RHR.SS.CC (~} EQUIPMENT & FLOOR DRAINS HIGH PRESSURE COOLANT INJECTICH (HPCII CI CC g MAIN.STEAtt ISOLATICN VALVE-LEAKAGE _ _ _ EC _ _ _ _ _ _ __ ___ CDITROL SYSTEM ittSIV-LCSI /} f NUCLEAR BOILER INSTRUMENTATION OSI) t0 CLEAR BOILER SYSTEM ttSSI NUCLEAR STEAM. SUPPLY _ SHUT 0FF_ SYSTEM (NS4)__ __ CC.SS.CI.RHR ALL
.CI. _ _ _ _
PLANT LEAK DETECTION CI C PRIMARY CONTAItttENT INSTRUMENT GAS PROCESS RADIATION ttCtiITOPIt!G SYSTEtt CI EC g } REACTOR _ CORE.ISCLATICH COOLING SYS..IRCIC).. _ .. CC . _ __ _ __ _ REACTOR DCLOSURE COOLDG WATER--ISO- CI Q LATIOti VALVES REACTOR ENCLOSURE HVAC--RECIRC. MODE SS g REACTCR. HATER. CLEANUP _SYSTUt.tPWCup___._. ._CI________ _ . _ . _ . _ _ _ _ _ _ _ _ REACTOR RECIRCULATID4 SYSTEM CI.S$ Q' RESIDUAL HEAT ret 10 VAL tRHR) SAFECUARD CC POWER RHR.CI.55.CC ALL g SAFEGUARD PIPItfG FILLSYSTD1__ _ _ .. . __ . _ _ . CI.CIN _ _ . _ _ . _ _ _ . . _ . _ _ _ _ _ _ _ . _ _ _ _ _
~
SAFETY RELIEF VALVE POSITIDH ItOICATID4 CC
] STAfCBY LIQUID CONTROL SYSTEM iSLC D STAtCBY CAS TREATMENT SYSTD1 (SGTS)
SS CI.EC g SUFFRESSICH. FOOL CLE ANUP_SYSTUt ____ __ .._ _ _.__ _ EC _ . _ _ _ _
~ ~ -
Y 4KV POWER ALL Q 440V LOAD CENTERS & F1CC*SALL g $ 1 CC :.CCRE COVERAGE ___ , _ l. _ __ _. _ _ _ _ _ _ _ _ _ ~ ~---- e i SS = SAFE SHuTocuN I i] s l l CI s CONTApt1DIT ISOLATION I RHR= RESIDUAL HEAT ret 10 VAL I g
- _ 1 CIHz_COtiTADetENT INTEGRITY _ f .
EC = EFFLUENT CONTROL i
- I j l ALL= ALL THE ABOVE g
_ _ - - - - _ _ ~ . . -- _ _ _ _ _ - __ , _ _ O e e O e m __ - - - - - -
_ - - . = . _..._ . . . _ ----- . . . ---- . . - - . . . . . . - - - . . - - . - . - . - , _ . - . . . ~ . _ . . . . - - - ~ ~ . . - - - - , . . . . . - . . . - - - - _ - - - - ~ . - ~ . . !O 1 i I. 4 i i 4 i l APPENDIX C 4 PLANT ENVIRONMENTS l
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Taps.g 3 gre,e t og 323 O&aalA7FD isset&L ase 8th53R58 PEAfrF FlfrI9f43WWra8 CDeelTICIs5 esh asPirma?1suG sT1supITIomum pelattee ihssd $ t y DmeeIII lategrateeIII sete/ pes ave /sies pase tries asea Pressese Temp (**r3 e trade /tw p is adel tielt t Innit 2 amas ans, maan ano. Reactor tacteeens,
- 882, 808 573, 874, mud peamp compassmente -3/4-tact e.g. 6S/995 $4/9e f.4S 5.09E+$
203, 284 200, 208 See 179 scIC pesup emmpestaeet -l/4-tach w.g. 4S/1IS 50/te 4.30 4.048+5
,309 . See apC3 yesmp campestmoet -1/4-4 met w.g. 6S/ SIS 50/98 2.43 0.46t+S IIS, 333, tel, 104, CS pesup compostaente -1/4-tact w.g. 6%/195 Se/90 2.S8-3 194, 197 345, 500 4.?st+2 3
939 982, tee 31evataan I?? accese asea -1/4-amch w.g. S0/94 65/l04 2.SE-3 c.70g+2 Its Elevotten 377 accese area -1/4-tact w e. 65/184 Se/9e 2.SE-3 0.70s 2 200, 247, 279, 204, Stewetten 200 accese asea -l/4 4 met e.g. 6S/194 Se/9e 2.$3-3 0.7eg+2 210 287 209 Cantatament teolattoo salve -l/4-inct v.g. 6S/12e 50/94 2.s 7.ceteg I vtmoet, el. 289 timit Il 206 Cnetainment teolatten water -1/4-inch w.g. 65/928 $0/94 2.0 7.Ger+5 compostoont, et, 289 (Unit 28 209 205 - acIC piptag asea -8/4-inch w.g. 65/195 $8/94 9.34 4. set +S 28s 203 IIPCI piping asea -9/4-tach v.g. 65/ TIS 58/98 2.43 c.4H+5 2 L 384 370 Elevatten 217 access asea -1/4-tach w.g. 6S/984 S0/94 2.SE-3 a.7es+2 3es, 307, 374, 375, Conta& ament toolation value -9/4-inch w.g. 65/128 $4/98 2.49 8.46E+5 309 316 Compostaeet,el. 297 i TIG42e64-elv t C-1
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e TA3 85.1 IPage 2 of 92) CAlfttLA71 D Im@ MAL ANU seAIlmt9e PtANT 988VIR00amfWTA3. COMDITIOpe$
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- LEICA RelattweISO st>+e I41CA16) 7t>t alIII t e esaus e III Temp 446 fium1daty hat e Ikase Ornee area timagt (*FS t (see ser teel gsads) (sadst Iantt i 13 nit 2 moon sea, moom aso. Deactor Enclosese 182, 803 153, lie, RHR pump cupgang tments Atens/l.50 995/275 900 0 (13) (129 eamma 4.78E*4 gamma 5.29E*6 283, 204 280, 299 tota I.3aL+6 teta 3.3SE*6 108 I?9 RCIC pump compasteent Atmus./2.78 415/222* 100* (283 (12) g9mma I.95E*6 gamma 2.44F+6 beta 3.38E*6 tota 3.30Ft6 Ist , ISO IIPCI pump compartment Atmos./2.7" Il%/297 b 160 b 1103 (121 gamma 3.9%E+6 gamma 4.pnF+6 beta I.lSF+4 leta I.3tF+6 IIS, 113, 189, 184, CS pap compartments Atsee. 115 90 (ISI (123 gamma 3.95F+6 gamma 3.95F+6 li4, 117 ISS, ISS beta 1.30F+6 beta I.30F+6 159 842, 189 Elevat6on 177 access asea Atmoa. 120 90 819) (125 gamma 3.70E*6 gassa 3.70E*6 beta 3.3SF+6 tota 3.38F+6 Ils Elevation 177 accesa area Atmon. 120 90 652) samma 6.63E*4 eamma 6.71E*4 beta 1.38F+6 reta 3.34F+6
*00, 297, 279, 284 Elevation 201 acsess area Atsus. 120 90 (its (12) gamma 3.70E+6 eessa 3.70r+6 JIS 287 heta 1.38F+6 bet a 3.38F+6 209 Cuntainment isolat6cn valve Atmos. 120 90 (19) (12) gamma 3.70E+6 gamma 4.40E+6 compartment, el. 201 (18mit Il beta I.38E*6 tota I.3pr+6 286 Cbatainment isolation valve Atmos. 328 90 (125 gamma 6.63F+4 aansa 7.66F*5 compartment, el. 20I ttm a t 2) teta 3.3pr+6 tota 3.38t+6 209 285 8CIC pig-ing area Atmos./5.3 8 195/2968 500* (223 (123 gamma t.87t+5 gamma 6.7tE*5 to t a 3.18E*6 teta 1.38E*6 248 h 283 ItPC8 piping area Atmos./6.t 31%/29t h IO0 h (213 (12) g9sume 0.42E*5 gamma 1.69P:+6 tota 3. 3 8t:* 6 tota 1.16rea 304 378 Elevation 287 access area A t ar>s . 120 90 (15) (32) gamma 4.15E+6 gamma 4.9%F+6 teta 1.34F+6 teta 3.30F+6 306, 307, 374, 375, Cbatainment teolation valve Atmos./1.4C 120/264 C 90cc (141 (123 samma 4.5%F+6 gamme 9.40F+6 309 376 Coopertment, el. 287 tat a 1.38F+6 teta 3.3e2+6 T1002se4-elv C-2
v TAALS. I Itage 3 of 12) CAlft4ATFD ameMAL ANE% MAIlptel PLANT EkVIDONMFNTAL CtedDITIONS ta*M TA*FNA?lpa' LYmeLITJUNS Notative Mumidity EnseIII InsegratedIII Min / Mas Aw4/ Mas pate tasme Ar ea Pr essur e Temp 88 F3 % (rads /hrt (radst tanit I tinit 2 aoom me. toon see, peactor Enclosure 482 475 CSD hydraulic area al/4-inch w.g. 65/104 50/90 0.9 3.53r*4 406 heutron monitoring area -l/4-inch w.g. 65/304 50/90 3.72E+4 6.99t+7 (Unit 4) 479 Iseutson monitoring area -l/4-inch w.g. 65/104 50/90 3.72E+4 6.9tE*7 (Unit 2) 447, SIS 488, 547 temin steam tunnel -l/4-inch w.g. 65/120 %e/90 3.04 1.35s+6 Set 575 arywe!! spray isolation -l/4-inch w.g. 65/995 50/90 0.225 7.99E+4 valve compartaent 502 576 tackwaak receiving tank -9/4-inch w.g. 45/980 50/90 577 2.03R+e compartaent 543 577 asCU system regenerative -1/4-inch w.g. 65/300 50/90 3.37 f 80E+6 heat escheneer compartment 504, 545 578, 579 asCU eyeten nonregenesative -l/4-inch w.g. 65/598 50/90 1.45 4.02E+5 heat eachanger compartments See Standby Liquid Ccatrol -1/4-inch w.g. 65/104 50/90 2.5E-3 4.78t*2 System Area 574 standby Liquid Controi system -l/4-inch w.g. 65/I04 50/90 2.5E-3 a.7et*2 Area Sc6A Ibatainment leydrogen peccabiner -1/4-inch w.g. .65/304 50/94 2.5t-3 0.70r+2 Area ( Area II, Northwest madel Seen Ontainment seydrogen meccabiner -l/4-inch w.g. 65/804 40/98 2.52-3 S.78t+2 Area (Asea 54, Isortheast side) 5868 Corridor - Access Area -1/4-inch w.g. 65/104 M/90 2.5F-3 8.79E+2 (Area IS, Southwest sadel Sees metidor - Access Area al/4-inch w.g. 65/104 50/90 2.5E-3 0.78E+2 IArea 10, Southeast sidel T1082804-4IV C-3
. . . _ _..m._ . _ _ . _, __ .
N . ( \ Tantf I (Page a of 12) CA8& LATED leM*AL Ase0 MAXIMtm PLANT EMthDNNfWrAL COhttlTIONS MAIIrate CONDITI(esM < tKA pelativelII rose IMAt6l 9ng ,g(Il i Ps essur e l38 Tess 8 8 8 soun tdi t y mate Dose tese ("F3 ($ee Noteal { gads) Ar ea ~(poset S (g aris) Unit 9 Unit 2 anos leo. Boom eso. pesetor Enclosuse 4e2 475 CRD hydsestic area At enee. 120 90 1953 (123 qsume 4.1SE+6 gamma 4.19Fe6 tota 1.38Fe6 tet a 1.369:*6 446 leeutron monitosing area A t es . 320 90 (19) (125 gamma 3.70F+6 ganea 7.26E+7 (Unit il beta 1.34E+4 teta 9.38E*6 479 leeutron monitoring asea Atmaa. 320 90 (24) 1828 gamma 4.08E+$ gassa 6.95E*7 (Unit 23 tota 1.30E*6 tota 3.38F+6 487, SIS 400, $47 femin steam tunnel At su .a./9. ,h 120/11t h 100h (278 (128 m S.16E*6 gm 6.Str+6 '! tete 1.30E+6 tota 6.38F46 - Set 57S Dryum!! apray isolation Ates. 32s 90 (16) t%29 gamma 3.95t+6 genea 4.elr+6 eelve compartmoet teta 1.30E*6 tota 1.38F+6 S43 $76 hectuaah seceiving tant Atmos. 320 90 (52) gamma 6.63E+4 gamma 2.03r*8 compostment tota 3.30E*6 te t e 1.30F+6
$43 577 sesCU system regenesative . Atmoa./2.69 120/284 I lea I (12) gamma 6.63r+4 genea 1.2SF+6 heat eschenger compartment tota 1.30E+6 to t a I.)SE*6 See, SOS 570, S79 sesCD system maaregenerattee Atmos./2.79 120/287 d foo d (125 gamma 6.63E*4 gassa 4.68F*S heat enchanger compasteents tota S.30E+6 tota 1.3aE*6
] 500 Standby 8.iquid coatso! Atmos. 120 90 (t6l (12) eamma 2.95E+6 gamma 3.95r*6 _ Systee Area teta 1.30E+6 tete 1.18F+6 174 Standby Liquid Chatso! System Atmos. I2e 90 (193 112) gamma 3.70F+6 gamma 3.70E*6 Area leta 3.3tE+6 to t a 4.30E*6 Seen . Containment sydsogen necembaner Atmos. 120 90 (193 842) gamma 3.70R+6 gamma 3.70E*6 Area (Asea ll, Isostivuest sidet beta 1.38E+6 teta 1.3Sr*6 Seen Chatainment leydrogen secombimer Atmos. 12e to (16) 4128 eamma 3.95E*6 gassa 3.45r*6 Area (Asea 14, Mostheast side) teta 9.30E+6 te t a 3.38r+6 5468 Corridor = Access Area Atmos. 320 90 (32) emana 6.63r+4 geoma 6.71E*4 (Asea IS, Southwest sidel teta 3.30E+6 teta 3.30F+6
-SGGS Cost! dor - Access Area Atmon. 320 99 (161 ( til games 3.95Fe6 eamma 3.e50+6 (Asee te, Southemat sidel tete 9. Nf**6 lete 1.39F+6 T1982SO4-elv C-4
.- .. . _ . . . __ _ . . .._ ._._ _m- _ .
V 5 ' TANI I (Paoe 5 og 12) CAlftflATf D IdOIU*AI AND ttARIMeg PEAR? FffVipOggeFNTAg CnNDITION!t POPMAI. nPilhT34i(tYeDOT[ lens M*tatIve f%em nd 6 t y ImeeIII IntegratedUI Man / Man Aeg/ Mas Date Ibse As ee Pr essur e Temp (*F) t fr eds/hr) tradap thte t i Un&t 2 poem Iso, hoop Iso. Reactor Enclosure Se6C Cnntalmeest trydrogen Decemb6nes -1/4-inch w o e. eS/ tee 50/90 2.SE-3 0.7er+2 Area (Area 16, Southeast a6 del SeeC Containment IIydrogen peccatelner -1/4-anch w.g. 6S/t04 Se/*e 2.St-3 0.7eE+2 Area (Area 17. Southwest side) Seep Fuel Pnot serv 6ce teater anoster -l/4-inch v.g. 6S/984 Sc/94 2.SR-3 0.70t+2 Pump Area (Asee 12, sawtheast Endel a Send Fuel Pool Service teater Imanates -1/4-inch v. g. 65/104 $0/90 2.SE-3 8.7er+2 Pimp Ases (Asea 13, sk>rthwest side) 587 See, Set, 502, macu eyetas pump compartmeets -1/4-inch w e. 65/104 S0/90 3.29 f.86t+6 Set S83 (gnortheast side) Ste, 522 544, 59) . fuscu syntan lactation -t/4-tach w.g. 6S/11S 50/98 55.5 t.26E*6 walve compastsent [ t Stt .SGS Fuel Pool Cooling teater Pump and -9/4-inch w.g. 65/984 50/90 2.55-3 0.7eE+2 leeet Eachanger Area Sgt Access Area att. 340') -t/4-tach w e. 65/104 50/9e 2.5r-3 e.74E+2 594 Accese Area (E1. 30e*3 -t/4-$nch w.g. 65/984 S0/90 2.SF-3 0.78E+2 1 S23 $93 Core aptay tactation -1/4-6mch wo e. 58/9e 0.1 65/t35 3.58t+4 valve compartment
$99 Set isCI teolation valve compartment -1/4-inch w.g. 65/115 50/98 0.8 3.SIE*4 608, 682 437, 434 Inorth and South corridors.
5
-1/4-inch w.g. 65/984 50/94 2.SF-3 0.78t+2 te$ tot et. 313
' 682, 618 651, 653 Rans filter compartment -t/4-inch w.g. 6S/104 $0/90 2.50-3 0.78E+2 T18e2444-elv 4
C-5
t v v TApip 3 (Paee 6 of $2p CAlavtJTt'le NiepMAl, AND MAXiPIWe PLANT ENVlllONPFNTAL (YNDlf!ON.9 MAstreet renMntTIte8S
- IIECA pelativetSI ten, itJCAI 'I totatIII PrcesureIII genpI4I esu m4d6ty sate innse 51ose Area (5464) (See Notes) (radst Unit t Umat 2
(*Fl_ t Isadst moon gem, poem gen. Reactor Enclosure Sc6C Containment Wydrogen Secombiner Atmos. 92n 90 (16) (12) gamma 3.95E+6 eamma 3.95F+6 Area (Area 16, Southeast ondet beta 1.38E*6 beta 1.38E+6 SeeC Contatament sydroges beconhanet Atmos. 12ip 90 (19) (12) gamma 3.70Fe6 gamma 3.70r66 Asea IAsee 17, southwest o&det beta 1.3eE+6 teta 1.30E*6 Sc60 ' Fuel pool Service tastes Booster Atmoa. 128 90 (16) (12) gamma 3.9tE+6 ammaa 3.95E+6 Pisap Asea (Area 32, Northeast $1 del teta 1.3eE+4 beta 1.3sE*4 Seed Fuel Foot Seswice Isates Suoster Atmos. 12e 90 (19) 182) gamma 3.70E+6 gamma 3.70E*6 Pump Area (Area 53, esosthwest e6 del beta 1.3eE+6 tota 9.30E+6 507, See, 500, $e2, sescu system pismp compartmento Atmos./2.79 920/297 8 fee * (123 gamma 6.63E+4 gamme 9.23E+6 583 583 (senetheast oldet beta 3.30E+6 beta 3.3pE+6 SIS, S22 504, 597 Isscu system teolation Atmos./2.79 120/28eI fee 9 (153 (12) gamma 4.15E*6 eamma 5.4tE*6 valve compartment tete 1.3eE*4 beta 1.34F+6 Sll 585 Fuel Pool Cooling teater Pump and Atmos. 12e 90 (l63 (123 gamma 3.95E+6 gamma 3.95F+6 heat Eschenger Area tota 1.30F*6 beta 1.30E+6 Sig Access Area (E1. 300') Atmos. 12e 90 (19) (123 gamma 3.7er+6 gamma 3.70E+6 tota 9.3er+6 beta 3.380+6 594 , Accese Area (E1. 300') Atmos. 12e 94 (163 (12) gamma 3.95F+6 gamma 3.95f+6 beta 1.3er+6 tet a 1.38F+6 523 $93 Case opsay teolation Atmos. 12e 90 gamma 3.95E+6 (16) (tal gamma 3.**r*6 valve compartment tota 1.30E*6 tota 1.38F*6 599 Set 17CI teolettom walve compartment Atmos. 128 90 (153 112) gamma 4.ISE*6 eamma 4.19E*6 leta 3.30E+6 teta 1.30E*6 648, 6e2 637, 63e teorth and South corridore, Atmos. 128 go (12) easume 6.63F.*4 eamma 6.71F*4 645 648 el. 233 tota 3.36t+6 tete I.3aF+6 682, 618 658, 653 mEh8 filter compartment Atmos. 928 90 (233 112) samme f.e4F.+7 gamma 1.ser+7 teta 3.38F+6 teta 1. 388 +6 Tlee2se4-elV C-6 , i m__ ._ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ __ __ _ _ _ _ _ _
r f f
. 1 ChifUIATFD NOeft&L AND MMlfuel P1 ANT ENVlenseurprrAL C00sDITIONS
.. 7 ., ,2, sums 4AL OPreaTING CONnstMo8M i '
selettveIII Humasitty pape UI Integsate8III Man /Mes Arg/ Man sete Ikase Area Pressure hop (Orb a frerte/bs ) lieas) i Primary Cente&nment Beme I, eheve core e.75 peig 65/958 20/les gamme- 34 gamme e.eB+6 i neut rone-35 neutsene-l.2e+7 t meme II, cose senten 8.75 peig 65/950 24/see genne-SS gamme-l.ere? i
- meut one-30 neut one t.t3+7 6
amme III, unees vesse! 8.75 peig 65/154 20/100 gamme-12 gamme-4.3E*6 meet some-84 meutrone-S.eE+6 emme IV, moes recirc. pape e.75 peng 65/156 20/100 gamme-Se gamme-l.es+7 mortsene-se meutrone-5.5a+4 teme V, >t5 ft from racisc. 0.75 Pets 65/958 28/900 gamme-25 gamme-8.0t+4 Pumpe meut:one.I6 meutreme-5.Se+6 j teme vt, sugeseestem chamber 8.75 peig 6S/150 20/100 gamme-19 gamme-3.7t+4 neut one-0.43 meutrone-l.Sres amam me. Cent on seructere 424 SGTS ognap. campesteem- Atmos. 6S/104 50/98 2.35E-2 s.23t+3 533 control team +t/4-tech u.g. 76 + 2 50/55 S.et-4 8.76t+2 S42 Ae!!!asy egnip. toom Atmos. 76 + 2 50/S$ S.8R-4 9.76t+2 Gee, eSe Cable apreselag sesan atmos. 65/ lee 50/g0 S.eE-4 3.762+2 . i Ties 2004-elv c-7
.u-... ~~ . -~ ..a- . . = . - . . _ _ _ . .. . - - - , . .. _ - - _. . _ - _ . _ ~ = . ~. - _ . _ - . ~ + . . - - - - - _.
I L (' TamIE 9 treee e of $2p l C11CRATen esneseAI. Age etszIsutee Pt. ANT rpWIM88twfAL GDDITI(1MS suffmee u--iiious IKA f menetteeII8 rm,., gr at6) m ,ggg) ereeeereI38 Temp I48 mumteaty meae sanee nose asse IPs6gt (43 4 (See noteel fredet fredst t primary emnestemene Emme I, ohmee este 44*8 338 ISS 47) gamme-4.S M*7 esame-S.4 Me? ! . set. e-. ee.t . .. . . n., hete-9.10E+9 heta-t legey ! l .m.e n . este ,e. en .4.. 3M i on -. . SM. 7 -6. 3M. ,
, meetsene-4 mestrons-9.lE*7 heta-1.10E*9 heta-I. tee *9 amme III. uness wesee! 44 0 3M 888 678 gamme-4.SM+7 gamme-S.02E*7 mentrons-8 mestrens-5.St+4 ;
hete-l.10S*9 heto-l.seret j- amme IV, meer sectre. pumps 44.s 3M 100 67) gamme-4.f M*7 genne-6.6te7 meetsome+4 esettens-S.SE*4 heta-9.89E*9 tote-l.let*9 amme W, hts ft free sectas. 44 8 II8 '88 III 988"**4 'IM*I 9 " **I*S8'I g meetsene-4 neutsame-S.SF+6 hete-9.ler+9 heta-9.I M*9 l Same V8. empereeelen cabammes 44.8 SM 308 E7) gamme-4.S M +7 gasse-4.96t+6 , asutreme-S meutrone-9.Ste$ j tete-9.16t*9 heto-l.letet amme mm. Cameral Stremrtuse 63e agrs egnep. sempertemme Atmo. 32e Se/Se t99 3.22r+S 3.3er*S
$33 Centrol seem et/4-6ach w.g. 79 58/68 4183 6.4 3.373,2 542 Ammittery aestp. game atmos. 78 50/64 sep 3. Me t 3.39g,2 449, 454 Cable apreestag seen Atmos. 305 se/tes g43 2.st g 3.97F*2 e
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'N T&a5 E 9 spege g og 923 CatD4ATEp anNuesL asD ga&ElftUBE FRAm? R3WIDOREurWrat CDeetTIONS ta eseAA. OrsAAT!ser.' (12@I75480 metetteelSS teueld el y IbseIII IstogsatedlII sete/same aeg/sses set e taase erse esseemse Temp 4*FS t ts ads /hs B 8seseI aman me, Castret Structuse <
ele 81ueC esusSp. campesteest, el. 384 neems. SS/tse Se/se 2.St-3 0.7ete2 625 Eluac assip, compose ===e, et. 332 atmos. 6S/S M Se/Se 2.SE- 3 a.76te2 333, 32e settery composteente atese. M/lH128 Se/9e S.es-4 f.76t+2
, he, Mt 425, 4M 427, 4M 62e-435 m esgaary settchener team M ene. 6S/fM S4/90 S.st-4 9.76t*2 e52, 453 assenter samme mese. 6S/ted SS/9e S.st-4 9.76t+2 250, M3 Caetset streetere ett!!er eseos atees. 6S/tM S$/90 2.Sr-3 a.7et.2 7834258 annett etace anstettee essenterlag nemaa. 65/tM $4/90 2.SE-3 0.7et+2 M
2e2 Elevet ten 297 Pipe hmmet Mass. $$/823 SS/ tee 2.S2-3 a.7ste2 399, StS Memel-demorater sectosere Mene. 6S/sts Se/9e S.et-4 3.76t*2 31 3 Momendmasseter carriens atene. SS/ tee 50/100 S.st-4 9.76t+2 seter Dame Fuse structose meses. es?stS SS/9e S.st-4 1.76te2 unit 3 tanat 2 team me. Beam he. Tushlee Emetemure j 332 MS h base . etes eroe -3/4 sach we. 6S/82e 70/98 7.It+e 2.Ser+6 coleeret. 254 332s MSm Serb &se-gemeseter stee -t/4 auch we. SS/92e Pe/9e 4.or+4 8.4et+6 aboos et. 2W 42e 454 enesueter heetes stee -9/4 &ach esg. 6S/92e Se/9e 9.4r*e S.Ser+S
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(Page 11 of 12) TABLE I (Cont'd) (~~,\ f G Notes (1) The normal total integrated doses are for 40 years. The present post-LOCA gamma doses are conservatively based on NUREG-0737 methodology. These conservative gamma doses would bound the total of the neutron doses and the post-IDCA gamma doses (if the gamma doses were calculated by NUREG-0588 methodology) l In view of this, it is not necessary to add the neutron doses to the present gamma doses for equipment qualification purposes. (2) 88'r represents the battery compartment average temperature. (3) First number corresponds to maximum LOCA/ loss of ventilation pressure. Second number corresponds to maximum High Energy Line Break pressure, where applicable. Break identification is provided in note (4). The maximum LOCA l pressure for each area should be assumed to last for 180 days for environmental
- qualification purposes, except for the primary containment. A bounding primary containment pressure profile is provided in Figure 2. The maximum High Energy l
Line Break (HELB) pressure for each area should be assumed to last until the ! isolation valve closes, which in all cases is significantly less than one l minute. The maximum pressures listed for the control structure are maximum l LOCA pressures. Maximum pressures resulting from other accidents will be evaluated later. (4) First number corresponds to maximum LOCA/ loss of ventilation temperature. Second number corresponds to maximum High Energy Line Dreak temperature, where l applicable. Break identification is indicated as follows: l a. RCIC steam line break in RCIC pump room l (m, b. HPCI steam line break in HPCI pump room
- c. HPCI steam line break in isolation valve compartment I d. RWCU line break in RWCU nonregenerative heat exchanger compartment
- e. RWCU line break in RWCU pump room i f. RWCU line break in RWCU regenerative heat exchanger compartment
- g. RWCU line break in RWCU isolation valve compartment
- h. Main steam line break in main steam tunnel
- 1. RHR steam line break in RHR compartment l LOCA temperature profiles as a function of time are provided in Figure .1 through l Figure 6. For areas without LOCA temperature proflies, assume the maximum temperature lasts 180 days. The isolation valve compartment HEL8 temperature l
profile as a function of time is provided in Figure 7. Areas which have i maximum HELE temperatures listed, but do not have HEL5 temperature profiles, only contain components which will have completed their safety function once the blowdown has ceased, which in all cases is significantly less than one minute. l The maximum temperatures listed for the control structure are maximum LOCA temperatures. Maximum temperatures resulting from other accidents will be evaluated later. ($) Those rooms which esperience High Energy Line treak, identified by letters per note 4, will be subjected to 1004 relative humidity for 72 hours af ter the start of the High Energy Line Break at which time the relative humidity will fall below 904. For the normal primary containment relative humidity, the minimum relative humidity is provided instead of the average relative humidity. b) ( T1002804-01V Rev. 2 C-11
t I (Page 12 of 12) I i TABLE 1 (Cont'd) ! f t l Notes (Cont'd) i , (4) Se LOCA total integrated doses are for ISO days. S e beta doses and dose . rates are conservatively based on infinite cloud geometry, and the doses for ! areas containing radioactive pipes are conservatively based on piping contact doses. Doses for specific components within these areas may be lower, depending l on distance and spatial relationships. ; (7) Primary Containment Cloud (See Table la). ( (8) Control Structure Cloud, Adjacent Piping Shine (Dose rates not tabulated ! because of low Total Integrated Dose (TID)) l (9) 8078 Carbon Filter (See Table Ib). t (10) Adjacent Cloud Shine, Adjacent Piping Shine and SGTS Carbon Filter Shine f (Dose rates not tabulated because of low TID). i (11) Control Structure Cloud and SGTS Carbon Filter Shine (Dese rates not tabulated l because of low TID). l (12) Secondary Containment Cloud (see Table to) (13) 30' Shutdown Cooling Piping (see Table lj) (14) 24' Shutdown Cooling Piping (see Table 11) (15) 18' Shutdown Cooling Piping (see Table th) , (16) 16' Shutdown Cooling Piping (see Table ig) (17) 4' Shutdown Cooling Piping (see Table 1e) , (10) 16' ECCS Piping (see Table ig)
- 19) 14' ECCS Piping (see Table It)
O ((20) 4' ECCS Piping (see Table 1e) (21) (22) 12' MFCI Steam Supply Piping (see Table Im) 10' DCIC Steam Exhaust Piping (see Table 11) (23) REAS Carbon Filter (see Table Ik) (24) 6' recombiner piping (see Table 14) . (25) This room is located on the reactor enclosure roof. ! (24) The North Stack Radiation Monitocing moon temperature drops to 130'F after 4 days i (27) 24* ECCS Piping (see Table 11) (20) Minimum temperature with loss of normal heating is 390F. This temperature : includes heat gain from Class 15 powered equipm6nt. (29) Temperature does not refleet NELS conditions because the components in these ; areas are not required to mitigate the consequences of a NELa. 5 O " "'"'- ' " - C-12 l
l l O TABLE la i 5 CALCULATED PRIMARY CONTAINMENT DOSE RATES , i Gamma Dose Rates ,
! TIME DOSE RATE INT. DOSE TOTAL t INT, HRS { R/HR RADS BAD.L l ,
t
.10E-01 1'.07E+07 .00 .00 l l'
.50E+00 3.51E+06 3.16E+06 3.16E+06
.10E+01 2.60E+06 1.52E+06 4.68E+06 !
. .20E+01 1.85E+06 2.20E+06 6.88E+06 1 .40E+01 . 1.23E+06 3.04E+06 9.92E+06 ) .30E+01 ', 7.10E+05 3.79E+06 1.37E+07 1 .16E+02 3.66E+05 4.15E+06 1.79E+07 i .24E+02 . 2.41E+05 2.39E+06 2.03E+07 l .96E+02 7.17E+04 1.01E+07 3.03E+07 l .24E+03 3.45E+04 7.32E+06 3.76E+07
.72E+03 4.37E+03 7.00E+06 4.46E+07
.22E*04 2.56E+01 1.22E+06 4.58E+07 i .43E+04 6.56E+00 3.02E+04 4.59E+07 i
i O Beta Dose Riteg r l TIME DOSE RATE INT. DOSE TOTAL , INT. HR$ R/HR RADS B&QL ; } .10E-01 1.30E+08 .00 .00'
.50E+00 4.48t+07 3.92E+07 3.92E+07
.l .10E+01 3.54E+07 2.00E+07 5.92E+07 i
.20E+01 2.68E+07 3.10E+07 9.02E+07
.40E*01 1.88E+07 4.51E+07 1.35E+08
! .30E+01 1.26E+07 6.20E+07 1.97E+08
; .16E+02 8.00E+04 8.10E+07 2.78E+08 i
.24E+02 5.92E+04 5.53E+07 3.34E+08
.96E+02 2.22E+06 2.72E+08 6.05E+08 j .24E*03 1.01E+06' 2.21E+08 8.26E+08 !
- .72E+03 1.25E+05 2.03E+08 1.03E+09 i
.22E+04 , 3.00E+04 9.59E*07 1.13E+09 '
.43E+04 1.87E+04 5.16E+07 1.18E+09 j c~
h s
. C-13 1
b TABLE lb n SGTS CARBON FILTER CALCULATED DOSE RATES
~
TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-01 2.50E-03 .00 .00
.50E+00 1.00E+01 6.1'/E-01 6.17E-01
.10E+01 3.10E+01 9.47E+00 1.01E+01
.20E+01 7.47E+01 4.97E+01 5.98E+01
.40E+01 1.40E+02 2.08E+02 2.68E+02
.80E+01 2.10E+02 6.91E+02 9.58E+02
.16E+02 2.63E+02 1.88E+03 2.84E+03
.24E+02 2.81E+02 2.18E+03 5.02E+03
.96E+02 3.50E+02 2.26E+04 2.76E+04
.24E+03 4.5.1E+02 5.74E+04 8.50E+04
.72E+03 2.30E+02 1.58E+05 2.43E+05
.22E+04 3.41E+00 7.75E+04 3.21E+05
.43E+04 2.40E-03 1.01E+03 3.22E+05 O
4 l l 1 i i E l C - . . . .. . . - - - - . . - . . - -..- . - - - - - - . - . . . - . . . ,,
TABLE Ic CALCULATED SECONDARY CONTAINMENT DOSE RATES . Gamma Dose Rates 1 TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS ,
. i
.10E-09 1.00E-10 .00 .00
.50E+00 2.49E+02 4.36E+00 4.36E+00
.10E+01 3.23E+02 1.42E+02 1.46E+02
.20E+01 3.93E+02 3.57E+02 5.03E+02
.40E+01 4.55E+02 8.47E+02 1.35E+03
.8CE+01 4.46E+02 1.80E+03 3.15E+03
.24E+02' 3.07E+02 5.96E+03 9.11E+03
.96E+02 1.87E+02 1.74E+04 2.65E+04
.24E+03 9.33E+01 1.94E+04 4.59E+04
.72E+03 6.40E+00 1.56E+04 6.15E+04
.43E+04 5.78E-02 4.85E+03 6.63E+04 Beta Dose Rates TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 1.00E-1O .00 .00
.50E+00 9.40E+02 1.57E+01 1.57E+01
.10E+01 1.39E+03 5.75E+02 5.91E+02
.20E+01 1.92E+03 1.64E+03 2.23E+03
.40E+01 2.50E+03 4.41E+03 6.64E+03
.80E+01 3.03E+03 1.10E+04 1.77E+04
.24E+02 3.50E+03 5.22E+04 6.99E+04
.96E+02 3.35E+03 2.47E+05 3.16E+05
.24E+03 1.75E+03 3.55E+05 6.71E+05
.72E+03 2.01E+02 3.44E+05 1.01E+06
.43E+04 4.23E+01 3.66E+05 1.38E+06 O
O . C- 15
1 O TABLE Id 6 INCH RECOMBINER , CALCULATED PIPING DOSE RATES TIME DOSE RATE INT. D SE TOTAL INT. HRS R/HR RADS RADS
.10E-09 7.53E+04 0 0
.50E+00 2.95E+04 2.44E+04 2.44E+04
.10E+01 2.25E+04 1.29E+04 3.73E+04
.20E+01 1.54E+04 1.87E+04 5.61E+04
.40E+01 9.75E+03 2.47E+04 8.08E+04
.80E+01 5.57E+03 2.99E+04 1.11E+05
.24E+02 1.82E+03 5.36E+04 1.64E+05
.96E+02 4.19E+02 6.86E+04 2.33E+05
.24E+03 2.08E+02 4.34E+04 2.76E+05
.72E+03 3.34E+01 4.59E+04 3.22E+05
.43E+04 8.80E-01 2.02E+04 3.42E+05 O .
9 I e
- e e
O C- 16
I O TABLE 1e 6 INCH ECCS ' CALCULATED PIPE DOSE RATES l 1 TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 5.79E+04 .00 .00 i
.50E+00 4.18E+04 2.47E+04 2.47E+04
.10E+01 3.57E+04 1.93E+04 4.40E+04
.20E+01 2.77E+04 3.15E+04 7.56E+04
.40E+01 1.97E+04 4.70E+04 1.23E+05
, .80E+01 1.32E+04 6.49E+04 1.87E+05
.24E+02 5.91E+03 1.45E+05 3.32E+05
.96E+02 1.91E+03 2.55E+05 5.87E+05
. 2 4 E+ 0.3 1.12E+03 2.13E+05 8.00E+05 >
.72E+03 4.42E+02 3.50E+05 1.15E+06
.43E+04 7.05E+01 7.28E+05 1.88E+06 O ,
6 8 O I C-17
I l i
~
TABLE If 14 INCH ECCS . CALCULATED PIPING DOSE RATES TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 1.15E+05 .00 .00
.50E+00 8.30E+04 4.92E+04 4.92E+04
.10E+01 7.07E+04 3.84E+04 8.75E+04
.20E+01 5.49E+04 6.25E+04 1.50E+05
.40E+01 3'.89E+04 9.29E+04 2.43E+05
.80E+01 2.58E+04 1.28E+05 3.71E+05
.24E+02 1.14E+04 2.83E+05 6.53E+05
.96E+02 3.62E+03 4.89E+05 1.14E+06
.24E+03 . 2.13E+03 4.05E+05 1.55E+06
.72E+03 8.54E+02 6.70E+05 2.22E+06
.43E+04 1.38E+02 1.41E+06 3.63E+06 0
e ( O ' C-5 l l 1
, , , , , - - - - - - . r n e e --er- - - - - 9 y q. - - + -,yv-.< ,v.m ., --e
O TABLE Ig 16 INCH ECCS - - CALCULATED PIPING DOSE RATES TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 1.24E+05 .00 .00
.50E+00 8.93E+04 5.30E+04 5.30E+04
.10E+01 7.60E+04 4.13E+04 9.42E+04
.20E+01 5.90E+04 6.71E+04 1.61E+05
.40E+01 4.18t 04 9.98E+04 2.61E+05
.80E+01 2.77E+04 1.37E+05 3.98E+05
.24E+02 1.22E+04 3.03E+05 7.01E+05
.96E+02 3.85E+03 5.21E+05 1.22E+06
.24E+03 2.27E+03 4.30E+05 1.65E+06
.72E+03 9.1'2E+02 7.15E+05 2.37E+06
.43E+04 1.48E+02 1.51E+06 3.88E+06 D
e C-19
l O TABLE 1h l l 18 INCH SHUTDOWN COOLING i
. CALCULATED PIPING DOSE RATES TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 1.32E+05 .00 .00
.50E+00 9.45E+04 5.60E+04 5.60E+04
.10E+01 8.04E+04 4.37E+04 9.97E+04
.20E+01 6.23E+04 7.10E+04 1.71E+05
.40E+01 4.42E+04 1.05E+05 2.77E+05
.80E+01 2.92E+04 1.45E+05 4.21E+05 .
.24E+02 1.28E+04 3.19E+05 7.39E+05
.96E+02 4.04E+03 5.47E+05 1.28E+06
.24E+03 2.3.7E+03 4.51E+05 1.73E+06
.72E+03 9.59E+02 7.50E+05 2.49E+06
.43E+04 1.55E+02 1.59E+06 4.08E+06
. O l l 1 0 . e *e C- 20
i f'
' l TABLE li l
24 INCH ECCS
- CALCULATED PIPING DOSE RATES l
TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 1.47E+05 .00 .00
.50E+00 1.05E+05 6.26E+04 6.26E+04
.10E+01 8.95E+04 4.85E+04 1.11E+05
.20E+01 6.93E+04 7.91E+04 1.90E+05
.40E+01 4.90E+04 1.17E+05 3.07E+05
.80E+01 3.24E+04 1.60E+05 4.68E+05
.24E+02 1.41E+04 3.53E+05 8.20E+05
.96E+02 4.40E+03 5.99E+05 >
1.42E+06
.24E+0.3 2.59E+03 4.93E+05 1.91E+06
.72E+03 1.05E+03 8.20E+05 2.73E+06
.43E+04 1.71E+02 1.74E+06 4.49E+06 I
O I C-21
TABLE lj . 30 INCH SHUTDOWN COOLING . CALCULATED PIPING DOSE RATES TIME DOSE RATE INT. D'OS$ TOTAL 1 INT. HRS R/HR RADS RADS i
.10E-09 1.57E+05 -
.00 .00
.50E+00 1.12E+05 6.65E+04 6.65E+04
.10E+01 9.48E+04 5.15E+04 1.18E+05
.20E+01 7.34E+04 8.37E+04 2.02E+05
.40E+01 5.19E+04 1.23E+05 3.25E+05
.80E+01 3.42E+04 1.70E+05 4.95E+05
.24E+02 1.48Ev04 3.70E+05 8.66E+05
.96E+02 4.59E+03 6.29E+05 1.50E+06 .
.24E+03 2.72E+03 5.15E+05 2.01E+06
.72E+03 1.1'1 E+ 0 3 8.59E+05 2.87E+06
.43E+04 1.80E+02 1.84E+06 4.71E+06 0 .
l e C 22
.. _ _ _ . ._ _ _ _ . . . _ - . - - . - . . - . , - . .- .~. _ . _ . . --. .
TABLE 1k CALCULATED RERS CARBON FILTER DOSE RATES
' TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-01 2.50E+03 .00 .00
.50E+00 7.99E+02 3.09E+01 3.09E+01
.10E+01 2.08E+03 6.70E+02 7.01E+02
.20E+01 4.20E+03 3.02E+03 3.72E+03
.40E+01 6.64E+03 1.07E+04 1.44E+04
.80E+01 8.90E+03 3.09E+04 4.52E+04
.24E+02 1.11E+04 1.60E+05 2.05E+05
.96E+02 1.18E+04 8.25E+05 1.03E+06
.24E+03 1.45E+04 1.89E+06 2.92E+06
.72E+03 7.40E+03 5.07E+06 7.99E+06
- .43E+04 7.69E-02 2.32E+06 1.03E+07 O
s O . e' C-23
f TABLE 11 10 INCH RCIC STEAM EXHAUST ' CALCULATED PIPING DOSE RATES ) TIME DOSE RATE INT. DOSE TOTAL INT. HRS R/HR RADS RADS
.10E-09 2.06E+05 .00 .00
.50E+00 6.02E+04 5.93E+04 5.93E+04
.10E+01 3.41E+04 2.30E+04 8.23E+04
.20E+01 1.31E+04 2.19E+04 1.04E+05
.40E+01 2.56E+03 1.29E+04 1.17E+05
.80E+01 1.40E+02 3.33E+03 1.20E+05
.24E+02 3.92E-03 2.14E+02 1.21E+05 i
O e 4 1 e 1 I 3 C- 2 4
i l O TABLE 1m CALCULATED 12 INCH HPCI STEAM SUPPLY PIPING DOSE RATES - l
- TIME DOSE RATE INT. DOSE TOTAL INT. HRS RADS R/HR RADS r .10E-09 ,
4.62E+06 .00 .00
.50E+00 2.25E+05 7.27E+05 7.27E+05
.10E+01 2.14E+04 4.33E+04 7.71E+05
.20E+01 2.28E+02 4.67E+03 7.76E+05
.40E+01 3.50E-02 5.20E+01 7.76E+05 O
4 1 1 a 9 O C- 25
I ZONE 1-
- - - ~ E L. 313*
7,o i 1h l Y.': an
,y:4 ZONE 2 l
I I ?i El' / I,el g,e -.--- p E L. 282* es; l l i $ l
' '!!lj -
y.}l l E L.2ss - - . . - - l.gm l
- f. . l l #2 l
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ZONE 3 ;y[.<
.' ZONE 4 l ZONE 5 y l iT:
l M.3 4.1 j i s- _j. 3- ._ __ - J _ _ - _ -Et. ass-I ZONE 6 ) i l LIMERICK GENERATING STATION UNITS 1 AND 2 SPECIFICATION 8031M-171 l I PRIMARY CONTAINMENT ZONES FIGURE 1 C- 26
iO ! l i 50 - 44 PSIG 40 - 37 PSIG . t ' t =30 SEC 5 vi 30 - Sh E a g 20 - O t. 17 PSIG t =6 HRS 10 - 10 PSIG t =t 36 HRS 4 pg,G t = 11.6 DAYS 0 3 DAYS 11.6 DAYS 180 DAYS 1 MIN 6 HRS 24 HRS 48 HRS
- TIME LIMERICK GENER ATING STATION UNITS 1 AND 2 SPEClFICATION 80314171
- CALCULATED POST LOCA BOUNDING PRIMARY CONTAINMENT PRESSURE PROFILE ,
C-27. FIGURE 2
l l MSLB & LONG TERM hrs 5 $ 8 E $ $ 5 8 _ e_L _.4- i, ,h.,.. i i_
, i.
il {.i 9
._. t.
350 Tin 300 W 3 4
=
W
'1T 200 % ,&
s ei J w I \Ia'I J9w 1EliI I 19s .THEi Ts X 7 J 34
, 5 I All a
8 X s lt' 25 i flhm i
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p . E 5 5 5 I B I B I
.1 .3 1 12 1 1.52 34 e 11.s 23.2 s1 1e0 ; hours DAYS Lit 0ERICK GENERATING STATION UNITS 1 ANO 2 SPECIFICATION 8031 M.171 p
CALCULATED Q , - BOUNDING DRYWELL TEMPERATURE PROFILE FOLLOWING A LARGE. BREAK LOCA C-28 FIGURE 3A
h TIME (hrs) - o b k 350 g 300 L us
>t 3
>=
I %w , g , 'c
' W, 3 250 ,
y a w r
'9,19m 1.
l A ai Isin 200 150
~~ ~ ;-
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--p [ . . . . - . . . . ._ _
. ri -_ .
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.r - - -- - - --
F I. - r ' -- 6 -
-- 6 -8 , - - . - ---- --- - -- .--
100-
! !jjl r[ -{[ [ [ }?j p g. 'g e
pFf
,1 1 2 3 4 58 81012 1 1.52 34 811.6 23.2 81 180 hours DAY _S Lit 4ERICK GENERATING STATION UNITS 1 ANO 2 SPECIFICATION 8031 M-171 I, CALCULATED l BOUNDING DRYWELL
. TEMPER ATURE PRO FILE c-29 FOLLOWING ASMALL BREAK LOCA FIGURE 38
l l l TIME (hrs)
~
w b
's 8 $ 8 l i
I !i t
.n l
~
i ! J l 350 i ggo I il l I 3 I 'I i i i I
, ' i 4
i I ! t . i i i
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.4it 3 %9 Pet W 4 ---
o ,g s. i,M Id TA T 200 v:= i n 5 U na. ir' fTX Im 83 14L enn g y,,_ <----- 9 A" __ l 1 NA e i ?L 150 . xu, I IL' TX a [I' u
'=mmN 11]
<l l I I I I I i 1. I i 100 i; i i i j i j i l i i e
.1 1 2 3 45881912 1 1.3 2 34 811.823.2 81 180 i
hours l DAYS LIMERICK GENERATING STATION UNITS 1 ANO 2 SPEClFICATION 8031-M.171 I' CALCULATED i BOUNDING DRYWELL TEMPERATURE PRO FILE C-30 FIGURE 3C 1 l I l
)
300 - T max = 264* F 250-o E Lu g
~ 200-l >.
4 c: 1 E i s i C) 150 , T=140* F 1 T=120.*Fl. gg , e , , eg, , , , , , , 0 1 2 3 4 5 1 2 3 4 5 6 72 MINUTES HOURS _ I 1 l LIMERICK GENER ATING $TATION
UNITS 1 AND 2 SPECIFICATION 8031.M-171 .
Os
. ISOLATION VALVE COMPARTMENT-l (EL 217) HELB TEMPERATURE PROFILE l ,..
C-32 ., FIGURE 5 l L
4 O APPENDIX D EQUIPMENT QUALIFICATION REVIEW RECORD O L O . b
. - - - --m..- , y .,-..,-....-rw-- . . , .,-, .. , _ - . ,_.-~- -- . - - ...-.--,
DESCRIPTION OF EQRR ENTRIES FACILITY: LGS - Limerick Generating Station UNIT: Provides the Unit Number as 1, 2, or 0 (for common equipment) EQRR: Assigns a unique Environmental Qualification Review Record number for each unique EQ package evaluated PREPARED BY: Indicates the initials of the individual preparing the EQRR DATE: Indicates the date the EQRR was prepared REVIEWED BY: Indicates the initials of the individual responsible for the review of the EQRR DATE: Indicates the date the EQRR was reviewed REVISION DATE: Indicates the date of current revision PLANT ID: Provides Plant ID from Component Classification Program SYSTEM: Provides name of system from Component Classification Program COMPONENT: Provides description of component being qualified l l D-2
~l
O
- ASSOCIATED COMPONENT: Provides description of associated components.
For valves, an "x" followed by a number indicates the associated penetration. MANUFACTURER: Provides name of manuafacturer
- ASSOCIATED MANUFACTURER: Provides name of manufacturer corresponding to the associated component identified above MODEL NUMBER: Provides model number of component
- ASSOCIATED MODEL NUMBER: Provides model number of associated component
- SERIAL NUMBER: Provides serial number of component
- ASSOCIATED S/N: Provides serial number of associated components SERVICE: Provides the service description; indicates the state of the equipment during normal operation FUNCTION: Provides the safety function _ of the equipment.
Indicates for which DBA the equipment is required to perform its S/R function. ACCURACY SPECIFIED: Provides _ the specified accurancy necessary to per. rm the equipment's safety function Demonstrated: Demonstrated provides the demostrated accuracy
Reference:
Provides the reference from which the demonstrated accuracy value was obtained LOCATION: Provides equipment's location
- Entry optional.
~
. . . .~. - -_ . . - -.
- RACK / PANEL For information only
- ASSOCIATED DRAWING: For information only
- PURCHASE ORDER NUMBER For information only 3 SUBMERGENCE: Indicate with a "Yes" if the component is required to be and has bee'. qualified for submergence.
Indicate with a "No" if the component is required
- to be qualified for submergence, but deficiency exists. Indicate with an N/A if the component !s not required to be qualified for submergence.
CHEMICAL SPRAY: Indicate with a "Yes" if the component is required
- to be and has been qualified for chemical spray.
Indicate with "No" if the component is required to be qualified for chemical spray, but deficiences v exist. Indicate with "N/A" if chemical spray is not required. OPERATING TIME: SPECIFIED: Provides the maximum time period I for which the equipment must perform its safety . function based upon FSAR requirements (minutes, hours, days). QUALIFIED: Provides the time period for which the equipment has been demonstrated to perform its safety . function based upon review of , documentation. DOC REF: Provides the documentation references for the specified and qualified values.
- QUAL METHOD
- Provides the qualification !
- j. methods employed. j
- Entry optional.
D-4
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l 4 TEMPERATURE: SPECIFIED: Provides the required maximum temperature that corresponds to the specified operating time given above. Applicability of _ HELB value dependent upon component's require-ment to function during that specific event. For a HELB value, a letter in parentheses identifies the specific HELB per Table 1, Page C6. QUALIFIED: Provides the maximum temperature demonstrated. DOC REF: Provides the documentation references for the specified and qualified values provided above. QUAL METHOD: Provides the qualification methods employed. 1 PRESSURE: SPECIFIED: Provides the required maximum pressure that corresponds to the specified ] (/ operating time given above. Applicability of
- HELB value dependent upon component's require--
i ment to function during that specific event. For a HELB value, a letter in parentheses identifies the I specific HELB per Table 1, Page C6. i QUALIFIED: Provides the maximum pressure - demonstrated. DOC REF: Provides the documentation references for the specified and qualified values provided l -above. j QUAL METHOD: Provides the qualification methods employed. l RELATIVE HUMIDITY: SPECIFIED: Provides the required maximum relative humidity that corresponds to the specified operating time given above. Applicability of
- HELB value. dependent upon component's require-ment to function during that specific event. For a D-5
--- w - , --w -- ,,+-r-,e-
,w,- -r--- . --,,,-e- ,- wn w-
l l HELB value, a letter in parentheses identifies the specific HELB per Table 1, Page D6.
- QUALIFIED
- Provides the maximum relative humidity demonstrated.
-DOC REF: Provides the documentation references for the specified and qualified values, f QUAL METHOD: Provides the qualification
- methods employed.
i t RADIATION: SPECIFIED: Provides the Total Integrated Dose (TID) that corresponds to the 40-year normal radiation TID plus the TID for the required j operating time and function provided above. For j cable or other exposed organics, both gamma and I beta . radiation are specified. The values are f followed by a "G" for_ gamma and "B" for beta radiation. For shielded organics, the gamma j radiation is specified. f QUALIFIED: Provides the maximum radiation ! dose demonstrated. DOC REF: Provides thehumentation references ] for the specified and qualified values provided above. l QUAL METHOD: Provides the qualification 1 methods employed. 1 AGING: SPECIFIED: 40 Years. QUALIFIED: Provides the designated life of the equipment; maximum installed life. 1 DOC REF: Provides the documentation references
- for the specified and designated values provided above.
QUAL METHOD: Provides the evaluation methods employed. D-6
(O OUTSTANDING ITEMS: Indicates any problems or outstanding items, as appropriate INTERFACES: Provides a description of any interfaces used and provides a reference to the applicable EQRR MAINTENANCE REQUIREMENTS: Provides any restricting maintenance requirements and/or provides the documentation reference REMARKS: Provides remarks as appropriate. Any non-conservative deviation for specified values should be noted in the remarks section DEFICIENCY RESOLUTION: Indicates unique deficiency resolutions, as j appropriate o i i Y i ( O D-7
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. l PREPARED BYt DATE: REVISION..D ATE : l_
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, _ ,1 _ _ _ _ . _ _ __ _ -.__ _-- _ - ._-___ _
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- l
~I7ARANTER l ENVIROFMENT _ _ _ _l DOCLHFNTATION REFERENCE ~
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A IHUMIDITY 8%) l I I l I l l l U l = --
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p ,. _ _ _ , g-o I- l l C IAGING l 1 l l l l l l __I I I .I _ I. I I I I IDEFICIENCY RESOLUTION: I l O i i i # I _ . _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ _ 1 1 __ --. q _ O ~ !.--- m.m -- -= = = = = = = = = = = = = = --mmm- m.mm-.m.--m mm-m.mm.--.mm !- mm.m mm-m.m ! e
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