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| Dunn Powim GOMI%NY l'.O. ISOK 33111D CIKAIII.OTTI!. N.O. 213242 O IIAL11.TUCKEll TEt.EPHONE
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| ~~~
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| February 8, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. 3. Adensam, Chief Licensing Brar.ch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
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| ==Dear Mr. Denton:==
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| In response to Ms. Elinor G. Adensam's letter of March 3,1983 and in accordance with the requirements of 10 CFR 50.49 and the Category II guidelines of NUREG-0588, Duke Power Company is providing the following information to demonstrate that electrical equipment required to perform a safety-related function in a harsh environment is appropriately qualified.
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| With regard to the fomat of this submittal, the infomation is arranged as follows:
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| o Introducticn and response to NRC questions on the Catawba Environmental Qualification Program.
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| o Updated response to NUREG-0588 which replaces Duke's previous submittal of June 17, 1982.
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| o Attachment 1 - Summary of Environmental Qualification of Class lE Equipment Located inside Containment o Attachment 2 - Summary of Environmental Qualification of Class lE Equipment Located in the Annulus o Attachment 3 - Summary of Environmental Qualification of Class lE Equipment Located outside Containment and Exposed to HELB Environment o Attachment 4 - Summary of Environmental Qualification of Class lE Equipment Located outside Containment and Exposed to the Post-LOCA Recirculation Radiation Environment o Attachment 5 - Duke Power Company Position on the Category II Guidelines of NUREG-0588
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| 8402090251 840208 PDR ADOCK 05000 A
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| Mr. Harold R. Denton, Director Fet ruary 8,1984 Page 2 Attachments 1, 2, 3 and 4 provide a tabular listing of Class lE equipment exposed to a harsh environment and include appropriate qualification data for the equipment. Attachment 5 provides the Duke Power Company position en the Category II Guidelines of NUREG-0588.
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| Very truly yours, h
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| Hal B. Tucker ROS/php Attachments cc: (w/ attachments)
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| Mr. Richard Boborgen EG&G, Idaho 1520 Sawtelle Street P. O. Box 1625 O Idaho Falls, Idaho 83401 V
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| (w/o attachments).
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| Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
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| Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street Columbia, South Carolina 29205 Mr. Jesse'L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207
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| Catawba Nuclear Station - Units 1 and 2 Environmental Qualification r3
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| ),
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| b In response to an NRC Request for Additional Information dated March 3, 1983 (Elinor G. Adensam to H. B. Tucker) concerning the Catawba environmental qualifi-cation program, Duke Power Company is providing the following information.
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| : 1. Provide a list of safety-related systems containing components in a harsh environment.
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| : a. Compare the systems in (1) above with those described in Table 3.2.2 of the FSAR. Justification should be provided for the exclusion of safety-related system (s) in Table 3.2.2 from the environmental qualification program (e.g., not required for accident mitigation, all components located in a mild environment, etc.). Indicate the Class 1E function (s) perforrr ed by each system.
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| : b. Identify all safety-related components of each system by manufacturer model number and plant component I.D. number. For each component I.D. number specify its specific location in the plant (e.g., room number or room I.D. such as RHR Pump Room, etc.) and its function.
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| : c. For each component, (inside and outside containment, in the annulus and those that are subjected to the post-LOCA recirculation environment) provide qualification information addressing temperature, pressure,
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| (] humidity, radiation, chemicai spray and submergence. If a particular
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| (/ parameter does not apply, make a statement to that effect.
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| : d. Specify the frequency of replacement for components qualified for a period shorter than the design life of the plant. A surveillance and maintenance program that includes a replacement plan should be documented and implemented.
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| ===RESPONSE===
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| Table 1 provides a list of safety-related systems containing equipment required to perform a safety function in a harsh environment. These systems are identified by the system designation (abbreviation), system title, and safety function.
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| It should be noted that for the purposes of this response, Table 1 is based not ,
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| only on the systems identified in FSAR Table 3.2.2-2 (Mechanical Systems) but also on the electrical systems which support the mechanical systems. For design purposes, the plant electrical systems are assigned unique system designations and are therefore identified in Table 1 along with the mechanical systems provided the system has safety-related equipment required to function in a harsh environment.
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| It should also be noted that certain systems which are functionally not safety-related do perform an isolation function. These systems, therefore, contain a limited amount of safety-related equipment and are identified in Table 2 if the safety related equipment is subjected to a harsh environment.
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| i k
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| EL40114E/1 1
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| la. Table 3 reflects a comparison of the systems identified in FSAR Table p 3.2.2-2 and Table 1 and identifies those systems from FSAR Table 3.2.2-2
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| ('' l that are not included in the Catawba harsh environment qualification program. The justification for not including these systems in the harsh environment qualification program is also provided.
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| Ib. The Catawba NUREG 0588 submittal identifies the safety-related electrical equipment located in a harsh environment by generic type, manufacturer, and model number. Where equipment functions can be identified within a generic equipment type and are meaningful from an environmental qualification standpoint, the functions are provided.
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| In terms of location, the Catawba NUREG 0588 submittal is divided into four sections which address the following safety-related equipment locations:
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| : 1) Containment
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| : 2) Annulus
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| : 3) Auxiliary Building - Pipe Rupture Environment
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| : 4) Auxiliary Building - Post LOCA Radiation Environment For the safety-related equipment which is identified by generic type and located in the Auxiliary Building, engineering reviews have determined that the accident environment identified in the Catawba NUREG 0588 equipment tables is the worse case environment applicable to the particular generic equipment type.
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| r3 Equipment specific identification numbers (i.e., tag numbers) are not k) provided in the Catawba NUREG 0588 submittal; however, this level of detail is available for audit in the various Catawba Nuclear Station design documents.
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| Ic. The environmental service conditions for the safety-related electrical equipment located in a harsh environment are identified in the Catawba NUREG 0588 submittal equipment tables. If a given environmental parameter does not apply, it is so noted in the equipment tables and associated notes.
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| Id. The reolacement intervals for electrical equipment required to function in a harsh environment are identified in the Catawba NUREG 0588 equipment tables. The replacement intervals are only identified for that equipment having a service life shorter than the design life of the plant.
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| The Catawba surveillance and maintenance program that includes qualification-mandated equipment replacement requirements is discussed in Catawba Technical Specifications and implemented through station procedures.
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| : 2. Provide a list of TMI Action Plant equipment (by Categories listed in NUREG-0737) currently in your program and its equipment I.D. number. If not in your program, describe the qualification status or your plans for qualification, including the schedule for completion of qualification in acco, dance with NUREG-0588.
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| EL40114U2
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| -g- -- m e e
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| ===RESPONSE===
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| ( Table 4 provides a list of TMI Action Plant electrical equipment required to perform a safety function in a harsh environment. This equipment is grouped according to NUREG 0737 category with information provided concerning qualification status.
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| : 3. The staff's scre ning criteria for radiation levels that result from an accident enviroranent inside containment is 4 X 107 rads total integrated dose (TID). In your June 17, 1982, submittal a value of 1 X 107 TID was used. Because this value is less than the screening criteria, a sample calculation that includes the basis and all assumptions used in determining both gamma and beta radiation levels must be provided.
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| ===RESPONSE===
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| A sample radiation calculation including the bases and assumptions used in determining the radiation levels at Catawba is provided at the end of Attachment 5.
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| : 4. The maximum temperature postulated to exist following a HELB inside containment may be higher than the value (527 F) specified in your June 17, 1982, submittal. This issue must be resolved with the NRC's Containment Systems Branch prior to acceptance by the Equipment Qualification Branch.
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| ===RESPONSE===
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| 4 This matter is currently under review by Duke Power Company and Westinghouse.
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| : 5. Provide a statement that 1E equipment located in areas which experience a significant percent increase in radiation during a LOCA has been reviewed for possible damage to solid states devices and describe the methods of qualification or bases for exemption.
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| ===RESPONSE===
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| Class 1E equipment in general and specifically Class 1E equipnent containing solid state devices have been reviewed for proper radiation qualification. The Class 1E equipment included in the Catawba environmental qualification program is that equipment required to perform a safety function in a radiation environment equal to or greater than 1 X 103 -rads TID. The 1 X 103 rads TID includes the 40 year normal dose plus appropriate accident radiation dose applicable to the equipment location.
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| The qualification method for Class 1E equipment exposed to a harsh radiation environment (> 1 X 103 rads TID) is identified in the Catawba NUREG 0588 submittal equipment tables.
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| : 6. The June 17, 1982, submittal did not always include the appropriate margin (1 hour or 10%) in the qualification data. Qualification data that are acceptable to the staff must include the appropriate margins in accordance with the requirements of NUREG-0588. Use of less than one hour must be C\ justified.
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| V EL40114E/3
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| ===RESPONSE===
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| h)'
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| We have reviewed the Catawba NUREG 0588 submittal (as revised) and have identified one equipment item for which a one hour margin on operability demonstrated is not provided. The equipment item is the pressurizer pressure transmitters (Barton 763, Lot 2). Justification for less than a one hour operability demonstrated margin is provided below.
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| The pressurizer pressure transmitters (Barton 763, Lot 2) provide input to the Reactor Protection System and the Engineered Safety Features Actuation System.
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| For design basis accidents that take credit for the pressurizer pressute reactor trip and safety injection actuation and that result in a harsh containment environment, the transmitters perform their safety function ir, less than 5 minutes. The qualification test for these transmitters demonstrate that the trip accuracy requirement (+10%) is maintained for five minutes and probably much longer although that was not the objective of the qualification program.
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| The qualification program did, however, verify that the transmitters will continue to operate for at least four months post-accident within a relaxed accuracy requirement which provides additional margin for the five minute trip requirement. It should also be noted that once the protectio 1 signal is generated by these transmitters, the signal is locked-in by the protection system and will not reset regardless of the subsequent performance of the transmitters.
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| : 7. Provide information to demonstrate that a flooding and aging analysis is included in your qualification program.
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| Q RESPONSE Flooding (submergence) and aging analyses are included in the Catawba environmental qualification program.
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| With regard to flooding, analyses are performed to identify both the inside containment and the outside containment flood levels. Based on these analyses, the safety-related electrical equipment located below the postulated flood levels is reviewed to determine the effects of submergence. Specially, the equipment is reviewed to determine if it is required to mitigate the event causing the flood (e.g., pipe rupture) or to bring the plant to a safe shutdown.
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| If the equipment is required to function, then submergence qualification is established or the equipment is relocated above the flood level. Safety-related equipment located below a postulated flood level and required to function as noted above is identified in the Catawba NUREG 0588 submittal.
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| With regard to aging, the inservice degradation of safety-related electrical equipment located in a harsh environment is addressed through preventative maintenance and surveillance programs with equipment and component refurbishment and/or replacement based on no susceptibility to aging degradation. These programs are based on qualification test results, manufacturer's recommendations, operating experience, and/or sound engineering practices. Replacement intervals for safety-related electrical equipment located in a harsh environment are identified in the Catawba NUREG 0588 submittal.
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| : 8. A discussion on the effects of beta radiation on components should be
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| ,- included in your qualification program.
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| I I
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| \- / RESPONSE The safety-related electrical equipment including cables that are located inside the containment and required to perform a safety function in the harsh containment environment have been reviewed for the effects of beta radiation.
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| Based on our review we have determined that there is no safety-related electrical equipment located inside the containment that is susceptible to beta radiation degradation.
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| : 9. The submittal should address the environmental qualification of safety-related mechanical equipment located in a harsh environment.
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| ===RESPONSE===
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| The environmental qualification of safety-related mechanical equipment located in a harsh environment is addressed in a separate submittal.
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| ,y C )
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| '\, //
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| V
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| TABLE 1 V Safety-Related Systems Containing Equipment Required to Function in a Harsh Environment SYSTEM SYSTEM SYSTEM ABBREVIATION TITLE SAFETY FUNCTION CA Auxiliary Feedwater Core Cooling FW Refueling Water Core Cooling KC Component Cooling Equipment Cooling NC Reactor Coolant Core Cooling ND Residual Heat Removal Core Cooling NF Ice Condenser Refrigeration Containment Heat Removal NI Safety Injection Core Cooling NS Containment Spray Containment Heat Removal NV Chemical and Volume Control Core Cooling RN Nuclear Service Water Supporting System SA Main Steam to Auxiliary Core Cooling Equipment VA. Auxiliary Building Post-Accident Clean-Up Ventilation VC Control Area Air Conditioner Supporting System VD Diesel Building Ventilation Heat Removal (N VE Annulus Vent Prevent Radioactive Release Q) YC VX Control Area Chilled Water Containment Air Return and Heat Removal Containment Heat Removal Hydrogen Skimmer EMF Radiation Monitoring Radiation Detection EPC 4160V ac Essential Supporting System Auxiliary Power EPE 600V ac Essential Supporting System Auxiliary Power EPG 240/120V ac Vital I and C Supporting System Power EPY 120/240V ac Essential Supporting System Auxiliary Power EZA Electrical Penetrations Supporting System EL40114E/6
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| TABLE 2 O Non Safety-Related Systems Containing Safety-Related Equipment Required to Function in a Harsh Environment to Provide an Isolation Function SYSTEM SYSTEM ABBREVIATION TITLE BB Steam Generator Blowdown CF Feedwater System NM Nuclear Sampling System RF Interior Fire Protection SM Main Steam SV Main Steam Vent to Atmosphere VB Breathing Air VI Instrument Air VP Containment Purge VQ Containment Air Release and Addition VY Containment Hydrogen Sample and Purge YM Make-up Demineralizer Water O
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| O EL40114E/7 Iig -
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| TABLE 3 O Comparison of Table 1 Systems to FSAR Table 3.2.2-2 SYSTEM SYSTEM REASON FOR ABBREVIATION TITLE EXCLUSION FROM TABLE 1 AD Standby Shutdown Non-Safety Diesel AS Auxiliary Steam Non-Safety BW Steam Generator Manual Wet Layup Recirculation Valves (Locked Closed)
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| CM Condensate Mild Environment CS Condensate Storage Mild Environment FD Diesel Generator Engine Mild Environment Fuel Oil GH Hydrogen Non-Safety GN Nitrogen Non-Safety GS Hydrogen Bulk Stoarge Non-Safety KD Diesel Generator Cooling Mild Environment Water KF Spent Fuel Cooling Mild Environment KR Recirculated Cooling Hon-Safety Water LD Diesel Generator Lube Oil Mild Environment NB Boron Recycle No active mitigating function NR Boron Thermal Regeneration No active mitigating function RC Condenser Circulating Non-Safety Water RL Conventional Low Pressure Non-Safety Service Water RY Exterior Fire Protection Non-Safety O
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| EL40114E/8
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| TABLE 3 (Cort'd)
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| O Comparison of Table 1 Systems to FSAR Table 3.2.2-2' SYSTEM SYSTEM REASON FOR ABBREVIATION TITLE EXCLUSION FROM TABLE 1 SB Main Steam Bypass to Non-Safety Condensate VG Diesel Generator Engine Mild Environment Starting Air VJ Computer Area Air Non-Safety Conditioner VN Diesel Generator Engine Mild Environment Air and Exhaust VV Containment Ventilation Non-Safety VZ Nuclear Service Water Mild Environment Pump Structure Ventilation WC Conventional Waste Water Non-Safety O Treatment WE Equipment Decontamination Manual Valves TE Feedwater Pump Turbine No accident mitigating Exhaust function WG Gaseous Waste Disposal No active mitigating function WL Liquid Radwaste No active mitigating function WN Diesel Generator Room Mild Environment Sump Pump WP Turbine Building Sump Non-Safety Pump WS Solid Radwaste No active mitigating function WZ Groundwater Drainage Mild Environment O
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| EL40114E/9
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| TABLE 3 (Cont'd)
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| O Comparison of Table 1 Systems to FSAR Table 3.2.2-2 SYSTEM SYSTEM REASON FOR ABBREVIATION TITLE I EXCLUSION FROM TABLE 1 YA Conventional Chemical Non-Safety Addition YD Drinking Water System Non-Safety YJ Co;nputer Area Chilled Non-Safety Wats.
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| ZD Diesel Generator Engine Mild Environment Crankcase Vacuum O
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| O EL40114E/10 I
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| TABLE 4
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| /~ ; ,
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| NUREG 0737 Safety-Related Equipment Located in a Harsh Environment
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| '0737 SECTION/ QUALIFICATION DESCRIPTION EQUIPMENT STATUS II.B.1 Reactor limitorque Motor See Attachment 1 Coolant' System Vents Operated Valve Page 15 SMB II.B.3 Post-Accident ~ Valcor Solenoid See Attachment 1 Sampling Valves Page 18a V70900-21-3 1I.0.3 Relief and Safety TEC Value Flow See Attachment 1 Valve Position Indication Monitor System Page 10
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| -Accelerameter-2273A
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| -Charge Converter-504A
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| -Transient Shield-160-2
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| -Cable-2273-C2 II.E.1.2 Auxiliary Feedwater Flow Transmitter See Attachment 3 System Automatic Initiation Barton 764 Page 6 O,
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| s_, 'and Flow Indication II.F.1 Additional Pressure Transmitter See Attachment 4 Accident Monitoring Rosemount 1153 Page 4
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| . Instrumentation High Radiation See Attachment 1 Detectors General Page 11 Atomic RD-23 II.F.2 Instrumentation RID-MINC0 See Attachment 1 for Detection of S8609, S8810 Page Sa
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| -Inadequate Core Cooling Mineral Insulated See Attachment 1 Thermocouple Cables and Page 38 Connectors O
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| m EL40114E/11 u ___ _ __--_-____---__._ _
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| l q CATAWBA NUCLEAR STATION - UNIT 1 AND UNIT 2
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| ==SUMMARY==
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| OF ENVIRONMENTAL QUALIFICATION OF CLASS lE EQUIPMENT EXPOSED TO A HARSH ENVIRONMENT The NRC has established in NUREG-0588 the requirements which applicants must meet in order to satisfy General Design Criterion 4 relating to the environmental qualification of Class lE equipment. Basically, the requirements are as follow:
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| : 1. Provide a table listing by generic type all Class lE equipment exposed to a harsh environment including the appropriate qualification data for the equipment.
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| : 2. Review the adequacy of the environmental qualification for the equipment identified in Item 1 above with respect to the NRC Staff's position described in NUREG-0588, document the degree of conformance, and justify any deviation.
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| In response to these requirements, Duke Power Company is providing the following:
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| e Attachment 1 - Summary of Environmental Qualification of Class 1E Equipment Located inside Containment
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| -[ ') e Attachment 2 - Summary of Environmental Qualification of Class lE
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| 's/ Equipment Located in the Annulus e Attachment 3 - Summary of Environmental Qualification of Class lE Equipment Located outside Containment and Exposed to the Post-LOCA Recirculation Radiation Environment e Attachment 5 - Duke Power Company Position on the Category II Guidelines of NUREG-0588 Attachments 1, 2, 3 and 4 provide a tabular listing of Class lE equipment exposed to a harsh environment and include appropriate qualification data for the equipcent. Attachment 5 provides the Duke Power Company position on the Category II Guidelines of NUREG-0588.
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| O U
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| SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS lE EQUIPMENT LOCATED INSIDE CONTAINMENT Pg Rev. M Rev. Pm Rev.
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| 1 1 2 1 3 1 4 1 5 1 Sa 0 6 1
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| '7 1 8 1 9 1 10 1 11 1 12 1 13 1 14 1 -
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| 15 1 O- 16 17 18 1
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| 1 1
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| 19 1 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1-32 1 33 1 34 1 35 0 36 0 37 0 38 0 CN-1 1 CN-2 1 A
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 1 l
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| ==SUMMARY==
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| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT l EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 763 l (1) Pressurizer Pressure (NSSS) (Lot 2)
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| , (Lower Containment) l l
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| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED .TN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% C~ SPAN)
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| ENVIRONMENT Temp: 327 F Temp: 380 F SI Initiation >5 minutes + 10% Max. er: or 7.7%
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| Press: 14.4 psig Press: 75 psig (<5 minutes) post DBE (5 minutes)
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| RH: 100% RH: 100%
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| Rad: 1X107R Rad: 5X107R Chem Spray: Boric Ci.am Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.
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| 2750 ppm Boron 8.5 pH SUBMERGENCE: No QUALIFICATION REPORT: WCAP 9885 METHOD: Test REPLACEMENT INTERVAL: 10 years ECSE
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page'2
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| ==SUMMARY==
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| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUlf MENT .ID: fransmitter - MANUFACTURER: Barton MODEL #: 764 (1) Pressurizer Level (NSSS) (Lot 2)
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| (Lower. Containment)
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| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
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| ENVIRONMENT i
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| Temp: 327 F Temp: 380 F 2 weeks 2 weeks i 25% Max. error 15%
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| Press: 14.4 psig Press: 75 psig post-DBE post DBE l RH: 100% RH: 100%
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| Rad: SX107R Rad: SX107R Chem Spray: Boric Chem Spray: Boric i acid and sodium acid and sodium tetraborate soln. hydroxide soln.
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| 2750 ppm Boron 8.5 pH SUBMERGENCE: No i QUALIFICATION REPORT: WCAP 9885 METHOD: Test 10 years ECSE REPLACEMENT INTERVAL:
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 3 l Rev. 1
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| ==SUMMARY==
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| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Veritrak MODEL #: 76DP (1) RCS Flow (NSSS)
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| (Lower Containment) l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY l DEMONSTRATED l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
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| ENVIRONMENT l
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| I The RCS Flow signals are not required for accidents that cause a change in the normal containment operating environment.
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| 1 Further, failure of these transmitters as a result of exposure to a harsh environment will not pt eclude the safety function of other equipment claimed in the accident analysis. Additionally, the information provided by these transmitters is not employed as a post accident monitoring parameter for operator action.
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| SUBMERGENCE: N/A QUALIFICATION RFPORT: N/A METHOD: N/A ECSE REPLACEMENT INTERVAL: N/A
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 4 l
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| ==SUMMARY==
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| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 :
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| LOCATED INSIDE CONTAINMENT l
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| l EQUIPMENT ID: RID - MANUFACTURER: RdF Corp. H0 DEL #: 21204 l l
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| l (1) RCS Temperature (NR)
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| (Lower Containment) l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
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| , (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) 1 ENVIRONMENT l
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| Temp: 327 F Temp: 420 F Reactor Trip 16 days i 0.2% 1 0.0%
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| Press: 14.4 psig Press: 55 psig (<5 minutes) post SLB RH: 100% RH: 100%
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| Rad: 1X108R Rad: 2.25X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydror.ide soln.
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| 2500 ppm Boron 0.24% NaOH 10.7 pH SUBMERGENCE: Yes (Note 3)
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| QUALIFICATION REPORT: WCAP 8687, Supp. 2. E05A-ESE-5 METHOD: Test REPLACEMENT INTERVAL: 20 years ECSE t ,
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 5
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| ==SUMMARY==
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| OF ENV.TRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 L0t,aTED INSIDE CONTAINMENT EQUIPMENT ID: RTD - MANUFACTURER: RdF Corp. MODEL #: 21205 (1) RCS Temperature (WR) (NSSS)
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| (Lower Containment)
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| ACCIDENT ENVIRCNMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICil REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED l (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) l
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| ' l ENVIRONMENT Temp: 327 F Temp: 420 F 2 weeks 4 months 1 0.2% 0.0%
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| Press: 14.4 psig Press: 55 psig post DBE post DBE Ril: 100% RH: 100%
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| Rad: 1X10sR Rad: 2.25X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid ard sodium tetraborate soln. hydroxide soln.
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| 2500 ppm Boror.
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| 0.24% Na0H 10.5 pH SUBMERGENCE: Yes (Note 4)
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| QUALIFICATION REPORT: WCAP 8687, Sup. 2, E06A-ESE-6 METHOD: Test REPLACEMENT INTERVAL: 10 years ECSE
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page Sa SUM 4ARYOFENVIRONMENTALQUALIFICATIONOFCLASS1EEQUIPMENT Rev. 0 LOCATED INSIDE CONTAINMENT
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| (
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| EQUIPMENT ID: -RTD - Temp. Comp. P.VLIS MANUFACTURER: MINC0 MODEL #: S 8809 (1) S 8810 ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
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| ENVIRONMENT Temp: 327 F Temp: 420 F 4 months 4 months i 1.19% i . 2%
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| Press: 14.4 psig Press: 75 psig Post DBE RH: 100% RH: 100%
| |
| Rad: 1X107R Rad: 1.6X10 8R Chem Spray: Boric 2750 PPM acid and sodium H3803 Na0H tetraborate soln. to 10.7 pil l
| |
| SUBHERGENCE: Yes (Note 4)
| |
| QUALIFICATION REPORT: EQDP-ESE-42 WCAP-8687, Supp. 2, E-42A (CNM-1399.03-357)
| |
| METHOD: Test REPLACEMENT INTERVAL: 10 years ECSE
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 6 l
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l LOCATED INSIDE CONTAINMENT I EQUIPMENT ID: Differential Pressure MANUFACTURER: Barton MODEL #: 581A-1 (1) Switch l Supply Header Flow to Reactor i
| |
| Coolant Pumps (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIREU IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327 F Temp: 340 F 1 year 1 year i 15% i 12.3%
| |
| Press: 14.4 psig Press: 72 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.3x108R Rad: 2x108R Chem Spray: Boric Chem Spray:
| |
| acid and sodium 3000 ppm tetraborate soln. pH: 10.5 SUBMERGENCE: No QUALIFICATION REPORT: Barton Report # 548-8890 Rev. A METHOD: Test REPLACEMENT INTERVAL: 18 years
| |
| | |
| . . . 1 CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 7 l
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT i EQUIPMENT ID: Differential Pressure MANUFACTURER: Solon MODEL #: 7PS11DW (1) Switch (Upper Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT l
| |
| Temp: 180 F Later Later Later Later Later
| |
| ! Press: 14.4 psig RH: 100%
| |
| Rad: Later Chem Spray: Boric acid and sodium tetraborate soln.
| |
| SUBMERGENCE: Later QUALIFICATION REPORT: Later METHOD: Later REPLACEMENT INTERVAL: Later MHVC
| |
| | |
| . . . l l l l
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 8
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| ! LOCATED INSIDE CONTAINMENT l EQUIPMENT ID: Limit Switches MANUFACTURER: NAMC0 MODEL #: EA-180 and EA-740 l (1) (Lower Containment) l l
| |
| ACCIDENT ENVIRONMENT OPERABILIT) OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED l (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) l ENVIRONMENT l
| |
| i Temp: 327 F Temp: 340 F 5 minutes 30 days N/A N/A Press: 14.4 psig Press: 70 psig post DBE Ril: 100% RH: 100%
| |
| Rad: 1X108R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.
| |
| 3000 ppm Boron 10.5 pH SUBMERGENCE: Yes (Note 5)
| |
| QUALIFICATION REPORT: NAMC0 Test Reports dated September 5, 1978 (CNM-1205.19-0041) i METil0D: Test REPLACEMENT INTERVAL: 4 years MEQP
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 9
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 i LOCATED INSIDE CONTAINMENT l EQUIPMENT ID: Limit Switches MANilFACTURER: NAMC0 MODEL #: EA-740 (1) (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT l
| |
| t Temp: 327 F Temp: 340"F 5 minutes 30 days N/A N/A i Press: 14.4 psig Press: 70 psig RH: 100% RH: 100%
| |
| Rad: 1x108R Rad: 2x108R Chem Spray: Boric Chem Spray: Boric acid acid and sodium and sodium hydroxide soln.
| |
| tetrabore.te soln. 3000 ppm Boron 10.5 ph SUBMERGENCE: Yes (Note 5)
| |
| QUALIFICATION REPORT: NAMC0 Test Report dated February 22, 1979 (CNM-1205.19-0041)
| |
| METHOD: Test REPLACEMENT INTERVAL: 4 years MEQP
| |
| | |
| O O O
| |
| , CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 10
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Safety Valve Position MANUFACTURER: TEC MODEL #: 2273A Accelerometer (1) Indication Sensors, Charge -
| |
| 504A Charge Converter Aras and Cables 160-2 Transient Shield (Lower Containment) 2273-C2 Cable Assembly i
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED I
| |
| (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT I
| |
| j Terp: 327 F Temp: 510 F 2 weeks 1 month N/A N/A
| |
| : Press: 14.4 psig Press: 85 psig post DBE post DBE i RH: 100% RH: 100%
| |
| : Red: 8X107R Rad: 2X108R I Chea Spray: Boric Chem Spray: Boric
| |
| ; acid and sodium acid and sodium
| |
| ; tatraborate soln. hydrazine and sodium i phosphate soln.
| |
| i 13,000 to 14,000 ppm i
| |
| 7-7.5 pH i SUBMERGENCE: No i
| |
| j QUALIFICATION REPORT: Tec Report 517-TR-03 Rev. 2 (CNM-1346.17-09 through 14) j METHOD: Test J
| |
| l REPLACEMENT INTERVAL: 4 years (Charge Converter Only) ECSE l
| |
| /
| |
| i i
| |
| | |
| l . . .
| |
| i
| |
| )
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 11
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: High Radiation MANUFACTURER: General Atomic Co. MODEL #: RD-23 (1) Detectors (Lower Containment)
| |
| ACCIDENT ENVIRONMENT DPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% GF SPAN)
| |
| ENVIRONMENT Temp: 240 F Temp: 315 f 1 year 1 year (Note 7) (Note 7)
| |
| Press: 14.4 psig Press: 77 psig post LOCA post LOCA RH: 100% RH: 100% (Note 6)
| |
| Rad: 1X108R Rad: Note 6 Chem Spray: Boric Chem Sprey: Boric acid and sodium acid and sodium tetraborate soln. thiosulfate and sodium hydroxide soln.
| |
| 3000 ppm Boron 10.5 pH SUBMERGENCE: No QUALIFICATION REPORT: GA Report E-254-960 METHOD: Test / Analysis N/A ECSE REPLACEMENT INTERVAL:
| |
| | |
| O O O \
| |
| I l
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 12 l l
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 ;
| |
| 1 LOCATED INSIDE CONTAINMENT ,
| |
| EQUIPMENT ID: Coaxial Cable for High MANUFACTURER: Rockbestos MODEL #: RSS-6-104-1081 (1) Radiation Detectors l (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 240 F Temp: 315 F 1 year 1 year N/A N/A Press: 14.4 psig Press: 77 psig post LOCA post LOCA RH: 100% RH: 100% (Note 6)
| |
| Rad: 1X108R Rad: 2.0x10 8R i Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. thiosulfate and sodium hydroxide soln.
| |
| 3000 ppm Boron 10.5 pH SUBMERGENCE: No QUALIFICATION REPORT: Rockbestos Report 2806 (Appendix 5 of G.A. Report E-254-960)
| |
| METHOD: Test / Analysis N/A ECSE REPLACEMENT INTERVAL:
| |
| | |
| 9 O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 13
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPHENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Excore Neutron MANUFACTURER: Westinghouse M3]EL #: WL-23686 4 (1) Detector (Power Range) (NSSS) l l
| |
| (Lower Containment) l l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT The Power Range Neutron Detectors are not required for accidents that cause a change in the normal containment operating environment. Further, failure of these detectors as a result of exposure to a harsh environment will not preclude the safety function of other equipment claimed in the accident analysis. Additionally, the information provided by these detectors is not employed as a post accident monitoring parameter for operator action. The flux monitoring instrumentation required per Regulatory Guide 1.97 will be provided by other equipment to be added at a later date.
| |
| SUBMERGENCE: N/A QUALIFICATION REPORT: N/A METHOD: N/A REPLACEMENT INTERVAL: N/A ECSE
| |
| | |
| i l
| |
| 1 l CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 14 l
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork HODEL #: NA-1 '
| |
| i j (1) (Lower Containment) i I
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327*F Temp: 340 F 30 days 30 days N/A N/A Press: 14.4 psig Press: 70 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1X108R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. thiosulfate, and sodium bydroxide soln.
| |
| 3000 ppm Boron 10.5 pH SUBMERGENCE: Yes (Note 5)
| |
| QUALIFICATION REPORT: N11/4, (December 1970); N14/2 (May 1970); IR116 (November 1973); TR222 (May 1972); 43979-1 (December 1978); TR.'78 (December 1974) (CNM-1205.19-6, -7, -8, -11, -15, -19)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MEQP s
| |
| | |
| e o e i
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 15
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT SMB EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: RH Motor Insulation (1) (Lower Containment) l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT 1
| |
| Temp: 327 F Tenp: 340*F 30 days 30 days N/A N/A Press: 14.4 psig Press: 105 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1X108R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid, and sodium tetraborate soln. hydroxide soln.
| |
| 3000 ppm Boron pH: 10.5 SUBMERGEN F: Yes (Note 5)
| |
| QUALIFICATION REPORT: Limitorque Report 600-376-A, September 1972; 600-456, December 1975 (CNM-1205.19-0001)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MEQP p
| |
| | |
| p
| |
| \.
| |
| Q V
| |
| f%
| |
| d CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 16
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT 'Rev. 1 4 LOCATED INSIDE CONTAINMENT i EQUIPMENT ID: Containment Air Return Fan MANUFACTURER: Ro ork MODEL #: 11 NAZI (1) Isolation Damper Motor Operators (Upper Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% CF SPAN)
| |
| ENVIRONMENT Te:p: 180 F Temp: 385 F 5 minutes 30 days N/A N/A Press: 14.4 psig Press: 75 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1X10sR Rad: 2X108R Cham Spray: Boric Chem Spray: Boric acid and sodium acid, and sodium tetraborate soln. hydroxide soln.
| |
| 6200 ppm Boron 9.5 pH SUBMERGENCE: No l
| |
| l QUALIFICATION REPORT: W'le f Report 43979-1 (CNM-1211.00-1076) l l METHOD: Test l
| |
| REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 17 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINHENT EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V526 (1) (Lower Containment) ,
| |
| 1 ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED :
| |
| (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT l
| |
| l Temp: 327 F Temp: 346 F 30 days 31 days N/A N/A Press: 14.4 psig Press: 113 psig post DBE l
| |
| RH: 100% RH: 100% *
| |
| ! Rad: 2X108R Rad: 1X108R l Ch:m Spray: Boric Chem Spray: Boric acid and sodium acid, and sodium tetraborate soln. hydroxide soln.
| |
| 9.5 - 10.5 pH l
| |
| l SUBMERGENCE: Yes (Note 5) l l QUALIFICATION REPORT: Valcor Report QRS2600-6042-1 (CNM-1205.08-0047)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A .MEQP
| |
| | |
| ( .
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 .
| |
| Page 18 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1' LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V70900-21-3 (1) (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERA 81LITY- GPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327 F Temp: 346 F 5 minutes 2 days N/A N/A Press: 14.4 psig Press: 113 psig post DBE post DBE i RH: 100% RH: 100% (Isolation l Rad: 1X108R Rad: 2X108R function-Deenergize Ch:2 Spray: Boric Chem Spray: Boric upon receipt of safety acid and sodium acid, and sodium signal) tetraborate soln. hydroxide soln.
| |
| 1720-2200 ppm Boric l acid 9.5 - 10.5 pH SUBMERGENCE: Yes (Note 5)
| |
| QUALIFICATION REPORT: Valcor Reports QR-52600-515, Rev. B; QR-70900-21-1, Rev. A; MR-70905-21-3-1 (CNM-1210.04-119, 253, 254
| |
| & MCM-1210.04-119)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: 5 years MPIC
| |
| '~ ' ' " ' ' ' '
| |
| | |
| f (%
| |
| \ 'u) . (J')
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 18a
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Valve Solenoid Ope'aiors MANUFACTURER: Valcor MODEL #: V70900-21-3 (1)' (Upper & Lower Corcainment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERADILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED. ACCIDENT (% OF SPAN) (% OF SPAN) ,
| |
| ENVIRONMENT l l
| |
| Terp: 327 F Later 1 year Later N/A' N/A l Press: 14.4 psig post DBE i RH: 100% (Sample function-Rad: 1X108R periodically energized ,
| |
| Chem Spray: Boric for containment atmosphere acid and sodium sample selection - H2 ) l l
| |
| SUBMERGENCE: No QUALIFICATION REPORT: Later 1
| |
| I METHOD: Later l
| |
| REPLACEMENT INTERVAL: Later
| |
| | |
| e ~s m
| |
| % s CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 19 SUPNARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: ASCO MODEL #: NP831655E (1) (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327*F Temp: 346*F 5 minutes 30 days N/A N/A Press: 14.4 psig Press: 70 psig post DBE post DBE I i RH: 100% RH: 100% (Isolation l 1.5X108R function)
| |
| Rad: 1.1X108R Rad: l Chea Spray: Boric Cham Spray: Boric
| |
| <scid and sodium acid, sodium tetraborate soln. thiosulfate, and sodium hydroxide l b pp:a 10 pH l
| |
| l SUBHERGENCE: No l
| |
| l l QUALIFICATION REPORT: ASCO Report AQS21678/TR, Rev. A, July 1979 (CNM-1205.02-0499)
| |
| METHOD: Test REPLACEMENI INTERVAL: N/A MEQP
| |
| | |
| CATAWBA NUCLEAR STATION - Ui4ITS 1 AND 2 Page 20
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Electric Hydrogen MANUFACTURER: Westinghouse /Sturtevant MODEL #: B ,
| |
| (1) Recombiner (NSSS)
| |
| (Upper Containment) i ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT
| |
| , Temp: 180 F Temp: 288 F 3 months 1 year N/A N/A I
| |
| Press: 14.4 psig Press: 77 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 8.1X107R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.
| |
| 2550 ppm Boron 9 - 10.5 pH SUBMERGENCE: No QUALIFICATION REPORT: WCAP-7709-L and Supp. 2, 3, 4, 5, 6, and 7 flETHOD: Test / Analysis REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| I h(Mh 0
| |
| +*p IMAGE EVALUATION ((/ g$ 4,
| |
| /
| |
| j/* TEST TARGET (MT-3) l.0 'FM Bu i E 9 Els 1.1 ,
| |
| EE i.8 l
| |
| [ I.25 1.4 1.6 1 =
| |
| 4 150mm >
| |
| < 6" ?
| |
| *e 4% /<$
| |
| s4;J;f+4 4
| |
| +?ig>A fffff ,, <p>
| |
| offfff x .
| |
| | |
| #@ M O Y *,k (( b#
| |
| g IMAGE EVALUATION
| |
| ,EE,, - ,,., ,
| |
| g$ ' 4, ,
| |
| 1.0 E E La DE ll E
| |
| ! T'5 En 1.8 1.25 1.4 1.6 4 150mm >
| |
| < 6" >
| |
| #% + sp
| |
| *$f%;' I? jf
| |
| ),y h ,
| |
| si,
| |
| .s _
| |
| | |
| D C\
| |
| V J (V i
| |
| CATAWBA NUCLEAR STATION - UNITS 1. AND 2 Page 21
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT i
| |
| . EQUIPMENT ID: Containment Air Return MANUFACTURER: Joy / Reliance MODEL #: 1XF-882739 (1) Fan Motors (Upper Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH RE(UIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT
| |
| , Temp: 180 F Temp: 350 F 2 months 1 year N/A N/A Press: 14.4 psig Press: 85 psig post DBE post DBE RH: 100% RH: 100%
| |
| ! Rad: 1.1X108R Rad: 1x109R Chea Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. hydroxide and sodium thio-i sulfate soln.
| |
| 3000 ppm Boron 10.5 pH SUBMERGENCE: No QUALIFICATION REPORT: Joy / Reliance Reports X-604 (CNM-1211.00-1009); NUC-9 (CNM-12il.00-1010)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| p t'%g
| |
| \,,/ L V CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 22
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Hydrogen Skimmer MANUFACTURER: Joy / Reliance MODEL #: 1XF-882747 (1) Fan Motors (Upper Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY . OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH RE(JIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT
| |
| , Temp: 180 F Temp: 350 F 2 months 1 year N/A N/A l
| |
| Press: 14.4 psig Press: 85 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.1X108R Rad: 2X108R 2 Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium j tetraborate soln. hydroxide and I
| |
| sodium thio-sulfate soln.
| |
| 3000 ppm Boron 10.5 pH
| |
| ! SUBMERGENCE: No j QUALIFICATION REPORT: Joy / Reliance Report X-604 (CNM-1211.00-1009), NUC-9 (CNM-1211.00-1010) l
| |
| \
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 23 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Electrical Penetrations MANUFACTURER: D. G. O'Brien Inc. MODEL #: Type A (1) Detectors (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327 F Temp: 340 F 1 year 1 year N/A N/A Press: 72 psig Press: 72 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.3x108R Rad: 2x108R NOTE: Type A must maintain mechanical Ch:m Spray: Boric Chem Spray: Boric leaktight integrity and must acid and sodium acid and sodium function electrically tetraborate soln. thiosulfate and sodium hydroxide soln.
| |
| 4000 ppm Boron 8.8 pH SUBMERGENCE: No QUALIFICATION REPORT: D G O'Brien, Inc. Qualification Report No. ER-247 (CNM-1361.00-0015)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O i
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 24 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT k
| |
| I EQUIPMENT ID: Electrical Penetrations MANUFACTURER: .D. G. O'Brien MODEL #: Types B, C, D, F, G, i (1) (Lower Containment) H, J, K, L, and M l
| |
| I
| |
| : ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| ! ENVIRONMENT TO WHICH
| |
| ' REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) 3 ENVIi'ONMENT Temp: 327 F Temp: 340*F 1 year 1 year N/A N/A Press: 14.4 psig Press: 15 psig post DBE post DBE
| |
| { RH: 100% RH: 100%
| |
| Rad: 1.3X10sR Rad: 2X108R NOTE: All types must maintain leaktight integrity.
| |
| j Ch:m Spray: Boric Chem Spray: Boric acid and sodium acid and sodium NOTE: Types B, C, D, F, G, H, K and M must function electrically.
| |
| l tetraborate soln. hydroxide soln.
| |
| t 4000 ppm Boron
| |
| ) 8.8 pH SUBMERGENCE: No i
| |
| QUALIFICATION REPORT: D. G. O'Brien, Inc. Qualification Report No. ER-268 (CNM-1301.00-0074) NOTE: Additional testing presently in progress.
| |
| Wyle Laboratories Qualification Report No. 45869-1 D. G. O'Brien, Inc. Qualification Report No. ER-252 (CNM-1361.00-0016)
| |
| I METHOD: Test / Analysis i
| |
| i REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 25
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT
| |
| ! Electrical Penetrations EQUIPMENT ID: MANUFACTURER: Conax Corporation MODEL #: Type N (1) (Lower Containment)
| |
| , ACCIDENT ENv1RONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| ; (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) -
| |
| ENVIRONMENT i
| |
| i l Terp: 327 F Temp: 350 F 1 year 1 year N/A N/A
| |
| ; Press: 72 psig Press: 72 psig post DBE post DBE i RH: 100% RH: 100%
| |
| i Rad: 1X108R Rad: 1x108R i Chem Spray: Boric Chem Spray: Boric acid and sodium acid l tetraborate soln. 1800-2000 ppm Boron j 6-10 pH 2
| |
| SUBMERGENCE: No QUALIFICATION REPORT: Conax Qualification Report No. IPS-1037 (CNM-1361.00-0038) l i
| |
| j METHOD: Test / Analysis l
| |
| ! REPLACEMENT INTERVAL: N/A
| |
| 't .
| |
| 4 m
| |
| | |
| /''i O D V V .
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 26
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR (1) Hookup Wire Insulation (Procurement (Lower Containment) Spec: CNS-1354.04-00-0006)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IH DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327 F Temp: 385 F 4 months 5 months N/A N/A Press: 14.4 psig Press: 66 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.3X108R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. phosphate, and hydrazine soln.
| |
| 6200 ppm Boron 8.6 - 10 pH SUBMERGENCE: No QUALIFICATION REPORT: F-C4836-4 and 80282 (CNM-1354.00-6017 and 0025)
| |
| METil0D: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| 9 *
| |
| (Q
| |
| (&
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 27
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: EPR
| |
| ; (1) Medium Voltage Power Insulation (Procurement
| |
| : (Lower Containment) Specs: CNS-1354.01-00-0001
| |
| ! & 0003)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT I
| |
| Temp: 327 F Temp: 346*F 4 months 4 months N/A N/A Press: 14.4 psig Press: 113 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.3X10sR Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. thiosulfate and i
| |
| sodium hydroxide soln.
| |
| 3000 ppm Boron 9 - 11 pH SUBMERGENCE: Yes QUALIFICATION REPORT: F-C4350-3 (CNM-1354.00-0003) j METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O ,O V v [v''\
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 28
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR (1) Control Insulation (Procurement (Lower Containment) Specs: CNS-1354.02-00-0001
| |
| & 0002) l j
| |
| ) ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY i ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327 F Temp: 385 F 4 months 5 months N/A N/A Press: 14.4 psig Press: 66 psig post DBE post DBE
| |
| ! RH: 100% RH: 100%
| |
| I Rad: 1.3X108R Rad: 2X108R l Chem Spray: Boric Chem Spray: Boric j acid and sodium acid, sodium j tetraborate soln. phosphate, sodium
| |
| : hydroxide and hydrazine soln.
| |
| 6200 ppm Boron 8.6 - 10 pH SUBMERGENCE: Yes i
| |
| 4 QUALIFICATION REPORT: F-C4969-1 and 80282 (CNM-1354.00-0009, CNM-1354.00-0025)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS 8
| |
| | |
| O O O l- CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 29
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| } LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR (1) Instrumentation and Control Insulation (Procurement 1 (Lower Containment) Specs: CNS-1354.03-00-0001, 06 ?' & 0003)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT
| |
| ! Tcap: 32? F Temp: 385 F 4 months 5 months N/A N/A Press: 14.4 psig Press: 66 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.3X108R Rad: 2X10sR Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium i tetraborcte soln. phosphate, and hydrazine soln.
| |
| 4 6200 ppm Boron 8.6 - 10 pH SUBMERGENCE: Yes QUALIFICATION REPORT: F-C4836-2 and 80282 (CNM-1354.00-0020, CNM-1354.00-0025)
| |
| METHOD: Test / Analysis l
| |
| 4 l
| |
| t l REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| : O O O 2
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 30 SUMARY OF ENVIRONMENTAL-QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l LOCATED INSIDE CONTAINMENT
| |
| ) EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL ): XLPE Insulation (1) Coaxial (Procurement j (Low = Containment) Spec: CNS-1354.04-00-0004)
| |
| * ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) j ENVIRONMENT l Temp: 327*F Temp: 385 F 4 months 5 months N/A N/A i Press: 14.4 psig Press: 113 psig post DBE post DBE RH: 100% RH: 100%
| |
| Rad: 1.3X108R Rad: 2X108R
| |
| ; Chrm Spray: Boric Chem Spray: Boric
| |
| ! acid and sodium acid, sodium tetraborate soln. phosphate, sodiuni i hydroxide and hydrazine soln.
| |
| l 6200 ppm Boron 8.6 - 10 pH l SUBMERGENCE: Yes 1
| |
| QUALIFICATION REPORT: F-C5120-2 and F-C5120-3 (CNM-1354.00-0021 and CNM-1354.00-0024)
| |
| METHOD: Test i
| |
| i
| |
| ! REPLACEMENT INTERVAL: N/A EPSS l
| |
| | |
| A T 'N k {d (d CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 31
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Brand Rex MODEL #: XLPE Insulation (1) Control (Procurement (Lower Containment) Specs: CNS-1354.02-0001
| |
| & 0002)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Tcmp: 327 F Temp: 385 F 4 months 5 months N/A N/A Press: 14.4 psig Press: 113 psig post DBE post DBE RH: 100% RH: 100%
| |
| i Rad: 1.3X108R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. phosphate, sodium
| |
| , hydroxide and i hydrazine soln.
| |
| 6200 ppm Boron 8.6 - 10 pH SUBMERGENCE: Yes i
| |
| QUALIFICATION REPORT: F-C5120-1 and FC5120-3 (CNM-1354.00-0023 and CNM-1354.00-0024) l l
| |
| METHOD: Test / Analysis l REPLACEMENT INTERVAL: N/A EPSS i
| |
| I
| |
| | |
| O O O <
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 32
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE-CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Eaton MODEL #: FR-EPDM (1) Instrumentation and Control (Procurement (Lower Containment) Specs: CNS-1354.03-00-0001, 0002 & 0003)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT .(% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327*F Temp: 327*F 4 months 4 months N/A N/A Press: 14.4 psig Press: 15 psig post DBE post DBE i RH: 100% RH: 100%
| |
| Rad: 1.2x108R Rad: 2x108R
| |
| 'Chzm Spray: Boric Chem Spray: Boric acid acid and sodium and sodium tetraborate tetraborate soln. solution 3,000 ppm 10 pH SUBMERGENCE: Yes QUALIFICATION REPORT: E17168-31 and DQAP/ CRC 0002 (CNM-1354.00-0018 and CNM-1354.00-0052)
| |
| METHOD: Test / Analysis '
| |
| REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| -s k ,)
| |
| m l
| |
| {
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 33
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 1 LOCATED INSIDE CONTAINMENT l
| |
| l
| |
| ! EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: FR-EPR (1) Control Insulation (Procurement (Lower Containment) Specs: CNS-1354.02-00-0001
| |
| & 0002) i ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i
| |
| (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) i ENVIRONMENT i
| |
| i 1 Temp: 327 F Temp: 346 F 4 months 4 months N/A N/A
| |
| ! Press: 14.4 psig Press: 113 psig post DBE post DBE i RH: 100% RH: 100%
| |
| ; Rad: 1.3X108R Rad: 2X108R q Chrm Spray: Boric Chem Spray: Boric acid and sodium acid, sodium i tetraborate soln. thiosulfate, l and sodium
| |
| ; hydroxide soln.
| |
| 3000 ppm Boron i 10.5 pH SUBMERGENCE: Yes QUALIFICATION REPORT: Okonite Report FN-1 (CNM-1354.00-0006) i i
| |
| i METHOD: Test i .
| |
| i REPLACEMENT INTERVAL: N/A EPSS 4
| |
| i -
| |
| | |
| f im CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 34
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: Tefzel (1) Hookup wire Insulation (Procurement (Lower Containment) Spec: CNS-1354.04-00-0006) l i ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED i REQUIRED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 327 F Temp: 341*F 4 months 4 months N/A N/A Press: 14.4 psig Press: 112 psig post DBE post DBE l RH: 100% RH: 100%
| |
| Rad: 1.3X108R Rad: 2X108R Chrm Spray: Boric Chem Spray: Boric acid and sodium acid, sodium
| |
| ! tetraborate soln. thiosulfate, and sodium hydroxide soln.
| |
| 3000 ppm Boron i 10.5 pH SUBMERGENCE: Yes QUALIFICATION REPORT: Okonite Report K-0-1 (CNM-1354.00-0004) 4 METHOD: Test REPLACEMENT INTERVAL: N/A EPSS l
| |
| i
| |
| | |
| ! O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 35 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O
| |
| ; LOCATED INSIDE CONTAINMENT i
| |
| EQUIPMENT ID: Cable Termination and MANUFACTURER: Raychem MODEL #: WCSF-N (1) Splice Material l (Lower Containment)
| |
| , ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT 10 WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT i
| |
| j
| |
| . Te p: 327*F Temp: 360"F 4 months 4 months N/A N/A Press: 14.4 psig Press: 70 psig post DBE post DBE
| |
| ! RH: 100% RH: 100%
| |
| Rad: 1.3X108R Rad: 2X108R Ch:m Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. thiosulfate and sodium hydroxide soln.
| |
| 3000 ppm Boron 9.5 - 11 pH l SUBMERGENCE: Yes
| |
| ; QUALIFICATION REPORT: F-C4033-3 and 71100 (CNM-1367.01-0002)
| |
| ; METHOD: Test / Analysis l
| |
| l REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O -
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 36 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPPENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Seal Material for Cable MANUFACTURER: 3M MODEL #: Scotch Cast 9 Epoxy (1) Entrance Fittings (XR-5240)
| |
| (Lower Containment)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIPED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN).
| |
| ENVIRONMENT Te:p: 327 F Later Later Later N/A N/A Press: 14.4 psig RH: 100%
| |
| Rad: Later Chem Spray: Boric acid and sodium tetraborate soln.
| |
| SUBMERGENCE: Later QUALIFICATION REPORT: Later METHOD: Later
| |
| {
| |
| REPLACEMENT INTERVAL: Later EPSS I
| |
| a
| |
| | |
| 'rV h b L/ b V
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 37 SUMARY 0F ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Seal Material for Cable MANUFACTURER: Dow Corning MODEL #: RTV-3145 (1) Fittings ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 180 F Later Later Later N/A N/A Press: 14.4 psig RH: 100%
| |
| Rad: Later Ch:m Spray: Boric acid and sodium tetraborate soln.
| |
| SUBMERGENCE: Later QUALIFICATION REPORT: Later METHOD: Test REPLACEMENT INTERVAL: Later EPSS
| |
| | |
| f^g p Cs O] Y CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 38
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT -
| |
| EQUIPMENT ID: Incore Thermocouple System MANUFACTURER: Combustion Engineers MODEL #: N/A
| |
| ; (1) Cable and Connectors ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT .
| |
| l j Temp: 327 F Later Later Later Later Later Press: 14.4 psig RH: 100%
| |
| ; Rad: 1.3X108R Chem Spray: Boric acid and sodium tetraborate soln.
| |
| SUBMERGENCE: N/A QUALIFICATION REPORT: Later METHOD: Tes
| |
| ; REPLACEMENT INTERVAL: N/A ECSE 4
| |
| | |
| Page CN-1 Rev. 1 CATAWBA NUCLEAR STATION UNITS 1 AND 2 V
| |
| ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED INSIDE CONTAINMENT Note 1 All equipment identified in this table is located inside the containment, specifically in the lower compartment except for the electric hydrogen recombiner, containment air return fan motors, hydrogen skimmer fan motors, containment air return isolation damper motors, differential pressure switches for damper control and cables associated with these devices which are located in the upper compartment.
| |
| Note 2 The parameters that compose the overall worst-case containment accident environment are as follows:
| |
| Temperature (Upper Compartment): 180 F, time history as shown in FSAR, Figure 6.2.1-6.
| |
| Temperature (Lower Compartment): 327*F peak-time history as shown in FSAR, Figure 6.2.1-16.
| |
| Pressure (Upper and Lower Compartment): 14.4 psig peak; time history as i
| |
| t fs)
| |
| J shown in FSAR, Figure 6.2.1-5.
| |
| Relative Humidity: 100%
| |
| Radiation: Total integrated radiation dose for the equipment location includes 40 year normal operating dose plus the appropriate accident dose.
| |
| Chemical Spray: Boric acid and sodium tetraborate spray resulting from i mixing in the containment sump of borated water from the refueling water l
| |
| storage tank and sodium tetraborate solution from ice bed melt. Refer to FSAR, Section 6.1.1.2 for additional information on chemical spray.
| |
| Submergence: Containment flood level is elevation 571+0.
| |
| Note 3 ,
| |
| Equipment performs its safety function prior to submergence.
| |
| I Note 4 RTD's are a sealed, water tight unit.
| |
| O (G
| |
| | |
| Page CN-2 Rev. 1 Note 5 Refer to FSAR response to question 440.48.
| |
| Note 6 The manufacturer's test report states that the detector assembly has only organic components which are not susceptible to degradation due to thermal or radiation aging.
| |
| Note 7 Overall system accuracy should be within a factor of 2 over the entire range as stated in Regulatory Guide 1.97, rev. 2*. The calibrated accuracy of the system is 120% of the system's range.
| |
| O
| |
| !O t
| |
| :l l
| |
| l l
| |
| l l
| |
| l l V l
| |
| | |
| O ATTACHMENT 2
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED IN THE ANNULUS
| |
| , Page Rev. Page Rev. Page Rev.
| |
| i 1 1 2 1 3 1
| |
| ; -4 1
| |
| , 5 1 6 1 7 1 8 1 i 9 1 10 1 11 1 12 1 i 13 1 14 1 15 1 16 1 O- 17 18 19 1
| |
| 1 1
| |
| 20 1 1 21 1 l 22 1 23 1
| |
| -24 1 25 1 26 1 27 1 AN-1 1 AN-2~ 1 i
| |
| O
| |
| | |
| 1
| |
| )
| |
| CATAWBA-NUCLEAR STATION - UNITS 1 AND 2 Page 1 SIM4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS l EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 764 i Steam Generator Levc1 (N/R) (NSSS) (Lot 2) i i
| |
| 2 ACCIDENT ENVIRONMENT OPERABILITY OPERAEILITY ACCURACY ACCURACY j ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i (1) QUALIFIED ACCIDENT ,(2) (% OF SPAN) (% OF SPAN)
| |
| : ENVIRONMENT ,
| |
| j Temp: 150 F Temp: 380 F Reactor Trip 1 year Trip Function: < + 5% (5 min) i RH: 100% RH: 100% (<5 minutes) post DBE +5% (5 min)
| |
| Rad: 4.5X107R Rad: 5X107R plus 4 months
| |
| , post DBE PAM Function: Max Error 15%
| |
| ; 125% (4 mo) (4 mo)
| |
| :)
| |
| i i
| |
| ~
| |
| QUALIFICATION REPORT: WCAP 9885 METHOD: Test l
| |
| REPLACEMENT INTERVAL: 10 Years ECSE
| |
| | |
| 4 CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 2 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 j LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 764 Steam Generator Level (W/R) i 4
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| : ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT .(2) (% OF SPAN) (% OF SPAN) i ENVIRONMENT I
| |
| Temp: 147 F Temp: 420*F 4 months 1 year 125% 110%
| |
| RH: 100% RH: 100% post DBE post DBE Rad: 1.5X107R Rad: 2.0X108R l
| |
| i 4
| |
| l QUALIFICATION REPORT: Barton R3-764-3 (CNM-1210.04-261) i METHOD: Test i
| |
| l REPLACEMENT INTERVAL: 10 Years MPIC l
| |
| I
| |
| | |
| O O O i
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 3 SUtMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| { LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter - MANUFACTURER: Veritrak MODEL #: 76DP j Main Steam Flow (NSSS) 1 i
| |
| : ACCIDENT ENVIRONMENT OFERABILITY OPERABILITY ACCURACY ACCURACY
| |
| 'I ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED. REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) i ENVIRONMENT Tha Main Steam Flow signals are not required for accidents that cause a change in the normal annulus operating environment.
| |
| j Further, failure of these transmitters as a result of exposure to a harsh environment will not preclude the safety function of other equipment claimed in the accident analysis. Additionally, the information provided by these transmitters is not i employed as a post accident monitoring parameter for operator action.
| |
| 1 i
| |
| i l
| |
| 1 QUALIFICATION REPORT: N/A METHOD: N/A l REPLACEMENT INTERVAL: N/A ECSE
| |
| | |
| 1 O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 4
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 386A
| |
| ,) Containment Pressure (NR) i ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIREG IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| . ENVIRONMENT
| |
| ]
| |
| Th2se transmitters will be relocated in the Penetration Room.
| |
| i i
| |
| QUALIFICATION REPORT: N/A
| |
| } MET!iOD: N/A l
| |
| t REPLACEMENT INTERVAL: N/A MPIC y
| |
| l
| |
| | |
| :L CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 5
| |
| ! SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 386A Containment Sump Level
| |
| ! ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| ; (1) QUALIFIED ACCIDENT (2) (% OF SPAN) '(% OF SPAN)
| |
| : ENVIRONMENT l
| |
| i Temp: 150 F Temp: 160 F 4 months 1 year 15% loop 112.06% inst.
| |
| ! RH: 100% RH: 100% post DBE post DBE j Rad: 4.5X107R Rad: 2.0X10sR j
| |
| l 1
| |
| i l
| |
| 2 QUALIFICATION REPORT: Wyle Report 43904-1 Vol. I-Rev.C, Vol. II-Rev.B (CNM-1210.04-252) 4 METHOD: Test REPLACEMENT INTERVAL: 10 Years MPIC 4
| |
| | |
| O O O f CATAWBA NUCLEAR STATION - UNITS 1 AND 2 .Page 6 l
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter - MANUFACTURER: Rosemount MODEL #: 1153086 i
| |
| Containment Pressure (WR)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i (1) QUALIFIED ACCIDEN1 (2) (% OF SPAN) (% OF SPAN)
| |
| . ENVIRONMENT These transmitters have been relocated in the Penetration Room.
| |
| i 1
| |
| i
| |
| ! QUALIFICATION REPORT: N/A i
| |
| l MEiH00: N/A i
| |
| i REPLACEMENT INTERVAL: N/A MPIC 1
| |
| i
| |
| | |
| ,- m m i
| |
| i CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 7 3
| |
| SUP94ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| . LOCATED IN THE ANNULUS i
| |
| EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 763 RCS Pressure (W/R) (NSSS) (Lot 2)
| |
| , ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| ! (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) t ENVIRONMENT i
| |
| Temp: 150*F Temp: 380 F 2 weeks 2 weeks 110% Max Error 6.1%
| |
| RH: 100% RH: 100% post DBE post DBE Rad: 1.7X105R Rad: SX107R i
| |
| l i
| |
| QUALIFICATION REPORT: WCAP 9885 i
| |
| METHOD: Test l
| |
| REPLACEMENT INTERVAL: 10 Years ECSE 1
| |
| | |
| O O O J;
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 8 SU M ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS
| |
| ' EQUIPMENT'ID: Limit Switches MANUFACTURER: NAMC0 MODEL #: EA-180 ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY 9 ACCU.ACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| .(1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) i ENVIRONMENT L fTemp: '150 F ,
| |
| Temp: 340*F 5 minutes 1 year N/A N/A RH: 100% . RH:,, 100% post DBE post DBE Rad: 1X104R ' Rad: , 2X108R (Note 3)
| |
| 's QUALIFICATION REPORT: NAMC0 Test Report dated September 5, 1978 and QTR-105 METHOD: Test REPLACEMENT INTERVAL: 4 Years MEQP
| |
| | |
| t > , < I L
| |
| )
| |
| DN O 91 e
| |
| gv ae PR YTP CAS AR RTF USO EA
| |
| /
| |
| A N
| |
| P Q
| |
| E M
| |
| CN CO%
| |
| AM(
| |
| E D
| |
| 1
| |
| - 5 A
| |
| N 7
| |
| 9 1
| |
| : ) - e
| |
| # N n YDA u L CEP J E ARS _
| |
| T D RI A , _
| |
| N O UUF / 2 _
| |
| E M CQO N 2 M CE 2 P AR% (
| |
| I R U T Q
| |
| E d n
| |
| E a 1
| |
| S 3 2S 7 A D 9 DL YE 1 NC TT A S IA r
| |
| _ FU LR E e
| |
| _ 1OL IT) rB b U BS2 aD o SNN k AN( e t TON r RO yt c IIA o EM s O NT t PE 1o UAE o OD p ,
| |
| CH R 6
| |
| - IT 1 F 1 O
| |
| NIN :
| |
| OLI R R IA E T TUD R AQE U ;
| |
| T T T 0 SLA C 7 AC A YN T 9 RTO F TI N 1 ANL U I TE s EE N LDNM eE) r LM A IEEN tB3 e CN M BRDO uD b UO AIIR n e m NR RUCI itt e)
| |
| _ AV I EQCV PEAN msooN c8 e
| |
| _ BN OR E 5 p( D&
| |
| WE A ,,
| |
| TF 47 AO /
| |
| _ C 1 ,
| |
| _ Y 16
| |
| - R 0
| |
| . A t
| |
| N0
| |
| # 0
| |
| _ P s t -
| |
| U r T r9
| |
| _ S o N D R o1 t EHE F 8 p .
| |
| - a MCI %0 e5 r NIF 001 R0 e OHI 40X 2
| |
| _ p RWL 312 k1
| |
| _ O I A r-VOU oM
| |
| _ r NTQ tN A
| |
| _ o E : oC /
| |
| - t p : R( N
| |
| _ o m:d M eHa TRR : :
| |
| e T L v R A l O V a P R V E E T R T
| |
| _ TN R N NE N O
| |
| : F 4 t I D EM * %0 O s I DN) 001 I e T
| |
| ?O1 50X T T N T CR( 111 A E N CI C M E AV I : E M N F D C P E : I O A I p : L H L
| |
| _ U m:d A T P Q eHa U E E E TRR Q M R i ,.i
| |
| | |
| 1
| |
| ; CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 10 i
| |
| SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| ; LOCATED IN THE ANNULUS i
| |
| EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SM RH Insulation -
| |
| }
| |
| . ACCIDENT ENVIRONMENT OPERABILITY OPERA 8ILITY ACCURACY ACCURACY 4 ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED . REQUIRED DEMONSTRATED
| |
| ; (1) QUALIFIED ACCIDENT '
| |
| (2) (% OF SPAN) (% OF SPAN) a ENVIRONMENT -
| |
| 4 L
| |
| , Temp: 150*F Temp: 340 F 5 minutes 1 year N/A N/A R$f: 100% RH: 100% post D8E post DEE l Rad: 1X104R Rad: 2X10sR (Note 3) i l
| |
| QUALIFICATION REPORT: Limitorque Report 600-376-A, September 1972; 600-456, December 1975 (CNM-1205.19-0001) I l
| |
| i METHOD: Test i
| |
| 1 l REPLACEMENT INTERVAL: N/A MEQP i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 11
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS t
| |
| EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: ASCO MODEL #: NP831655E l
| |
| ! ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| ; ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ; ENVIRONMENT 1
| |
| Temp: 150 F Temp: 346 F 5 minutes 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X104R Rad: 1.5X10sR (Note 3) l l
| |
| I l
| |
| l QUALIFICATION REPORT: ASCO Report AQS21678/TR Rev. A, July 1979, (CNM-1205.02-0499) l NETH00: Test l REPLACEMENT INTERVAL: N/A MEQP l
| |
| \
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 12 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNOLUS EQUIPMENT ID: Cable - MANUFACTURER: Anaconoa H0 DEL #: FR-EPR Hookup Wire Insulation (Procurem nt Spec.
| |
| CNS-1354.04-CO-0006)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150 F Temp: 194 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X108R (Note 4) i l
| |
| l QUALIFICATION REPORT: F-C4836-4 and 80282 (CNM-1354.00-0017 and CNM-1354.00-0025)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 13
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: EPR Medium Voltage and Power Insulation (Procurement Specs: CNS-1354.01-00-0001
| |
| & 0003)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150*F Temp: 194 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X108R (Note 4)
| |
| QUALIFICATION REPORT: F-C4350-3 (CNM-1354.00-0003)
| |
| METHOD: Test t
| |
| REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 14
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS
| |
| *%r EQUIPMENT ID: Cable - Category C 'aiai,0 MANUFACTURER: Anaconda MODEL #: FR-EPR Control Insulation (Procurement Specs: CNS-1354.02-00-0001
| |
| & 0002) '
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQ'JIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150*F Temp: 194 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post.08E Rad: 1X108R Rad: 2X108R (Note 4)
| |
| QUALIFICATION REPORT: F-C4969-1 and 80282 (CNM-1354.00-0009 and chm-1354.00-0025)
| |
| I METHOD: Test i
| |
| i REPLACEMENT INTERVAL: N/A EPSS i
| |
| l l
| |
| l' l _ _-.
| |
| | |
| O O O 4
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 15
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 i LOCATED IN THE ANNULUS i
| |
| l EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Instrumentation anc Control Insulation (Procurement
| |
| ; Specs: CNS-1354.03-00-0001, l 0002 & 0003) ,
| |
| i
| |
| {
| |
| ! ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| ' ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCID'c hi (2) (% OF SPAN) (% OF SPAN)
| |
| ; ENVIRONMENT i
| |
| i
| |
| ! Temp: 150*F Temp: 194 F 4 months 1 year N/A N/A
| |
| ; RH: 100% RH: 100% post DBE post D6E Rad: 1X10sR Rad: 2X108R (Note 4)
| |
| I 1
| |
| i i
| |
| j QUALIFICATION REPORT: F-C4836-2 and 80282 (CNM-1354.00-0020 and CNM-1354.00-0025) i j METHCo. Test
| |
| [j REPLACEMENT INTERVAL: N/A EPSS
| |
| )
| |
| i
| |
| | |
| O O O i
| |
| i CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 16
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS 1
| |
| EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Low Voltage Power Insulation (Procurement Spec: CNS-1354.01-00-0003)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT
| |
| , Temp: 150*F Temp: 194 F 4 months 1 year N/A N/A l RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X108R (Note 4) t l
| |
| 6 QUALIFICATION REPORT: F-C4350-2 (CNM-1354.00-0002)
| |
| METHOD: Test -
| |
| REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O 4
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 17 i
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTA8. QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL #: XLPE Control Insulation (Procurerant Specs: CNS-1354.00 l-0001
| |
| & 0002)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED 1 (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) l ENVIRONMENT i
| |
| 4 l Temp: 150*F Temp: 194*F 4 months 1 year N/A N/A
| |
| : RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X10sR (Note 4) i i
| |
| QUALIFICATION REPORT: F-C5120-1 and F-C5120-3 (CNM-1354.00-0023 and CNM-1354.00-0024)
| |
| METHOD: Test l REPLACEMENT INTERVAL: N/A EPSS i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 18
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL #: XLPE Coaxial Insulation (Procurement Spec: CNS-1354.04-00-0004)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) 4 ENVIRONMENT I
| |
| l Temp: 150 F Temp: 194 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X108R (Note 4) l
| |
| ! QUALIFICATION REPORT: F-C5120-2 and F-C5120-3 (CNM-1354.00-0021 and CNM-1354.00-0024)
| |
| )!
| |
| I METHOD: Test 4
| |
| REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| /
| |
| b,' k
| |
| (.
| |
| U CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 19
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - MANUFACTURER: Eaton MODEL #: FR-EPDM Instrumentation and Control Insulation (Procurement Specs:
| |
| CNS-1354.03-00-0001, 0002 &
| |
| 0003)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150 F Temp: 327 4 months 4 months N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X10sR Rad: 2.0X108R QUALIFICATION REPORT: E17168-31, DQAP/ CRC 0002 (CNM-1354.00-0018 & CNH-1354.00-0052)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 20 SUfetARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: EPR Medium Voltage Insulation (Procurement Specs:
| |
| CNS-1354.01-00-0001 & 0003) 1 i
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACC'URACY ENVIRONMENT TO WHICH REQUIRED IN DEMON 5!9ATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) i ENVIRONMENT I
| |
| Temp: 150 F Temp: 194 F 4 months 1 year N/A N/A i RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X10sR
| |
| , (Note 4) i i
| |
| QUALIFICATION REPORT: Okonite Report G-3 (CNM-1354.00-0007) i METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 21 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS lE EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS 4
| |
| EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: FR-EPR Control .
| |
| Insulation (Procurement Spec: CNS-1354.02-00-0001
| |
| & 0002)
| |
| J ACCIDENT ENVIRONMENT . OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Terp: 150 F Temp: 194*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X10sR j (Note 4)
| |
| I QUALIFICATION REPORT: Okonite Report FN-1 (CNM-1354.00-0006) 1 METHOD: Test l
| |
| l REPLACEMENT INTERVAL: N/A EPSS l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 22
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: Tefzel Hookup wire Insulation (Procurement Spec: 1354.04-00-0006)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| , ENVIRONMENT 10 WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150 F Temp: 194 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X108R Rad: 2X10sR (Note 4) l I
| |
| QUALIFICATION REPORT: Okonite Report K-0-1 (CNM-1354.00-0004) l METHOD: Test l
| |
| l l
| |
| l REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 23
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable Termination MANUFACTURER: Ray Chem MODEL #: WCSF-N Splice Material ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150 F Temp: 194*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X10sR Rad: 2X108R (Note 4) t QUALIFICATION REPORT: Test Reports F-C4033-3 and 71100 (CNM-1367.01-0002)
| |
| METHOD: Test i
| |
| REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| f% fh NN LY ./
| |
| )
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 24
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 4
| |
| LOCATED IN THE ANNULUS EQUIPMENT ID: Seal Material for Cable MANUFACTURER: 3M MODEL #: Scotch Cast 9 Epoxy
| |
| , Entrance Fittings (XR-5240)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 150 F Later 4 months Later N/A N/A RH: 100% post DBE Rad: 1X108R i
| |
| t QUALIFICATION REPORT: Later METHOD: Later i
| |
| REPLACEMENT INTERVAL: Later EPSS 4
| |
| l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 25
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: 1TB0X0001 MANUFACTURER: Duke MODEL #: N/A (Note 5)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) r ENVIRONMENT Temp: 147 F Temp: 212*F Continuous Continuous N/A N/A RH: 100% RH: 100%
| |
| Rad: 1.3X107R Rad: 3.0X107R QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O i
| |
| , CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 26 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS
| |
| ! EQUIPMENT ID: '1TBOX0002 MANUFACTURER: Duke MODEL #: N/A
| |
| ; (Note 5)
| |
| ACCIDENT EINIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT
| |
| . Temp: 147*F Temp: 212*F Continuous Continuous N/A N/A J
| |
| RH: 100% RH: 100%
| |
| I Rad: 1.3X107R Rad: 3.0X107 1
| |
| 1 QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis i
| |
| REPl.ACEMENT INTERVAL: N/A
| |
| | |
| O O O 4
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 27 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| , LOCATED IN THE ANNULUS EQUIPMENT ID: 1TB0X0327 MANUFACTURER: Duke MODEL #: N/A j (Note 5)
| |
| ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| ! ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED l (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT Temp: 147*F Temp: 330*F Continuous Continuous N/A N/A i RH: 100% RH: 100%
| |
| Rad: N/A 1
| |
| l i
| |
| l QUALIFICATION REPORT: CNC-1381.05-00-0054 l
| |
| l METHOD: Test / Analysis ;
| |
| j REPLACEMENT INTERVAL: N/A
| |
| | |
| Page AN-1 Rev. 1 CATAWBA NUCLAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED IN THE ANNULUS Note 1 The environmental conditions in the annulus (primarily temperature and radiation) are dictated by the containment environment because of the physical arrangement of the annulus with respect to the containment.
| |
| Therefore, the worst case annulus temperture and radiation environment is based on the worst case containment accident environment. Additionally, there are no pipe ruptures postulated in the annulus that cause a pressure excursion nor u there chemical spray in the annulus.
| |
| ' The parameters that compose the overall worst case annulus environment are as follows:
| |
| Temperature: 150*F Relative Humidity: 100% ,
| |
| Radiation: Total integrated radiation dose for the equipment location includes the 40 year normal operating dose plus the appropriate accident
| |
| ; dose based on the equipment operability requirements. -
| |
| s Submergence: Annulus Flood Level is 554'& 0". No safety-related equipment
| |
| ,) is located below this level.
| |
| Note 2 The operability time demonstrated is the period required for the equipment to reach its qualified radiation dose in the accident environment.
| |
| Temperature transients in the annulus, due to a MSLB or LOCA inside containment, are minimal and well within the design capabilities of the equipment. Therefore, temperature is not a factor in operability time.
| |
| Note'3 Five minutes is adeguate time to assure containment isolation and the required repositioning of other safety-related valves.
| |
| Note 4 The qualified temperature is based on the insulation rating of the cable.
| |
| The temperature of the insulation is a function of the cable conductor temperature and ambient temperature.
| |
| O
| |
| | |
| Pagt AN-2 Rsv. 1 Note 5 O The equipment listed is a NEMA 4 enclosure containing general application devices (e.g., relays, switches, terminal blocks, etc.). The qualified environment is dictated by the single limiting device contained in the enclosure. The enclosure and device qualification is documented in calculation CNC-1381.05-0054.
| |
| i O .
| |
| 4-O
| |
| | |
| O ATTACHMENT 3 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT 1
| |
| Pg Rev. M Rev. M Rev.
| |
| 1 1 35 1 78 0 2 1 36 1 79 0 3 1 37 1 PRN-1 0 ,
| |
| 4 1 38 1 5 1 39 1 6 1 40 1 7 1 41 1 8 1 42 1 9 1 43 1 10 1 44 1 11 1 45 1 12 1 46 1 13 1 47 1
| |
| , 14 1 48 1 15 1 49 1 16 1 50 1
| |
| ^ 17 1 51 1 i
| |
| 18 1 52 1 -
| |
| 19 1 53 1 20 1 54 1 21 1 55 1 22 1 56 1 23 1 57 1 24 1 58 1
| |
| : 25 1 59 1 26 1 60 1 27 1 61 1 l 28 1 62 1 1
| |
| 29 1 63 1 30 1 64 0 31 1 65 0 1 32 1 66 0 ,
| |
| l 33 1 67 0 34 1 68 0 69- 0 70 0 71 0 72 0 73 0 l 74 0 L
| |
| 75 0 76 0 L 77 0
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 1
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Transmitter - MANUFACf0RER: Veritrak MODEL #: 76DP Main Feedwater Flow (NSSS)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| The Main Feedwater Flow signals are not required for pipe ruptures that cause a change in the normal Auxiliary Building (Doghouse) operating environment.
| |
| QUALIFICATION REPORT: N/A METHOD: N/A REPLACEMENT INTERVAL: N/A ECSE
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 2
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Transmitter - MANUFACTURER: ~Veritrak MODEL #: 76DP Steam Line Pressure (NSSS) ,
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| These transmitters will be relocated in an area of mild environment.
| |
| QUALIFICATION REPORT: N/A METil00: N/A REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 3
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Barton M00.EL #: 386A NW Surge Chamber Level A and B PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 157 F 172 F Continuous Continuous 131.7% 112.3%
| |
| QUALIFICATION REPORT: y Report #43904-1 Vol. I-Rev. C, Vol. II-Rev.B (CNM-1210.04-252)
| |
| W'le i
| |
| METHOD: Test -
| |
| l l
| |
| REPLACEMENT INTERVAL: 10 Years MPIC
| |
| | |
| a Cl h) m CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 4 SupMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONHENT i
| |
| EQUIPMENT.ID: Transmitter - Component Cooling MANUFACTURER: Rosemount MODEL #: 1153D84 Heat Exchanger Inlet Flow 4
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Te:p: 212 F Temp: 318*F Continuous Continuous N/A N/A QUALIFICATION REPORT: Rosemount Reports 108025 and 108026 I
| |
| I METHOD: Test / Analysis REPLACEMENT INTERVAL: 10 Years MPIC I
| |
| i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 5 SU M ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Transmitter- MANUFACTURER: Rosemount MODEL #: 1153084 Boric Acid Tank Level PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY -
| |
| ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 160 F Temp:318 F Continuous Continuous later 112.3%
| |
| QUALIFICATION REPORT: Rosemount Report 108025 and 108026 METHOD: Test REPLACEMENT INTERVAL: lu Years MPIC i
| |
| | |
| (* \
| |
| G) (''J w G(O e
| |
| . ?l J CATAWBA NUCLEAR STATION - UNITS l'AND~2 Page 6 ? ''
| |
| SUMARY OF ENVIRONMEllTAL QUALIFICATION OF~ CLASS 1E EQUIPMENT Rev. 1 '
| |
| , y LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT 3 p,.#
| |
| EQUIPMENT ID: Transmitter- '
| |
| -MANUFACTURER: ''
| |
| Barton MODELE#: 764g'I I-Aux. FW Flow
| |
| . 7 1
| |
| ! PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ': ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) .(% OF SPAN)
| |
| ; ENVIRONMENT (2) ,
| |
| Te:p: 330 F Temp:420 F Later 1 yr. Later 110%
| |
| Press: 8.85 PSIG Press: 75 PSIG Post DBE t
| |
| 2 i
| |
| i
| |
| ! i QUALIFICATI01- REPORT: Barton R3-764-9 (chm-1210.04-0261)
| |
| )
| |
| l METHOD: Test
| |
| ! REPLACEMENT INTERVAL: 10 Years MPIC d
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 7 i
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: D/P Switch MANUFACTURER: Barton MODEL #: 580A-0 RHR Pump Minimum Flow PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| , ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 248 F Temp: 340*F Later 1 year Later Later j Post DSE i
| |
| l i
| |
| t i
| |
| i i QUALIFICATION REPORT: Barton Report #548-8890 Rev. A l
| |
| METHOD: Test i
| |
| REPLACEMENT INTERVAL: Later MPIC i
| |
| | |
| , O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 8
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: D/P Switch MANUFACTURER: Barton MODEL #: 5'61A-0 KC HX A&B Inlet Flow
| |
| ! PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED
| |
| ' REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) e l Temp: 212 F Temp: 340*F Continuous Continuous 15.0% 15.0%
| |
| l
| |
| -l
| |
| ] QUALIFICATION REPORT: Barton Report #548-8890 Rev. A '
| |
| METHOD: Test l
| |
| REPLACEMENT INTERVAL: Later MPIC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 9 SUPNARY OF ENVIRONMENTAL. QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| . LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| ! EQUIPMENT ID: D/P Switch MANUFACTURER: Barton MODEL #: 580A-l'
| |
| ; CA pumps - Loss of Suction l
| |
| l PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| ; Te:p: Ambient Temp: 340 F Continuous Continuous Later Later 4
| |
| h Submergence: Yes (Later) 1 l 1 QUALIFICATION REPORT: Barton Report #546-8890 Rev. A j HETH00: Test i
| |
| REPLACEMENT INTERVAL: Later MPIC I
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 10 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OGTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: D/P Switch- MANUFACTURER: Barton MODEL #: 580A-1 KC Surge Tank Level 1
| |
| , PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) 4 Terp: 127 F Temp: 340 F Continuous Continuous 15.0% 13.1%
| |
| i l
| |
| f i
| |
| QUALIFICATION REPORT: Barton Report #548-8890 Rev. A e
| |
| METHOD: Test l
| |
| REPLACEMENT INTERVAL: Later MPIC l
| |
| | |
| - _ - _ = .. _ _ _ _ _ - . _ . _ _ - _ _ .
| |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 11
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIFMENT ID: Pressure Switch- MANUFACTURER: SOR Inc. MODEL #: 12NG-84-NX-CIA NW Surge Chamber Pressure PIPE RilPTURE ENVIRONMENT OPERABILITY OPERABIL'ITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PI?E RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212 F Temp: 250 F Continuous Continuous , 16.5% 12.0%
| |
| QUALIFICATION REPORT: Later METHOD: Later REPLACEMENT INTERVAL: Later MPIC
| |
| | |
| ( = -.
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 12 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINiiENT AND EXPOSED TO PIPE RUPTURE ENVIRCNMENT EQUIPMENT ID: Transmitter - ESF Filters ' MANUFACTURER: Cornwell Inst. MODEL #: 100 Downstream HEPA Differential Pressure PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) . QUALIFIED PIPE RUPTURE
| |
| (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 182 F Later Later later Later Later QUALIFICATION REPORT: Later
| |
| ) METHOD: Later i
| |
| REPLACEMENT INTERVAL: Later Note Transmitter is being changed out to a Foxboro.
| |
| l Sheet will be updated next revision. Testing in progress. MHVC 1
| |
| | |
| O O- O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 13 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT a
| |
| EQUIPMENT ID: Level Switches- MANUFACTURER: Magnetrol MODEL #: A-103F-3X-Y-MPG ND & NS Room Sump Level 4
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED
| |
| ' REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE ,
| |
| (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212 F Temp: 285 F Later Continuous Later 11/2 inch i
| |
| I.
| |
| i l QUALIFICATION REPORT: Duke Power Co. Reports TR-053 & TR-060 METHOD: Test REPLACEMENT INTERVAL: 15 Years MPIC i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 14
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED IO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Level Switches-Doghouse Level MANUFACTURER: Magnetrol MODEL #: A-103F-3X-Y-MPG PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED .
| |
| REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Te p: 240 F 285 F Approximately 15 secs. Continuous i 1/4 inch i 1/4 inch prior to accomplishment of trip function, i.e.,
| |
| trip main fdw pumps QUALIFICATION REPORT: Duke Power Company Reports TR-053 and TR-060 METHOD: Test REPLACEMENT INTERVAL: 15 Years MPIC
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 15
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Differential Pressure MANUFACTURER: Solon MODEL #: 7PS11DW Switch I
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILI-TY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) j Not required to mitigate the consequences of an HELB.
| |
| QUAI.IFICATION REPORT: N/A METHOD: N/A REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| 1
| |
| ) CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 16 StMtARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| : EQUIPMENT ID: Pressure Switch MANUFACTURER: Dwyer MODEL #: 3000-0 1
| |
| l PIPE RUPTURE ENVIRONMENT -OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| ; ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED-i (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) l ENVIRONMENT (2) 4 Pressure Switch has been deleted by DCA-CN-1M1398 1 and 2M1398 i
| |
| i i
| |
| QUALIFICATION REPORT:
| |
| I I
| |
| ) METHOD:
| |
| i j REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 17
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Stem Mounted Limit Switch MANUFACTURER: NAMCO MODEL #: EA-180 i
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 212 F Temp: 340 F Continuous Continuous N/A N/A I
| |
| i I
| |
| QUALIFICATION REPORT: NAMCO report dated September 5, 1978 and QTR-105 1
| |
| ! METHOD: Test I
| |
| REPLACEMENT INTERVAL: 4 Years MEQP J
| |
| I
| |
| | |
| Q u V(''\ fJ CATAW8A NUCLEAR STATION - UNITS 1 AND 2 Page 18
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Stem Mounted Limit Switches MANUFACTURER: NAMC M00LL #: EA-170-302 4
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) i j Temp: 212*F Temp: 212 F Continuous Continuous N/A N/A i
| |
| i s
| |
| QUALIFICATION REPORT: NAMC0 report dated July 24, 1978, report QTR-107 and NAMCO letter dated 4/9/81 i
| |
| HETHOD: Test REPLACEMENT INTERVAL: 4 Years l MEQP/MHVC I
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 19 SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: . Stem Mounted Limit Switches MANUFACTURER: NAMC0 MODEL #: EA-740 i
| |
| . PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| : i. ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED j (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) i l <
| |
| l Te:p: 212 F Temp: 340*F Continuous Continuous N/A. N/A i
| |
| l QUALIFICATION REPORT: NAMCO report dated February 22, 1979 i
| |
| I i METHOD: Test i
| |
| i REPLACEMENT INTERVAL: 4 years MEQP 4
| |
| | |
| Q O\
| |
| V s O' CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 20 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Fuel Handling Area Exhaust MANUFACTURER: Reliance MODEL #: 1YF882585, 2YF882585, Fan Motors 1YF882745 PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENiIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 147 F Temp: 161 F Continuous Continuous N/A N/A 9
| |
| QUALIFICATION REPORT: Thermal Life Calculation (CNC-1381.05-00-0056)
| |
| METHOD: Test and Analysis REPLACEMENT INTERVAL: N/A EPSR
| |
| | |
| O O O i
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 21-SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 i LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT j EQUIPMENT ID: Auxiliary Building Filtered MANUFACTURER: Reliance ,
| |
| MODEL #: 1XF-882610, 2XF-882610 Exhaust Fan Motors 1XF-882771 f
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE
| |
| , (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 127 F Temp: 141 F Continuous Continuous N/A N/A I
| |
| I i
| |
| i i
| |
| QUALIFICATION REPORT: Thermal Life Calculation (CNC-1381.05-00-0056) i l METHOD: Test / Analysis f REPLACEMENT INTERVAL: N/A EPSR l
| |
| l l
| |
| | |
| 4 CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 22
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| ; EQUIPMENT ID: Residual Heat Removal MANUFACTURER: Westinghouse, Buffalo MODEL #: VSHX-TEWC i
| |
| Pump Motors (NSSS)
| |
| . PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| ! ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED l (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) 4 ENVIRONMENT (2) .
| |
| i
| |
| , Tcmp: 212 F Temp: 221*F 150 Minutes Continuous N/A N/A l
| |
| i 4
| |
| ! QUALIFICATION REPORT: WCAP 8754 METHOD: Test / Analysis I
| |
| REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 23
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF-CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND' EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Centrifugal Charging Pump MANUFACTURER: Westinghouse, Buffalo MODEL #: LLD-TEWC Motors -
| |
| (NSSS)
| |
| PIPE RUPTURE ENVIRONMENI OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED
| |
| : (1) QUALIFIED PIPE RUPTURE , (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 212 F Temp: 221 F Continuous Continuous N/A N/A
| |
| -l 2
| |
| 1 J
| |
| , QUALIFICATION REPORT: WCAP 8754, Rev. 1 METHOD: Test / Analysis i
| |
| REPLACEMENT INTERVAL: N/A MEQP i
| |
| | |
| O O O 1
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 24 i SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT i EQUIPMENT ID: Safety Injection Pump MANUFACTURER: Westinghouse, Buffalo MODEL #: LAC-TEWC i Motors (NSSS)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| . ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED j (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) 4 Terp: 212 F Temp: 221*F 150 Minutes Continuous N/A N/A 1
| |
| i l
| |
| i l QUALIFICATION REPORT: WCAP 8754, Rev. 1 i
| |
| l METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A MEQP l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 25
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Component Cooling Pump MANUFACTURER: Westinghouse, Buffalo MODEL #: 74F18651 S/N 1,2,3,&4 Motors 74F19752 S/N 1,2,3,&4 PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Tezp: 212*F Temp: 212 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNH-1318.00-0004; CNC-1381.05-00-042; CNC-1381.05-00-04?
| |
| , METHOD: Test / Analysis l
| |
| REPLACEMENT INTERVAL: N/A EPSR I
| |
| | |
| ; O O O
| |
| [ CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 26
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Fuel Pool Cooling Pump HANUFACTURER: Westinghouse, Buffalo MODEL #: 73F69065 S/N 1&2
| |
| , Motors 73F69066 S/N 1&2 s
| |
| l PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% CF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Te:p: 163 F Temp: 212 F Continuous Continuous N/A N/A l
| |
| i l
| |
| l QUALIFICATION REPORT: CNM-1318.00-0004; CNC-1381.05-00-042; CNC-1381.05-00-049 1
| |
| I ~
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSR l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 27
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMEP.T Rev. 1 l LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Containment Spray Pump MANUFACTURER: Westinghouse, Buffalo MODEL #: 74F18671 S/N 1&2 Motors 74F18672 S/N 1&2
| |
| , PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY i ENVIRONMENT -TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) i Temp: 212 F Temp: 212 F Later Continuous N/A N/A I
| |
| ]
| |
| 4 i
| |
| 'r
| |
| ! QUALIFICATION REPORT: CNM-1318.00-0004; CNC-1381.05-00-042; CNC-1381.05-00-049 j METHOD: Test / Analysis 1
| |
| j REPLACEMENT INTERVAL: N/A EPSR l
| |
| i I
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 28 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Boron Injection Recirculation MANUFACTURER: Westinghouse /Chempump MOUEL #: GB 1/2 K-751H-1S Pump Motors (NSSS)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED-REQUIRED (1) QUALIFIED PIPE RUPTURE' .(% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| These pus.ps have been deleted.
| |
| QUALIFICATION REPORT: N/A METHOD: N/A REPLACEMENT INTERVAL: N/A MEQP C)
| |
| | |
| Q O qV O V
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 29 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Boric Acid Transfer Pump MANUFACTURER: Westinghouse /Chempump MODEL #: GVH-10K-12H-15 Motors (NSSS)
| |
| PIPF RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) l Temp: 212 F Temp: 212 F 150 Minutes Continuous N/A N/A i
| |
| QUALIFICATION REPORT: Based on standard rating of Class H insulation NOTE: Pump is a " canned pump." Hotor is enclosed in a scaled casing and is cooled by the pumpage; therefore, the motor is not exposed to external temperature environment.
| |
| i j METHOD: Analysis i
| |
| REPLACEMENT INTERVAL: N/A MEQP l
| |
| l
| |
| | |
| _ _ _ _ - __-___ _ __ - ___ - ____ _ . - - _ - _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ =
| |
| 0 O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 30 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Containment Spray & Residual MANUFACTURER: Reliance MODEL #: 1YF882456, 1YF882767 Heat Removal Pump Room Sump Pump Motors '
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 212*F Temp: 226*F Continuous Continuous N/A N/A QUALIFICATION REPORT: Thermal Life Calculation (CNC-1381.05-00-0056)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSR
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 31
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Annulus Ventilation Fan MANUFACTURER: Reliance MODEL #: 2YF-882519 PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONS 1 RATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONME."T(2)
| |
| Not required to mitigate the consequences of an HELB 1
| |
| i QUALIFICATION REPORT: N/A METHOD: N/A i
| |
| REPLACEMENT INTERVAL: N/A MHVC i
| |
| i e
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 32 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Main _ Steam Isolation MANUFACTURER: Atwood and Morrill MODEL #: MSI Valve Actuator Valve Assembly PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY p ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE -
| |
| (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) .
| |
| I Te:p: 330 F Temp: 340 F Continuous Continuous N/A N/A i
| |
| i l
| |
| 1
| |
| )
| |
| ; QUALIFICATION REPORT: Procedure 201-39500, Test Report STR-060578-1 (CNM-1205.12-0009) l METHOD: Test REPLACEMENT INTERVAL: N/A MEQP l
| |
| | |
| l O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 33
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| . LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Feedwater Isolation MANUFACTURER: Borg-Warner (NVD) MODEL #: Pneumatic-Hydraulic Valve Operator P/N 38991 I-PIPE RUPTURE ENVIRONMENT 0PERABILITY OPERABILITY ' ACCURACY ACCURACY
| |
| ] ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED j (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) 4 ENVIRONMENT (2) 1 Terp: 330 F Temp: 340*F Continuous Continuous N/A N/A i
| |
| l l
| |
| 4 l
| |
| I, 3
| |
| QUALIFICATION REPORT: 1736 (CNM-1205.12-0014 METHOD: Test i RFPLACEMENT INTERVAL: N/A MEQP i
| |
| i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 34 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRO MENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SMB RH Insulation 1 ,
| |
| i PIPE RUPTURE . ENVIRONMENT OPERABILITY OPERABILITY ACCURAr:Y ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSIRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) 7 j Temp: 330 F Temp: 340*F Continuous Continuous N/A N/A e
| |
| I i
| |
| l i
| |
| i i
| |
| ! QUALIFICATION REPORT: 600-376-A, September 1972; 600-456, December 1975 (CNM-1295,19-0001)
| |
| I i METHOD: Test i
| |
| REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 35 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SMB B Insulation PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212*F Temp: 250 F Continuous Continuous N/A N/A QUALIFICATION REPORT: 80003, May 1976 (CNM-1205.19-0001 METil00: Test REPLACEMENT INTERVAL: N/A MEQP i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 36 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-1 PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Tcap: 330 F Temp: 340*F Continuous Continuous N/A N/A t
| |
| QUALIFICATION REPORT: N 11/4, December 1970; TR116, October 1973; TR222, June 1975 (CNM-1205.19)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 37 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-2 with NA-1 Switch Mechanism PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212 F Temp: 212*F 170 Minutes 200 Hours N/A N/A QUALIFICATION REPORT: TR3025, April 1980; TR222, June 1975; N11/4 December 1970; TR116, October 1973 (CNM-1205.19-0006,7,8&9)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O 4
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 38 SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l LOCATED OilISIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT j EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V526 PIPE RUPTURE ENVIRONMENT OPERAGILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212*F Temp: 346*F Continuous Continuous N/A N/A I
| |
| i i
| |
| QUALIFICATION REPORT: QR52600-6042-1 (CNM-1205.08-0047)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MEQP
| |
| :l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 39 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT' EQUIPMENT ID: 3 Way Valve Solenoid Operators MANUFACTURER: ASCO MODEL #: NP8320A172E/V PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) .?UALIFIED PAPE RUPTURE (% OF SPAN) (% OF SPAN),
| |
| ENVIRONMENT (2)
| |
| Not required to mitigate the consequences of an HELB.
| |
| QUALIFICATION REPORT: N/A i
| |
| l METHOD: N/A i
| |
| REPLACEMENT INTERVAL: N/A MHVC l
| |
| L
| |
| | |
| O O- O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 40 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. l' LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V70900-21-3 PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTunE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 330*F Temp. 346*F Continuous Continuous N/A N/A i
| |
| l QUALIFICATION REPORT: QR-70900-21-1 Rev. A; QR-52600-515 Rev. 8, MR-70905-21-3-1 (CNM-1210.04-253 254 & MCM-1210.04-119) l l METHOD: Test / Analysis i
| |
| REPLACEMENT INTERVAL: 5 Years MPIC e
| |
| l
| |
| | |
| , O O O I
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 41 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIROMENT EQUIPMENT ID: Electro-Hydraulic Operators MANUFACTURER: ITT General Controls MODEL #: NH-90EH Series (HVAC) l 1
| |
| l PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY
| |
| : ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| ! (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ; ENVIRONMENT (2) ,
| |
| i i
| |
| j Not required to mitigate the consequences of an HELB.
| |
| i
| |
| ! I i
| |
| l i
| |
| 1 i
| |
| i
| |
| ; QUALIFICATION REPORT: N/A i
| |
| i
| |
| ; METHOD: N/A i i
| |
| REPLACEMENT INTERVAL: N/A f MHVC i _- _ -. ..
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 42 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| ; LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIP.'!ENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Hookup Wire Insulation (Procurement Spec: CNS-1354.04-00-0005)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Tc.mp: 330 F Temp: 385 F Continuous Continuous N/A N/A l
| |
| QUALIFICATION REPORT: 80205-1 (CNM-1354.00-0019)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 43 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: EPR 1
| |
| Medins Voltage Power Insulation (Procurement Specs: CNS-1354.01-00-0001
| |
| & 0003)
| |
| < PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT 'TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| { ENVIRONMENT (2)
| |
| Temp: 330 F Temp: 346 F Continuous Continuous N/A N/A QUALIFICATION REPORT: 80205-1 (CNM-1354.00-0019)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
| |
| . __A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 44 SU MARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Control Insulation (Procurement Specs: CNS-1354.02-00-0001
| |
| & 0002)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRA'stD REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 330 F Temp: 385*F Continuous Continuous N/A N/A QUALIFICATION REPORT: 80205-1 (CNM-1354.00-0019)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O I
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 45 i
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Instrumentation.3nd Control Insulation (Procurement Specs: CNS-1354.03-00-0001, l 0002 & 0003)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 330 F Temp: 385*F Continuous Continuous N/A N/A l
| |
| i 4
| |
| l .
| |
| ; QUALIFICATION REPORT: F-C4836-2 (CNM-1354.00-0020) i l METHOD: Test / Analysis i
| |
| 4 I
| |
| ; REPLACEMENT INTERVAL: N/A ,
| |
| EPSS I
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 46 SLM1ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Low Voltage Power Insulation (Procurement Specs: CNS-1354.01-00-0001
| |
| & 0003)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Tcmp: 330 F Temp: 385 F Continuous Continuous N/A N/A l
| |
| QUALIFICATION REPORT: 80205-1 (CNM-1354.00-0019)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 47
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL #: XLPE Control Insulation (Procurement Specs: CNS-1354.02-00-0001
| |
| , & 0002)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRFD IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| , ENVIRONMENT (2) l Temp: 330 F Temp: 385 F Continuous Continuous N/A N/A J
| |
| QUALIFICATION REPORT: FC-5120-1 and FC-5120-3 (CNH-1354.00-0023) and CNM-1354.00-0024 METHOD: Test I REPLACEMENT INTERVAL: N/A EPSS i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 48 SUMARY OF ENVIPONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| , EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL #: XLPE Coaxial Insulation (Proc rement Spec: CNS-1354.04-00-0004)
| |
| J PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATEU REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) i l Temp: 330 F Temp: 385*F Continuous Continuous N/A- N/A I
| |
| QUALIFICATION REPORT: FC-5120-2 and FC-5120-3 (CNM-1354.00-0021 and CNM-1354.00-0024) j METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| L CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 49
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT 10: Cable - MANUFACTURER: Eaton MODEL #: FR-EPDM Instrumentation and Control Insulation (Procurement Specs:
| |
| CNS-1354.03-00-0001, 0002 & 0003)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) a
| |
| : Temp: 330*F 430'F Continuous Continuous N/A N/A l
| |
| i l
| |
| l QUALIFICATION REPORT: Quali fication test of electrical cables by Isomedix (CNM-1354.00-0035).
| |
| i
| |
| ) METHOD: Test /Analysic 1
| |
| i i REPLACEMENT INTERVAL: N/A EPSS i
| |
| i
| |
| | |
| O O O ,
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 50
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: EPR 4
| |
| Medium Voltage Insulation (Procurement j Specs: CNS-1354.01-00-0001
| |
| ; & 0003) l PIPE RUPTURE ENVIRONMENT OPERABILITY OPERA 8ILITY ACCURACY ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMQNSTRATED REQUIRED DEMONSTRATED 1
| |
| (1) QUALIFIED PIPE RUPTURE (% OF SPAh) (% OF SPAN) :
| |
| { ENVIRONMENT (2) i i
| |
| 1
| |
| ! Temp: 330 F Temp: 455*F Continuous Continuous N/A N/A t
| |
| .i l
| |
| l l
| |
| i l
| |
| 1 QUALIFICATION REPORT: Okonite Report #355 (CNM-1354.00-0022) i
| |
| ; NETHOD: Test 1
| |
| REPLACEMENT INTERVAL: N/A EPSS i
| |
| | |
| i-O O O 4
| |
| ! CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 51 Su m ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS JE EQUIPMENT Rev. 1 l!
| |
| i LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIROMENT l EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: FR-EPR 2
| |
| Control Insulation (Procurement Specs: CNS-1354.02-00-0001 r j & 0002) 4 k
| |
| ; PIPE RUPTURE ENVIRONMENT OPERABILITY OPERA 8ILITY ACCURACY ACCURACY
| |
| ! ENVIRONMENT TO WHICH . REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| : (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| < Temp: 330*F Temp: 455*F Continuous Continuous N/A N/A i
| |
| i
| |
| }
| |
| i I
| |
| l QUALIFICATION REPORT: Okonite Report #355 (CNM-1354.00-0022) i METHOD: Test i
| |
| l REPLACEMENT INTERVAL: N/A EPSS l
| |
| i ;
| |
| }
| |
| i <
| |
| | |
| ry p b
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 52
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL Qi'ALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT 1
| |
| EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: Tefzel Hookup Wire Insulation (Procurement Spec: CNS-1354.04-00-0006)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED
| |
| ; (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ! ENVIRONMENT (2) i Temp: 330 F Temp: 455'F Continuous -
| |
| Continuous N/A N/A s
| |
| QUALIFICATION REPORT: Okonite Report #344 (CNM-1354.00-0026)
| |
| METHOD: Test
| |
| .i REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 53
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Cable Termination MANUFACTURER: Ray Chem MODEL #: WCSF-N Splice Material PIPE RUPTURE ENVIRONMENT CPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMCJT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 330 F Temp: 360 F Continuous Continuous N/A N/A l
| |
| QUALIFICATION REPORT: 71100 & F-C4033-3 (CNM-1367.01-0001 & 2)
| |
| METHOD: Test l
| |
| l REPLACEMENT INTERVAL: N/A . EPSS
| |
| | |
| C\
| |
| O
| |
| ( '\
| |
| U V CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 54 Su MARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Seal Material for Cable MANUFt.CTURER: 3M MODEL #: Scotch Cast 9 Epoxy Entrance Fittings (XR-5240) 4 PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED
| |
| . (1) QUALIFIED PIPE RUPTURE
| |
| (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 330 F Later Continuous Later N/A N/A 1
| |
| I
| |
| ; QUALIFICATION REPORT: Later METHOD: Later i
| |
| EPSS
| |
| | |
| O O O e
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 55 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 i
| |
| LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: Electric Heater and Control MANUFACTURER: Indeeco MODEL #:
| |
| Panel ,
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY
| |
| ' ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) 1 Not Required to mitigate the consequences of an HELB.
| |
| i
| |
| }
| |
| i
| |
| ) '
| |
| I QUALIFICATION REPORT: N/A i
| |
| ! METHOD: N/A i
| |
| ! REPLACEMENT INTERVAL: N/A MHVC R
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 56
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l
| |
| LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT ,
| |
| EQUIPMENT ID: IEATC12 MANUFACTURER: Duke MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212 F Later Continuous Later N/A N/A ,
| |
| : QUALIFICATION REPORT: Later l
| |
| METHOD: Later l
| |
| F
| |
| ! REPLACEMENT INTERVAL: Later !
| |
| 4 i
| |
| ~
| |
| i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 57 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1EATC13 MANUFACTURER: Duke MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN . DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 187 F Temp: 212 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 METil00: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 58
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUAllFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT l EQUIPMENT ID: 1ELCC0046 MANUFACTURER: DUKE MODEL #: N/A l
| |
| (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Enclosure is to be moved to a mild environment.
| |
| 1 i
| |
| QUALIFICATION REPORT: N/A J
| |
| METHOD: N/A 4
| |
| REPLACEMENT INTERVAL: N/A i
| |
| | |
| m d
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 59 SUP9tARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1ELCP0112 MANUFACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) i ENVIRONMENT (2)
| |
| Temp: 127*F Temp: 150 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA-NUCLEAR STATION - UNITS 1 AND 2 Page 60 I SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.1
| |
| .f LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| 'EQUIPMENTcID: 1ELCP0113 -
| |
| MANUFACTURER: DUKE MODEL #: N/A l- (3) -
| |
| .m_
| |
| + PIPE RUPTUNE , ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY E;WIRONMENT- TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) _
| |
| I
| |
| ; Temp: 147*F Temp: 150 F Continuous Continuous N/A NA I
| |
| 1 j
| |
| J 7 QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 61 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| , EQUIPMENT ID: IELCP0167 MANUFACTURER: DUKE MODEL #: N/A 4
| |
| (3) i PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ; ENVIRONMENT (2) i Tecp: 187"F Later Continuous Later N/A N/A-4 i
| |
| I QUALIFICATION REPORT: Later l METHOD: Later i
| |
| REPLACEMENT INTERVAL: Later i
| |
| | |
| 4 O O O i
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 62
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID': 1ELCP0168 MANUFACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED PEQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) i ENVIRONMENT (2) i j Temp: 212 F Later Continuous later N/A N/A I
| |
| 1 QUALIFICATION REPORT: Later 4
| |
| METHOD: Later REPLACEMENT INTERVAL: N/A l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 63
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1ELCP0243 MANUFACTURER: DUKE MODEL #: N/A (3) ,
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED . DEMONSlHATED (1). QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 238*F Temp: 255 F Continuous Continuous N/A N/A t QUALIFICATION REPORT: CNC-1381.05-00-0054 f!ETHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O 0 Q) (J G CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 64 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1ELMC0020 MANUFACTURER: DUKE MODEL #: N/A PIPE RUPTURE ENVIRONMENT PPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO MIICH REQUIRED IN DEMONSTRATED kEQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 127 F Temp: 212 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 .
| |
| METil0D: Test / Analysis 4
| |
| REPLACEMENT INTERVAL: N/A
| |
| | |
| , O O O t
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 65 l SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . Rev. 0 3 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1ELMC0021 MANUFACTURER: DUKE MODEL #: N/A (3) i
| |
| < PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) l Terp: 147 F Temp: 212*F Continuous Continuous N/A N/A 1
| |
| l !
| |
| ! l i
| |
| l 4
| |
| 1 j QUALIFICATION REPORT: CNC-1381.05-00-0054 j METHOD: Test / Analysis i
| |
| j REPLACEMENT INTERVAL: N/A i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 66
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1HSBP000T MANUFACTURER: DUKE' MODEL #: N/A (3) -
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE. (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Te:p: 187*F Temp: 330 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 67 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPME!!T Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: ISMTC1 MANL'FACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Te2p: 212 F Temp: 212 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis l
| |
| REPLACEMENT INTERVAL: N/A l
| |
| | |
| O O
| |
| ~
| |
| : O
| |
| :1 i CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 68 a
| |
| 'SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TB0X0015 MANUFACTURER: DUKE MODEL #: N/A (3) i i PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| I Te:p: 212*F Temp: 330*F Continuous Continuous N/A N/A 1
| |
| i i
| |
| I QUALIFICATION REPORT: CNC-1381.05-00-0054 i
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 69 SUMARY OF ENVIRONMENTAL- QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0-LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTU8tE ENVIRONMENT EQUIPMENT ID: 1TBOX0016 MANUFACTURER: DUKE MODEL #: N/A (3) t i PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212 F Temp: 330 F Continuous Continuous- N/A N/A 4
| |
| QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A e
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 70
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TB0X0017 MANUFACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCUPACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2) i Temp: 212 F Temp: 330 F Continuous Continuous N/A N/A l
| |
| l QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A l
| |
| l
| |
| | |
| ,-- .s s CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 71
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TBOX0018 MANUFACTURER: DUKE MODEL #: N/A j (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED 4
| |
| (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Temp: 212*F Temp: 330 F Continuous Continuous N/A N/A t
| |
| QUALIFICATION REPORT: CNC-1381.05-00-0054 i
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 72 SUP94ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TB0X0019 MANUFACTURER: DUKE MODEL #: N/A l (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN)- (% OF SPAN)
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| ENVIRONMENT (2)
| |
| : Temp: 212 F Temp: 330 F Continuous Continuous N/A N/A i
| |
| QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 73 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TB0f0020 MANUFACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
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| ENVIRONMENT (2)
| |
| Temp: 212 F Temp: 330*F Continuous Continuous N/A N/A 4
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| 4 i
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| QUALIFICATION REPORT: CNC-1381.05-00-0054 .
| |
| I f METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 74
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TB0X0021 MANUFACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 212 F Temp: 330 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATI0"N . UNITS 1 AND 2 Page 75 SUP94ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1T80X0100 MANUFACTURER: DUKE, MODEL #: N/A (3) .
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE. RUPTURE (% OF SPAN) (% OF SPAN)
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| ENVIRONMENT (2)
| |
| Te:p: 187 F Temp: 212 F Continuous Continuous N/A N/A QUALIFICATION REPORT: CNC-1381.05-00-0054 HETHOD: Test / Analysis I
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| i REPLACEMENT INTERVAL: N/A I
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| i
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 76 Rev. 0 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT
| |
| . EQUIPMENT ID: 1TB0X0132 MANUFACTURER: DUKE MODEL #: N/A
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| ; (3)
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| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY . ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
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| ENVIRONMENT (2)
| |
| Temp: 212*F Temp: 255 F Continuous Continuous N/A N/A j QUALIFICATION REPORT: CNC-1381.05-00-0054 i
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| .i i METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A I
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| i
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| | |
| O fN C\
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| V V CATAWBA W3 CLEAR STATION - UNITS 1 AND 2 Page 77 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATE 9 OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: 1TBOX0352 MANUFACTURER: ' DUKE MODEL'#: N/A (3)
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| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) 1
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| , ENVIRONMENT (2) 4 Terp: 330 F Ter.,p: 330 F Continuous Continuous N/A N/A i
| |
| QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| p p-e 's
| |
| %j '
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 78
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT EQUIPMENT ID: ITBOX0353 MANUFACTURER: DUKE MODEL #: N/A (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN) i ENVIRONMENT (2)
| |
| Temp: 180 F Temp: 330*F Continuous Continuous N/A N/A 1
| |
| 4 QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2. Page 79 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO PIPE RUPTURE ENVIRONMENT I EQUIPMENT ID: 1TB0X0481 MANUFACTURER: DUKE MODEL #: N/A
| |
| : (3)
| |
| PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY j ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED PIPE RUPTURE (% OF SPAN) (% OF SPAN)
| |
| ENVIRONMENT (2)
| |
| Terp: 212*F Temp: 220 F Continuous Continuous N/A N/A t
| |
| QUALIFICATION REPORT: CNC-1381.05-00-0054 i
| |
| METHOD: Tect/ Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| f.
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| L PRN-1 Page 80 Rev. O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF CLASS 1E ELECTRICAL EQUIPMENT LOCATED OUTSIDE CONTAINMENT EXPOSED TO PIPE RUPTURE ENVIRONMENT Note 1 The methods employed to evaluate pipebreaks and to determine the resulting environmental parameters are discussed in Section 3.6 of the Catawba FSAR.
| |
| N_ote ?
| |
| t for The pipe of one area rupture the Auxiliary environment is assumed Building, Elevation to exist 543' for 2exists which 1/2 hours-(excep/6 for 2 5 hours) based on 30 minutes at the peak temperature after which action by the operator isolated the break and allows the Auxiliary Building temperature to decrease to normal in 2 hours. Use of the term " Continuous" indicates operability required / .
| |
| demonstrated throughout the pipe rupture period.
| |
| Pressure: Not a significant qualification parameter for pipe rupture outside the containment since all locations outside containment are open areas not susceptable to pressure build-up.
| |
| Relative Humidity: Not a significant qualification aarameter for pipe rupture outside the containment due to tie large open areas in which pipe ruptures occur and the relative short duration O of the pipe rupture environment.
| |
| V Radiation: There is no significant increase in radiation levels outside the containment as a result of a pipe rupture outside the containment.
| |
| Chemical Spray: Not a qualification parameter for pipe rupture outside the contaiment since there is no chemical spray outside the containment.
| |
| Submergence: Based on analysis performed by Duke Power Company, it has been determined that there is no safety-related electrical equipment, required to mitigate the event causing the flood (e.g., pipe rupture) or required to bring the plant to a safe shutdown condition given a flood event, located below the postulated flood levels.
| |
| Note 3 The equipment listed is a NEMA 4 enclosure containing general application devices (e.g., relays, switches terminal blocks, etc.). The qualified environment is dictatedbythesinglelimitingdevicecontainedintheenclosure. The enclosure and device qualification is documented in calculation CNC-1381.05-00-0054.
| |
| l
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| | |
| 9 O ATTACHMENT 4 1
| |
| | |
| ==SUMMARY==
| |
| OF EfNIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE ,
| |
| POST-LOCA RECIRCULATION RADIATION ENVIRONMENT Page Rev. M- Rev. & Rev.
| |
| 1- 1 36 1 70 0 2 1 37 1 71 0 3 1 38 1 72 0 4 1 39 1 73 0 5 1 40 1 74 0 6 1 41 1 75 0 7 1 42 1 76 0 '
| |
| S 1 43 1 77 0 9 1 44 1 78 0 10 1 45 1 79 0 11 1 46 1 80 0 12 1 47 1 RN-1 1 >
| |
| 13 1 48 1 14 1 49 O
| |
| .V 15 1 50 1
| |
| 1 16 1 51 1 17 1 52 1 18 1 53 1 19 1 54 0 20 1 55 0
| |
| - 21 1 56 0 22 1 57 0 23 1 58 0 24 1 59 0
| |
| ! 25 1 60 0 26 1 61 0 27 1 62 0 28 1 63 0 29 1 64 0 29A 0 65 0 30 1 66 0 l 31 1 67 0 32 1 68 0 33 1 69 0 34 1 35 1 O
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| l
| |
| ,9 ._
| |
| ,, .-+w,- e-ga -
| |
| ,---m -e%+,*v----*--m'--^w r--=~twitv-'e-r w'T-* *** '''M'- ' -""'***'T ~ " ' ' " ' ' ' ' ' - ' ' " ^ * * * ~ ' "**#
| |
| | |
| l O O O t
| |
| i CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 1 i SUP#tARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i-
| |
| ! EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 386A (1) NW Surge Chamber Level RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID).(2) (TID) 1.0X103 RAD 2.0X108 RAD QUALIFICATION REPORT: Wyle Report #43904-1 Vol. I Rev. C, Vol. II-Rev. B (CNM-1210.04-252)
| |
| METHOD: Test REPLACEMENT INTERVAL: 10 years MPIC
| |
| | |
| ; O O O i
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 2 i SUMARY OF. ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT t EQUIPMENT ID: Pressure Transmitter (HVAC) MANUFACTURER: Rosemount MODEL #: 1152 ,
| |
| I (1)
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| { RECIRCULATION RADIATION RADIATION . LEVEL TO WHICH 1 ENVIRONMENT QUALIFIED (TID) (2) (TID) 4.9X105 RAD 5.0X108 RAD i
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| \
| |
| 8 QUALIFICATION REPORT: Rosemount Test Report 38019 (CNM-1211.00-1778)
| |
| METHOD: Test i
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| REPLACEMENT INTERVAL: N/A MHVC t
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 .
| |
| Page 3 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Transmiiter - MANUFACTURER: Barton MODEL #: 336A (1) Containment Pressure.(NR)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.0X103 RAD 2.0X108 RAD QUALIFICATION REPORT: Wyle Report #43904-1, Vol. I - Rev. C, Vol. II - Rev. B (CNM-1210.04-252)
| |
| METHOD: Test REPLACEMENT INTERVAL: 10 years
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 4
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Rosemount MODEL #: 1153D86 (1) Containment Pressure RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)-
| |
| 1.0X108 RAD 2.4X107 RAD 4
| |
| 1
| |
| ; QUALIFICATION REPORT: Rosemount Reports 108025 and 108026 i
| |
| l METHOD: Test / Analysis j REPLACEMENT INTERVAL: 10 years
| |
| | |
| O ,
| |
| O .
| |
| O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 5
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| ! EQUIPMENT ID: Pressure Transmitter- MANUFACTURER: Barton 'MODEL #: 386A (1) Annulus Pressure i
| |
| ! RECIRCULATION RADIATION 1 RADIATION LEVEL TO WHICH
| |
| ; ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| I j 1.0X103 RAD 2X108 RAD I
| |
| 1 QUALIFICATION REPORT: Wyle Report #43904-1, Vol. I - Rev. C, Vol. II - Rev. B (CNM-1210.04-252)
| |
| METHOD: Test 1
| |
| REPLACEMENT INTERVAL: 10 years i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 6
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Cornwall Inst. MODEL #: 100 (1) ESF Filters Downstream HEPA Differential Pressure RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X107 RAD Later i
| |
| QUALIFICATION REPORT: Later METHOD: Later REPLACEMENT INTERVAL: Later MHVC Note: Transmitter is to be replaced. Submittal will be updated on next revision 9
| |
| | |
| ~
| |
| [ -
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| M CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 7
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Revi'.0 ~
| |
| LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA PECIRCULATION RADIATION ENVIRONMENT .
| |
| EQUIPMENT ID: NSR Filters / Differential MANUFACTURER: Foxboro MODEL #: N-E10 Series f
| |
| i (1) Pressure Transmitter '
| |
| s RECIRCULATION RADIATION - "
| |
| ; RADIATION LEVEL TO WHICH
| |
| ! ENVIRONMENT QUALIFIED
| |
| ,' (TID) (2) (TID) i 2X107 RAD 2.2X108 RAD d
| |
| QUALIFICATION REPORT: 45592-4 (CNM-1211.00-1792)
| |
| METI;0D: Test REPLACEMENT INTnRVAL: Later MHVC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 8 SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRCMENT EQUIPMENT ID: Differential Pressure Switch MANUFACTURER: Penn MODEL #: P67CA-1 (1)
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| RECIRCULATION RADIATION RADIATION ' LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| <1X103 RAD N/A TO BE DELETED QUALIFICATION REPORT: N/A METHOD: N/A ,
| |
| l REPLACEMENT INTERVAL: N/A MHVC
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| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 ANO 2 Page 9
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 2E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT 4
| |
| EQUIPMENT ID: Differential Pressure Switch MANUFACTURER: Solon MODEL #: 7PS11DW (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 4 8X10sRAD- Later l
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| 4 I
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| t i
| |
| I i
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| l QUALIFICATION REPORT: Later METHOD: Later REPLACEMENT INTERVAL: Later MHVC 4
| |
| | |
| O . O O i I
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Fage 10 SUMARY OF ENVIR0 MENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAIMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIROMENT -
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| i EQUIPMENT ID: Temperature Switch MANUFACTURER: United Electric MDOEL #: 800-6BS/6CS i (1)
| |
| RECIRCULATION RADIATION i RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| <1.0X108 RAD N/A !
| |
| TO BE DELETED t
| |
| QUALIFICATION REPORT: N/A METHOD: N/A REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 11 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIR0! MENT i'
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| EQUIPMENT ID: Pressure Switch MANUFACTURER: Dwyer MODEL #: 3000-0 (1) l RECIRCULATION RADIATION RADIATION LEVEL TO WHICH
| |
| ', ENVIRONMENT QUALIFIED (TID) (2) (TID) i
| |
| <1.0X108 RAD N/A TO BE DELETED i
| |
| 4 i
| |
| j QUALIFICATION REPORT: N/A i
| |
| I i METHOD: N/A i
| |
| i REPLACEMENT INTERVAL: N/A MHVC i
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| l
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 12 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIAIION ENVIRONMENT
| |
| ~
| |
| EQUIPMENT ID: Pressure Switch - . MANUFACTURER: SOR Inc. MODEL #: 12N-B4-HX-C (1) NW Surge Chamber Pressure i
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH
| |
| , ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.0X103 RAD Later ,
| |
| QUALIFICATION REPORT: Later i
| |
| METHOD: Later 4
| |
| REPLACEMENT INTERVAL: Later MPIC I
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| | |
| O O O CATAWBA NUCLEAR STATI0Pi - UNITS 1 AND 2 Page 13 SUPMARY OF ENVIR0tMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: D/P Switch - MANUFACTURER: Barton MDDEL #: 580A-1 (1) KC Surge Tank Level RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3.1X10sRAD 2.0X108 RAD QUALIFICATION REPORT: Barton Report #348-8890 Rev. A l METHOD: Test REPLACEMENT INTERVAL: Later MPIC
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| | |
| O O O 1
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 14 i
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| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i .
| |
| l .
| |
| EQUIPMENT 10: Limit Switches MANUFACTURER: NAMCO MODEL #: EA-170 (1)
| |
| ! RECIRCULATION ' RADIATION
| |
| ! RADIATION LEVEL TO WHICH i ENVIRONMENT QUALIFIED !
| |
| (TID) (2)
| |
| : (TID) 8X108 RAD 2X108 RAD i
| |
| i t
| |
| i QUALIFICATION REPORT: QTR-107 1
| |
| METHOD: Test REPLACEMENT INTERVAL: 5 years MHVC/MEQP
| |
| | |
| N--
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 15
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Damper Limit Switches MANUFACTURER: NAMCO MODEL #: EA-180 (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT '
| |
| QUALIFIED (TID) (2) (TID) 8X10sRAD 2.36X108 RAD QUALIFICATION REPORT: QTR-106 (CNM-1205.19-42)
| |
| METHOD: Test .
| |
| REPLACEMENT INTERVAL: 4 years MHVC
| |
| .. . . 1
| |
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| 4
| |
| {
| |
| ' CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 16 j
| |
| Rev. 1 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT i LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i.
| |
| ) EQUIPMENT ID: Level Switches MANUFACTURER: Magnetrol MODEL #: A103F-3X-MPG j (1) ND & NS Room Sump Level RECIRCULATION RADIATION RADIATION LEVEL TO WHICH
| |
| . ENVIRONMENT QUALIFIED j (TID) (2) (TID) l 5.3X10sRAD Later l
| |
| ; i I
| |
| ; QUALIFICATION REPORT: Later l i
| |
| ; METHOD: Later .
| |
| i l
| |
| i l REPLACEMENT INTtRVAL: Later MPIC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 17 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Temperature Controller MANUFACTURER: Love Controls MODEL #: 54-834-8160-8134-838-8174 (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| <1.0X108 RAD Later TO BE DELETED QUALIFICATION REPORT: Later METHOD: Later 6
| |
| MHVC
| |
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 18
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: RTD/ Control Room Temperature MANUFACTURER: Weed MODEL #: 601 Series l (1) Control i RECIRCULATION RADIATION
| |
| ; RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED
| |
| ; (TID) (2) (TID)
| |
| I 4
| |
| 4.08X104 RAD Later d
| |
| l
| |
| ; QUALIFICATION REPORT: Later METHOD: Later !
| |
| ! REPLACEMENT INTERVAL: Later MHVC i
| |
| l
| |
| | |
| O O O '
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 19 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Residual Heat Removal Pump MANUFACTURER: Westinghouse, Buffalo MDDEL #: LAC-TEWC (1) Motors (NSSS)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.8X108 RAD 2X10sRAD QUALIFICATION REPORT: WCAP 8754, Rev. I and Calculation MCC-1385.05-00-0102 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 20
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT 19: Centrifugal Charging Pump MANUFACTURER: Westinghouse, Buffalo MODEL #: LLD-TEWC (1) Motors (NSSS)
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| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 6.1X10sRAD 2X108 RAD QUALIFICATION REPORT: WCAP 8754, Rev. 1 and Calculation MCC-1385.05-00-0102 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A MEQP 1 . . _ _ _ _ _ _ _ _ __
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| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 21
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Fuel Pool Cooling Pump Motors MANUFACTURER: Westinghouse, Buffalo MODEL #: 73F69065 S/N 1&2 (1) . 73F69066 S/N 1&2 1
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| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 5.3X103 RAD 2X108 RAD i
| |
| j f
| |
| i
| |
| , QUALIFICATION REPORT: CNM-1318.00-0004; CNM-1318.00-0005 i
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSR i
| |
| l
| |
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 22
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 '
| |
| LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE. POST-LOCA RECIRCULATTON RADIATION ENVIRONMENT 3 EQUIPMENT ID: Boric Acid Transfer MANUFACTURER: Westinghouse /Chempump MODEL f: GVH-10K-12H-15 j (1)' Pump Motors (NSSS) i
| |
| ; RECIRCULATION P.ADIATION i RADIATION LEVEL TO WHICH i
| |
| ENVIRONMENT QUALIFIED l (TID) (2) (TID) i
| |
| <1.0X103 RAD Later i
| |
| TO BE DELETED j
| |
| i i
| |
| I, j
| |
| I QUALIFICATION REPORT: Later METHOD: Later i
| |
| HEQP i
| |
| 2
| |
| | |
| O O O
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| , CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 23 i
| |
| SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1
| |
| , LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i .
| |
| EQUIPMENT ID: Annulus Ventilation MANUFACTURER: Joy / Reliance MODEL #: 1XF-882739 j (1) Fan Motors l RECIRCULATION RADIATION j RADIATION LEVEL TO WHICH I
| |
| ENVIRONMENT QUALIFIED j (TID) (2) (TID) 8.0X108 RAD 1.0X108 RAD j
| |
| i I t QUALIFICATION REPORT: NUC-9 (CNM-1211.00-1010); X-604(CNM-1211.00-1009) t i
| |
| l METHOD: Test / Analysis
| |
| ; REPLACEMENT INTERVAL: N/A MHVC -
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| l
| |
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 24
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| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 3 LOCATE 0 OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT j
| |
| EQUIPMENT ID: Chilled Water Pump MANUFACTURER: Reliarce MODEL #: 1YF-882766 l (1) Motors 1YF-882766 RECIRCULATION RADIATION j RADIATION LEVEL TO WHICH 2
| |
| ENVIRONMENT QUALIFIED 4
| |
| (TID) (2) , (TID) i 4.9X10sRAD 1X108 RAD i
| |
| i i
| |
| j QUALIFICATION REPORT: Radiation Qualification Report (CNC-1381.05-00-0055) l METHOD: Test / Analysis
| |
| '. REPLACEMENT INTERVAL: N/A EPSR
| |
| | |
| ; CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 25 .
| |
| : i. SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. I i LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE' POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i EQUIPMENT ID: Control Room Air Handling MANUFACTURER: Reliance MODEL #: 1YF-882986, 2YF-882986 i (1) Unit Fan Motors RECIRCULATION RADIATION I
| |
| RADIATION LEVEL TO WHICH
| |
| ! ENVIRONMENT QUALIFIED (TID) (2)
| |
| (TID) i 5.6X10sRAD 1X10 8RAD t
| |
| i i
| |
| l l
| |
| Radiation Qualification Report (CNC-1381.05-00-0055)
| |
| QUALIFICATION REPORT:
| |
| i i
| |
| i
| |
| ; METHOD: Test / Analysis l
| |
| i i REPLACEMENT INTERVAL: N/A EPSR i
| |
| , ...v .-- - , _ , . - , . -
| |
| | |
| (3 (D O 1
| |
| V t) U .
| |
| i CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 26 l
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| ] LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT a EQUIPMENT ID: Control Room Area Air MANUFACTURER: Reliance MODEL #: 1XF-882609, 2XF-882609 (1) Handling Unit Fan Motors 1YF-883344, 1YF-882760 RECIRCULATION RADIATION 4
| |
| RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 4.1X104 RAD 1X10sRAD
| |
| .I 5
| |
| i QUALIFICATION REPORT: Radiation Qualification Report (CNC-1381.05-00-0055)
| |
| METHOD: Test / Analysis l REPLACEMENT INTERVAL: N/A -
| |
| EPSR I
| |
| I
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 27 i
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATI0ll ENVIRONMENT 1
| |
| EQUIPMENT ID: Fuel Handling Area Exhaust MANUFACTURER: Joy / Reliance MODEL #: 1YF-882585, 2YF882585 (1) Fan Motors 1YF-882745 4
| |
| RECIRCULATION RADIATION l RACIATION LEVEL TO WHICH i ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.4X10sRAD 1X108 RAD l
| |
| i QUALIFICATION REPORT: Radiation Qualification Report (CNC-1381.05-00-0055)
| |
| METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSR 1
| |
| l
| |
| | |
| 4 O O O 4
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 -Page 28
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| . EQUIPMENT'ID: Auxiliary Building Filtered MANUFACTURER: Reliance MODEL #: 1XF882610, 2XF882610 (1) Exhaust Fan Motors IXF882771 RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED l
| |
| (TID) (2) (TID) 4 4
| |
| 1.1X108 RAD 1X108 RAD t
| |
| QUALIFICATION REPORT: Radiation Qualification Report (CNC-1381.05-00-0055)
| |
| METHOD: Test / Analysis
| |
| ; REPLACEMENT INTERVAL: N/A EPSR 1
| |
| 2
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 29 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| , EQUIPMENT ID: Containment Spray and Residual MANUFACTURER: Reliance MODEL #: 1YF882456, 1YF882767 (1) Heat Removal Pump Room Sump
| |
| { Pump Motors RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) t 2.6X105 RAD 1X108 RAD l
| |
| i 1
| |
| I i
| |
| j QUALIFICATION REPORT: Radiation Qualification Report (CNC-1381.05-00-0055) i i
| |
| HETH00: Test / Analysis l
| |
| 1 REPLACEMENT INTERVAL: N/A EPSR
| |
| | |
| O O O 4
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 29A
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT F
| |
| EQUIPMENT ID: Switchgear Room Air Handling MANUFACTURER: Reliance MODEL #: 1YF-882577, 2YF-882577 (1) Unit Fan Motor 1YF-882758, 2YF-882758 ,
| |
| RECIRCULATION RADIATION i RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.0X103 PAD 1X108 RAD I
| |
| QUALIFICATION REPORT: Radiation Qualification Report (CNC-1381.05-00-0055)
| |
| : METHOD: Test / Analysis
| |
| ; REPLACEMENT INTERVAL: N/A EPSR i
| |
| i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 30
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LDCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Containment Spray Pump MANUFACTURER: Westinghouse, Buffalo MODEL #: 74F18671 S/N 1 & 2 (1) Motors 74F18672 S/N 1 & 2 RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.0X105 RAD 2.0X108 RAD 1
| |
| I i
| |
| j QUALIFICATION REPORT: CNM-1318.00-0004; CNM-1318.00-0005 i
| |
| METHOD: Test i
| |
| ; REPLACEMENT INTERVAL: N/A EPSR l
| |
| i
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 31 SUP9tARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ED: Control Room Pressure Filter MANUFACTURER: Joy / Reliance MODEL #: 1YF-882680 (1) Fan Motors RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| <l.0X108 RAD IX109 RAD TO BE DELETED QUALIFICATION REPORT. X-604 (CNM-1211.00-1009)
| |
| NETHOD: Test e
| |
| MHVC
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 32 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Safety Injection Pump Motor MANUFACTURER: Westinghouse MODEL #: LAC-TEWC (1) (NSSS)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.0X108 RAD 2.0X10 8RAD j
| |
| QUALIFICATION REPORT: WCAP8754, Rev. 1 (CNM-1201.05-0424)
| |
| METHOD: Test / Analysis i
| |
| REPLACEMENT INTERVAL: N/A MEQP l
| |
| l
| |
| | |
| ~
| |
| O .
| |
| O O l
| |
| i .
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 33 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIR0tNENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SMB RH Motor Insulation
| |
| ] (1) i RECIRCULATION RADIATION
| |
| ; RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED !
| |
| 4 (TID) (2) (TID) 2.8X108 RAD 2X108 RAD QUALIFICATION REPORT: 600-376-A, September 1972 and 600-465, December 19'E (CNM-1205.19-0001) l l METHOD: Test REPLACEMENT INTERVAL: N/A MEQP
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| --r- , 7
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 34 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0
| |
| , LOCATED OUTSIDE CONTAINMENT AND EXPOSFs TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque- ' MODEL #: SMB B Hotor Insulation
| |
| ' (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH 4
| |
| ENVIRONMENT QUALIFIED ,
| |
| (TID) (2) (TID) -
| |
| 1
| |
| ; 2.8X108 RAD 2X107 RAD i
| |
| .i QUALIFICATION REPORT: B0003, May 1976 (CNM-1205.19-0001) i METHOD: Test REPLACEMENT INTERVAL: N/A , MEQP
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 35 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-1 (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) i i
| |
| ) 2.8X10sRAD 2X108 RAD i
| |
| l l
| |
| I 1 i
| |
| QUALIFICATION REPORT: TR-116, October 1973 (CNM-1205.19) i !
| |
| l METHOD: Test t
| |
| l REPLACEMENT INTERVAL: N/A MEQP l
| |
| 1
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 36
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTitL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIA110N ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-2 with NA-1 (1) Switch Mechanism
| |
| ; RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 4.2X108 RAD 3X107 RAD QUALIFICATION REPORT: N 14/2, May 1980 (CNM-1205.19-0019) l METHOD: Test REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| O O O 1
| |
| 4 CATAWBA NUCLEAR STATION UNITS 1 AND 2 Page 37
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V70900-21-3 i (1) 4 i RECIRCULATION RADIATION i RADIATION LEVEL TO WHICH j ENVIRONMENT QUALIFIED 4
| |
| (TID) (2) (TID)
| |
| I 7.8X108 RAD 2X10sRAD l
| |
| i i
| |
| j QUALIFICATION REPORT: QR-70900-21-1, Rev. A; QR-52600-515, Rev. B; MR-70905-21-3-1 (CNM-1210.04-253, 254 and MCM-1210.04-119)
| |
| METHOD: Test / Analysis
| |
| : REPLACEMENT INTERVAL: 5 years MPIC I
| |
| i
| |
| | |
| D O /
| |
| (0_/ .
| |
| i
| |
| : CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 38 i
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| SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POSI-LOCA RECIRCULATION RADIATION ENVIRONMENT j EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V526 j (1) i RECIRCULATION RADIATION l RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| I
| |
| : 2.8X108 RAD 2X108 RAD i
| |
| i i
| |
| l QUALIFICATION REPORT: QR-52600-6042-1 (CNM-1205.08-0047) i METHOD: Test t
| |
| ; REPLACEMENT INTERVAL: N/A MEQP
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 39 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 3-way Valve Soleaoid Operators MANUFACTURER: Asco MODEL #: NP83?0A172E/V (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3.0X105 RAD 2.0X107 RAD QUALIFICATION REPORT: AQR-67368 Rev. 0 (CNM-1211.00-1780)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| i O O O
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| ! CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 40
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE. CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT l
| |
| j ' EQUIPMENT ID: Electro-Hydraulic Damper MANUFACTURER: ITT General Controls MODEL #: NH-90EH Series (1) Operators RECIRCULATION RADIATION.
| |
| RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| ! 8X108 RAD 8.0X107 RAD i
| |
| 1 t
| |
| i t
| |
| i QUALIFICATION REPORT: 721.77.095 (CNM-1211.00-1182) l l METHOD: Test l
| |
| I l
| |
| REPLACEMENT INTERVAL: N/A MHVC l
| |
| l; I
| |
| | |
| T CATAWBA NUCLEAR STATION - UNITS 1 AND 2 'Page 41
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E-EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| , EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: EPR. Insulation (1) Medium Voltage (Procurement Specs: CNS-1354.01-00-0001
| |
| & 0003)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH 1 ENVIRONMENT QUALIFIED-(TID) (2) (TID) i 1
| |
| 2X108 RAD 2X108 RAD i
| |
| ?
| |
| QUALIFICATION REPORT: G-3 (CNM-1354.00-0007)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS ,
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 42
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: FR-EPR Insulation (Procurement ,
| |
| (1) Control Specs: CNS-1354.02-00-0001 1
| |
| & 0002)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) i 2X108 RAD 2X10 8RAD l
| |
| l l
| |
| l QUALIFICATION REPORT: FN-1 (CNM-1354.00-0006) l METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| i O O O 2
| |
| CATAWBA NUCLEAR STATION - UNIIS 1 AND 2 Page 43 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. i l' LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| ! EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: Tefzel
| |
| ! (1)- Hookup wire Insulation (Procurement Spec: CNS-1354.04-00-0006) i RECIRCULATION RADIATION
| |
| ! RADIATION' LEVEL TO WHICH l ENVIRONMENT QUALIFIED (TID) (2) 4 (TID) i
| |
| ; 2X108 RAD 2X10sRAD 1
| |
| i i
| |
| l !
| |
| QUALIFICATION REPORT: K-0-1 (CNM-1354.00-0004) i METHOD: Test 1
| |
| ] REPLACEMENT INTERVAL: N/A EPSS i
| |
| i A ...
| |
| | |
| o o o
| |
| ~
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 44
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT 4
| |
| l EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL #: XLPE Insulation j (1) Control (Procurement Specs: CNS-1354.02-00-0001
| |
| & 0002)
| |
| J RECIRCULATION RADIATION
| |
| ! RADIATION LEVEL TO WHICH
| |
| : ENVIRONMENT
| |
| ' QUALIFIED (TID) (2) (TID) 2X108 RAD- 2X108 RAD i
| |
| I l
| |
| QUALIFICATION REPORT: F-C5120-1 (CNM-1354.00-0023)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| 7-s p g ..
| |
| d V (
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 45
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Re v. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Brand-Rex MODEL #: XLPE Insulation (1) Coaxial (Procurement Spec: CNS-1354.04-00-0004)
| |
| RECIRCULATION RADIATION
| |
| -RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED
| |
| : (TID) (2) (TID) l 2X108 RAD 2X108 RAD l
| |
| I i
| |
| l QUALIFICATION REPORT: F-C5120-2 (CNM-1354.00-0021) i 4
| |
| i
| |
| ! METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| )
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 46
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable'- MANUFACTURER: Anaconda MODEL #: FR-EPR Insulation (1) Hookup Wire (Procurement Spec: CNS-1354.04-00-0006)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X108 RAD 2X108 RAD QUALIFICATION REPORT: Test Report F-C4836-4 (CNM-1354.00-0017)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 47
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA REDIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: EPR Insulation (1) Medium Voltage Power (Procurement ~
| |
| Specs: CNS-1354.01-00-0001
| |
| & 0003)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH j ENVIRONMENT QUALIFIED l (TID) (2) (TID) l 2X108 RAD 2X10sRAD QUALIFICATION REPORT: F-C4350-3 (CNM-1354.00-0003)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 48
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Insulation (1) Control (Procurement Specs: CNS-1354.02-00-0001
| |
| & 0002)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X108 RAD 2X198 RAD QUALIFICATION REPORT: F-C4969-1 and 80282 (CNM-1354.00-0009)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 49
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVICONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Insulation j (1) Instrumentation and Control (Procurement 4
| |
| Specs: CNS-1354.03-00-0001, 0002 & 0003)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH j ENVIRONMENT QUALIFIED i
| |
| (TID) (2) (TID) l i
| |
| 2X108 RAD 2X108 RAD 1
| |
| 1 l
| |
| I i
| |
| l QUALIFICATION REPORT: F-C4836-2 (CNM-1354.00-0020)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A EPSS l
| |
| l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 ANO 2 Page 50 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED 10 THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable - MANUFACTURER: Anaconda MODEL #: FR-EPR Insulation (1) Low Voltage Power (Procurement Specs: CNS-1354.01-00-0001
| |
| & 0003)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WilICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X108 RAD 2X108 RAD
| |
| ; QUALIFICATION REPORT: F-C4350-2 (CNM-1354.00-0002) i METHOD: Test REPLACEMENT INTERVAL: N/A EPSS I
| |
| | |
| O O O
| |
| )
| |
| CATAWBA NUCLEAR STATION - UNITS 1'AND 2- Page 51
| |
| ' SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Cable Termination Splice MANUFACTURER: Raychem MODEL #: WCSF-N (1) Material-1 RECIRCULATION RADIATION ;
| |
| I RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X108 RAD 2X108 RAD QUALIFICATION REPORT: F-C4033-3 and 71100 (CNM-1367.01-0002) l METHOD: Test l
| |
| REPLACEMENT INTERVAL: N/A EPSS
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 52
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICAliON OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| ; EQUIPMENT ID: Seal Material - MANUFACTURER: 3M MODEL #: Scotch Cast 9 Epoxy (1) (XR-5240)
| |
| ! RECIRCULATION RADIATION RADIATION LEVEL TO WHICH i ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X108 RAD 2X108 RAD i
| |
| 1 l
| |
| i I
| |
| i
| |
| ! QUALIFICATION REPORT: 44390-1 (CNM-1364.00-0001)
| |
| METHOD: Test REPLACEMENT INTERVAL: Later EPSS
| |
| | |
| i i
| |
| i CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 53 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0
| |
| , LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT 4
| |
| , EQUIPMENT ID: Electric Heater and MANUFACTURER: Indeeco MODEL #: N/A (1) Control Panel i
| |
| 3 I
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH l ENVIRONMENT QUALIFIED l (TID) (2) (TID) 1 1.0X108 RAD 1.0X108 RAD '
| |
| l i
| |
| I i
| |
| j QUALIFICATION REPORT: CCL No. A-447-82-01
| |
| )
| |
| l METHOD: Test REPLACEMENT INTERVAL: N/A MHVC i
| |
| i
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 54
| |
| ' SUP9tARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .
| |
| Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: NSR Filers / Electric Heater MANUFACTURER: Indeeco MODEL #: N/A (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2.0X107 RAD 2.0X108 RAD QUALIFICATION REPORT: A-447-82-01 (CNM-1211.00-1544)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 55
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| ! EQUIPMENT ID: NSR Filters / Fire Detection MANUFACTURER: Alison MODEL #: A-971 Series j (1) System i
| |
| ! RECIRCULATION RADIATION RADIATION LEVEL TO WHICH_
| |
| ! ENVIRONMENT- QUALIFIED (TID) (2) (TID) i 2.0X107 RAD 1.33X109 RAD
| |
| 'l I
| |
| 1 i
| |
| J 4
| |
| l QUALIFICATION REPORT: 45155-1 (CNM-1211.00-1559) 4 METHOD: Test l
| |
| l REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS _1 AND 2 Page 56
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1
| |
| _ LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Control Room Area Chillers _ MANUFACTURER: Carrier MODEL #: 19FA (1) Auxiliary Power Panel RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 4.1X104 RAD 1.0X108 RAD t
| |
| 4 1
| |
| l i
| |
| l
| |
| * l i
| |
| i l QUALIFICATION REPORT: A-133-77 (CNM-1211.00-0071) i l
| |
| l METHOD: Test l
| |
| REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| (~ 3
| |
| '(O) \
| |
| '(d CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 57
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Control Room Area Chillers MANUFACTURER: Carrier MODEL #: N/A (1)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 5.6X105 RAD 1.0X108 RAD QUALIFICATION REPORT: A-133-77 (CNM-1211.00-71)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MHVC i
| |
| l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 58
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Humistat/ Auxiliary Bldg. MANUFACTURER: American Instrument MODEL #: Hygrosensor (1) Exhaust Isolation RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3.0X105 RAD 1.0X107 RAD QUALIFICATION REPORT: DTB04R76-0146 (CNM-1211.00-563)
| |
| METHOD: Test REPLACEMENT INTERVAL: N/A MHVC
| |
| | |
| 4 O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 -Page 59
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i
| |
| , EQUIPMENT ID: 1EATC9 MANUFACTURER: Duke MODEL #: N/A (1).
| |
| (3)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| A 1.0X104 RAD 1.25X104 RAD
| |
| .l 4
| |
| i QUALIFICATION REPORT: CNC-1381.05-00-0054 i
| |
| METHOD: Test / Analysis
| |
| ; REPLACEMENT INTERVAL: N/A l
| |
| | |
| b)
| |
| (./ N b
| |
| V CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 60 SUMARY OF ENVIRCNMENTAL QUALIFICATION OF '6 LASS 1E EQUI!HENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: IEATC9A MANUFACTilRER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED
| |
| ! (TID) (2) (TID) 1.2X104 RAD Later i
| |
| 4 4
| |
| 1' QUALIFICATION REPORT: Later l
| |
| l METHOD: Later l
| |
| i l
| |
| REPLACEMENT INTERVAL: N/A l
| |
| l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 61
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0
| |
| , LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
| |
| ; EQUIPMENT ID: IELCP0112 MANUFACTURER: Duke MODEL #: N/A l (1) 1 (3)
| |
| RECIRCULATION RADIATION
| |
| ; RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 5.0X108 RAD 1.25X104 RAD l
| |
| 1 i
| |
| I i QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 62 ,
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT ,
| |
| EQUIPMENT ID: 1ELCP0113 MANUFACTURER: Duke MODEL #: N/A ,-
| |
| .. ?
| |
| (1)
| |
| , (3)
| |
| RECIRCULATION RADIATION l RADIATION LEVEL TO WHICH ,
| |
| ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| Later - Enclosure is Later being shielded i
| |
| l I ,
| |
| i J
| |
| i QUALIFICATION REPORT: Later I
| |
| l METHOD: Later l
| |
| REPLACEMENT INTERVAL: N/A l
| |
| l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 5 Page 63 S'JMMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: IELCP0168 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| <1.0X108 RAD N/A Enclosure is being moved QUALIFICATION REPORT: N/A METHOD: N/A l REPLACEMENT INTERVAL: N/A l
| |
| | |
| Q.
| |
| \) C)
| |
| (>
| |
| M.
| |
| (d CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 64 SUPMARY OF ENVIRONMENTA'. QUALIFICATION OF CLASS IE EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1ELMC0020 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) ;
| |
| 9.0X103 RAD 1.25X104 RAD QUALIFICATION REPORT: CNC-1381.05-00-0054 i
| |
| METHOD: Test / Analysis e
| |
| REPLACEMENT INTERVAL: N/A l
| |
| | |
| O O- O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 65 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1ELMC0021 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) l Later Later Enclosure is being shielded 1
| |
| l QUALIFICATION REPORT: Later 1
| |
| METHOD: Later REPLACEMENT INTERVAL: Later
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 66 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: ITB0X0015 MANUFACTURER: Duke M00EL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION 1 RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED l (TID) (2) (TID)
| |
| )
| |
| ., 2.8X108 RAD 3.0X107 RAD i
| |
| i 4
| |
| j 1
| |
| QUALIFICATION REPORT: Clic-1381.05-00-0054 l :
| |
| ]
| |
| METHOD: Test / Analysis I
| |
| . REPLACEMENT INTERVAL: N/A
| |
| )
| |
| i l
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 67
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF 4; ASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1TBOX0019 MANUFACTURER: Duke M00EL #: N/A (1)
| |
| (3)
| |
| ~
| |
| RECIRCULATION RADIATION
| |
| ; RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2.8X108 RAD 3.0X107 RAD l
| |
| 4
| |
| ;l i
| |
| ; QUALIFICATION REPORT: CNC-1381.05-00-0054 l
| |
| METHOD: Test / Analysis
| |
| ]
| |
| REPLACENENT INTERVAL: N/A r
| |
| i
| |
| | |
| O O O I
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 68 SUM ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT.
| |
| ! EQUIPMEKr ID: 1TBOX0020 MANUFACTURER: Duke MODEL #: N/A t (1) l (3) l RECIRCULATION RADIATION
| |
| ! RADIATION LEVEL TO WHICH j ENVIRONMENT QUALIFIED
| |
| , (TID) (2) (TID) i i
| |
| 1 3.0X108 RAD 3.0X107 RAD i
| |
| i i;
| |
| 8 i
| |
| 1
| |
| ! QUALIFICATION REPORT: CNC-1381.05-00-0054 ll 1
| |
| i METHOD: Test / Analysis J
| |
| REPLACEMENT INTERVAL: N/A i
| |
| | |
| ~
| |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 69 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1TBOX0021 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RAOIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| I l
| |
| 3.0X108 RAD 3.0X107 RAD QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 70
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O '
| |
| LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1TB0X0298 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION I RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) l 9.3X105 RAD 1.0X108 RAD l
| |
| l QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O 1
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 71
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1TB0X0299 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED l (TID) (2) (TID) J l
| |
| 1.9X105 RAD 1.0X108 RAD l '
| |
| L ,
| |
| l QUALIFICATION REPORT: CNC-1381.05-00-0054 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 72 SUf9tARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0 l LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1TBOX0345 MANUFACTURER: Duke MODEL #: N/A (1).
| |
| (3)
| |
| RECIRCULATION RADIATION
| |
| , RADIATION LEVEL TO WHICH
| |
| ; ENVIRONMENT QUALIFIE9 (TID) (2) (TID) 4.9X105 RAD 2.7X108 RAD l
| |
| 4 l
| |
| l i
| |
| QUALIFICATION REPORT: CNC-1381.05-00-0054 i
| |
| HETH00: Test / Analysis j REPLACEMENT INTERVAL: N/A j .
| |
| | |
| i .
| |
| O O O i- CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 73 sV MAf:Y OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 1TB0X0346 MANUFACTURER: Duke MODEL #: N/A (1)
| |
| (3)
| |
| RECIRCULATION RADIATION
| |
| ; RADIATION LEVEL TO WHICH 1
| |
| ENVIRONMENT QUALIFIED (TID) (2) (TID)
| |
| ; 5.6X10sRAD 2.7X108 RAD j
| |
| I
| |
| .i QUALIFICATION REPORT: CNC-1381.05-00-0054 ,
| |
| I
| |
| : METHOD: Test / Analysis i
| |
| REPLACEMENT INTERVAL: N/A l
| |
| i 4
| |
| | |
| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 74
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: General Purpose Dry Type MANUFACTURER: Square D Co. MODEL #: " Watchdog"
| |
| : (1) Transformers
| |
| ! RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 5.6X105 RAD 1.11X108 RAD i
| |
| 1 QUALIFICATION REPORT: CNM-1308,03-16 l
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| METHOD: lest/ Analysis REPLACEMENT INTERVAL: N/A EPSS i
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| O O O
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| . CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 75' SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Motor Control Centers MANUFACTURER: Nelson Electric Co. MODEL #: 1035U (1) ,
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| i RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 7.3X103 RAD 2X10sRAD l
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| l QUALIFICATION REPORT: CNM-1314.01-268 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 76 SU MARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMEilT ID: 4160 Volt Metal Clad MANUFACTURER: Brown-Boveri Electric MODEL #: 5HK250 (1) Switchgear RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 7.3X103 RAD 1X10sRAD QUALIFICATION REPORT: CNM-1312.02-81 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 77 SU MARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 4160/600 Volt Load Center MANUFACTURER: Westinghouse MODEL #: ASL l (1) Transformers RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED l (TID) (2) (TID) 7.3X103 RAD 1X104 RAD l QUALIFICATION REPORT: CNM-1312.06-57 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
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| O O O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 78 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 600 Velt Load Centers MANUFACTURER: Brown-Boveri Electric MODEL #: K1600S, K2000S (1)
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| RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 7.3X103 RAD 1X105 RAD QUALIFICATION REPORT: CNM-1312.06-58 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
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| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 79 SU M ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: 125VDC and 120VAC Power MANUFACTURER: Nelson Electric Co. MODEL #: 1035U (1) Panelboards RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED ,
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| (TID) (2) (TID) 4.1X104 RAD 1X105 RAD l
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| l QUALIFICATION REPORT: CNM-1314.01-268 METHOD: Test / Analysis REPLACEMENT INTERVAL: N/A EPSS
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| i; CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 80 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT
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| ; EQUIPMENT ID: 125VDC and 120VAC MANUFACTURER: Nelson Electric Co. MODEL #: 1035U 1 (1) Distribution Centers i
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| i RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) j 7.3X103RA,0 1X10 5RAD l
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| 1 1
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| j QUALIFICATION REPORT: CNM-1314.01-268 l
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| I METHOD: Test / Analysis 1
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| ; REPLACEMENT INTERVAL: N/A EPSS
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| Page RN-1 Rev. 1
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| . CATAWBA NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCAiED OUTSIDE CONTAINMENT AND EXPOSED TO POST-LOCa RECIRCULATION RADIATION ENVIRONMENT Note 1 Class 1E equipment that is exposed to the post-LOCA recirculation radiation environment has been evaluated for proper radiation qualification and is included in this table if it is exposed to a total integrated dose equal to or greater than 1X103 RAD. A total integrated dose (i.e., forty year normal plus one year accident dose) of less than 1X103 RAD is considered negligible since no materials have been identified at Catawba that exhibit a significant
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| , using mechanism when exposed to less than 1X103 RAD.
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| Note 2 The . recirculation radiation environment consists of the forty year normal -
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| operating radiation dose plus the dose received from one year of post-LOCA reactor coolant recirculation. Equipment with Replacement Interval will
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| ; experience less than the listed total Integrated Dose.
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| This attachment addresses Class 1E equipment located outside containment that is exposed to the post-LOCA recirculation radiation environment. Because this harsh radiation environment outside the containment results from an accident LOCA) inside the containment, no other accident conditions are assumed to exist O o(utside the containment. Therefore temperature, pressure, relative humidity, chemical spray and submergence outside containment are not applicable.
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| Ncte 3 The equipment listed is a NEMA 4 enclosure containing general application devices (i.e., relays, switches, terminal blocks, etc.). The qualified environment is dictated by the single limiting device contained in the
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| ; enclosure. The enclosure and device qualification is documented in calculation
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| ; CNC-1381.05-00-0054.
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| ATTACHMENT 5 DUKE POWER COMPANY POSITION j
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| i 1
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| ON THE CATEGORY II GUIDELINES OF NUREG 0588 1 ,
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| l ,
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| ; h ~ Rev. M Rev. Page Rev. -
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| T CATAWBA NUCLEAR STATION NUREG 0588 CATEGORY II DUKE POWER COMPANY
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| , GUIDELINES POSITION
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| : 1. 0 ESTABLISHMENT OF THE QUALIFICATION
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| ; PARAMETERS FOR DESIGN BASIS EVENTS 1.1 Temperature and Pressure Conditions Inside Containment -
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| Loss-of-Coolant 1.1.1- The time-dependent temperature The containment' structural design and pressure, established for the has been based-on the results of design'of the containment struc- an analysis performed by Westing-ture and found acceptable by the house employing the methodology staff,'may-be used for environ- described below. The results of
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| ; mental qualification of equip- this analysis are reported in Sec-ment. tion 6.2 of the FSAR.
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| 1.1.2 . Acceptable methods for calculat- Westinghouse employs the methodology ing and establishing the contain- described in WCAP-8312A for calculat-ment pressure and temperature ing the LOCA mass and energy release.
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| envelopes to which equipment- Appendix A to NUREG-0588 indicates s should be qualified-are summarized that this methodology is acceptable below. Acceptable methods f6r cal- to the Staff.
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| j v} - culating mass and energy release rates are summarized in Appendix A.
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| Pressurized Water Reactors (PWRs) i Ice Condenser Containment :Calcu- Westinghouse conforms to the Staff
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| {1 ate LOCA containment environment position for Ice-Condenser Plants using LOTIC or equivalent industry by employing LOTIC to calculate the codes. Additional guidance is pro- containment transient following LOCA.
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| vided.in SRP Section 6.2.1.1.B,
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| [ NUREG-75/087.
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| 1.1.3. _In lieu of using the plant-specific Plant-specific profiles are the containment temperature and pressure basis for Catawba equipment quali-design profiles for BWR and ice fication testing.
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| condenser types of plants, the gen-eric envelope shown in Appendix C may be used for qualification test-ing.
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| 1 v
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| i CATAW8A NUCLEAR STATION p
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| \d NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.1.4 The_tes't profiles included in Plant specific profiles are the basis Appendix A to IEEE Std. 323-1974 for Catawba equipment qualification should not be considered an ac- testing. It should be noted that the ceptable alternative in lieu of IEEE 323-1974, Appendix A temperature using plant-specific containment and pressure profiles envelope the temperature and pressure design worst-case Catawba containment acci-profiles unless plant specific dent temperature and pressure condi-analysis is provided to verify tions and have been used by some manu-the adequacy of those profiles. facturers for generic qualifications.
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| 1.2 Temperature and Pressure Conditions Inside Containment -
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| Main Steam Line Break (MSLB) 1.2.1 Where qualification has not Catawba is an ice-condenser contain-been completed, the environ- ment, therefore; Appendix 8 is not mental qualification should be applicable. The methodology for calculated using a plant-speci- calculating the containment temperature fic model based on the staff- and pressure conditions following a
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| , m approved assumptions discussed MSLB is described below.
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| [V ) in Item 1 of Appendix B.
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| 1.2.2 Models that are acceptable for Westinghouse employs the methodology calculating containment parameters described in WCAP 8822 for calculat-are listed in Section 1.1.2. ing the mass and energy release fol-lowing a Main Steam Line Break (MSLB).
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| At the specific request of Duke, Westinghouse has completed the mass and energy release calculations assum-ing no entrainment. Westinghouse conforms to the Staff position for Ice-Condenser Plants by employing LOTIC to calculate the containment transient following MSLB.
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| 1.2.3 In lieu of using the plant- Plant specific profiles are the specific containment temperature basis for Catawba equipment quali-and pressure design profiles for fication.
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| BWR and ice condenser plants, the generic envelope shown in Appendix C may be used.
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| n N.]
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| 2
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| . CATAWBA NUCLEAR STATION NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.2.4 The test profiles included in Plant specific profiles are the basis Appendix A to IEEE Std.'323-1974 for Catawba equipment qualification should not be considered an testing. It should be noted that the acceptable alternative in lieu of IEEE 323-1974, Appendix A temperature using plant-specific containment and pressure profiles envelop the temperature and pressure design worst-case Catawba containment accident profiles unless plant-specific temperature and pressure conditions analysis is provided to verify the and have been used by some manufacturers
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| -adequacy of those profiles, for generic qualification.
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| 1.2.5 Where qualification has been lhe environmental qualification tests completed but only LOCA condi- for equipment installed inside the tions were considered, then it containment at Catawba that is required must be demonstrated that tha to function during and following a MSLB LOCA qualification conditions envelop the maximum calculated MSLB exceed or are equivalent to the conditions.
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| maximum calculated MSLB conditions.
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| : 1. 3 Effects of Chemical Spray 1
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| 1.3.1 The effects of caustic spray' Chemical spray is included in quali-(' ') should be addressed for the fication tests for equipment located equipment qualification. The inside the containment provided the concentration of caustics used equipment is required to operate in for qualification should be the spray environment. The chemical equivalent to or more severe composition of the spray used during than those used in the plant testing is equivalent to or more severe containment spray system. than in the plant containment spray system.
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| 1.3.2 If the chemical composition of In the Catawba containment spray the caustic spray can be affected system, no single failure can occur by equipment malfunctions, the that will result in a more severe most severe caustic spray environ- spray solution composition than the ment that results from a single anticipated composition.
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| failure in the spray system should be assumed. See SRP Section 6.5.2 (NUREG-75/087), Paragraph II, Item (e) for caustic spray solution guidelines.
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| j' 3
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| CATAWBA NUCLEAR STATION
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| ,m.
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| 4v) NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4 Radiation Conditions Inside and Outside Containment The radiation environment for The calculated radiation environ-qualification of equipment should ment is based on the 40 year normal be based on the normally expected operating dose pias the appropriate radiation environment over the DBA dose.
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| equipment qualified life, plus that associated with the most severe design basis accident (DBA) dur-ing or following which that equip-ment must remain functional. It should be assumed that the DBA-related environmental conditions occur at the end of the equipment qualified life.
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| The sample calculations in Appen-dix 0 and the following positions p provide an acceptable approach Q for establishing radiation limits for qualification. Additional i radiation margins identified in Section 6.3.1.5 of IEEE Std.
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| 323-1974 for qualification type testing are not required if these methods are used.
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| 1.4.1 The source term to be used in The radiation environments through-I determining the radiation environ- cut the station following a DBA ment associated with the design LOCA are determined assuming instan-basis LOCA should be taken as an taneous release from the fuel to the instantaneous release from the fuel containment of 100% of the noble gas to the atmosphere of 100 percent inventory, 50% of the core iodine in-of the noble gases, 50 percent of ventory, and 1% of the remaining core the iodines, and 1 percent of the fission product inventory. This source remaining fission products. For term is used to derive radiation levels all other non-LOCA design basis for all equipment requiring radiation accident conditions, a source term qualification. The release fractions involving an instantaneuus release are consistent with TID-14844 and
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| .from the fuel to the atmosphere of NUREG 0578, Item 2.1.6b.
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| 10 percent of the noble gases (ex-cept Kr-85 for which a release of 30 percent should be assumed) and 10 percent of the iodines is p acceptable.
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| E
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| CATAWBA NUCLEAR STATION p
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| NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4.2 The calculation of the radiation All radioactivity released initially environment associated with de- remains within the containment. For sign basis accidents should take conservatism, airborne radioactivity into account the time-dependent is assumed to be homogeneously dis-transport of released fission tributed throughout the containment products within various regions at the initiation of the accident.
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| of containment and auxiliary Recirculation of water from the structures. containment sump is assumed to begin at 10 minutes into the accident.
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| Prior to initiation of recirculation, normal radiation environments are assumed to exist throughout the station outside containment and the annulus. The time-dependent transport mechanisms considered are consistent with NUREG 0578, Item 2.1.6b.
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| 1.4.3 The initial distribution of acti- See the response to 1.4.2 above.
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| vity within the containment should be based on a mechanistically ra-l l
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| p]
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| tional assumption. Hence, for com-partmented containments, such as in a BWR, a large portion of the source should be assumed to be initially contained in the drywell.
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| The assumption of uniform distri-bution of activity throughout the containment at time zero is not appropriate.
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| 1.4.4 Effects of ESF systems, such as To increase the conservatism of the l containment sprays and contain- calculated radiation values, no credit ment ventilation and filtration is taken for removal process such as systems, which act to remove air- containment spray, filters, or natural l borne activity and redistribute deposition. The only removal mechanism activity within containment, should considered is radioactive decay.
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| , be calculated using the same as-f sumptions used in the calculation of offsite dose. See SRP Section 15.6.5 (NUREG-75/087) and the re-lated sections referenced in the Appendices to that section.
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| CATAWBA NUCLEAR STATION 3
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| (J- 1 NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4.5 Natural deposition (i.e., plate- The assumption of an instantaneous out) of airborne activity should plate-out of 50% of the iodine released be determined using a mechanistic from the core is not used. As stated model and best estimates for the above, natural deposition is not used model parameters. The assumption in the development of post-LOCA ra-of 50 percent instantaneous plate- diation levels.
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| out of the iodine released from the core should not be made. Re-moval of iodine from surfaces by steam condensate flow or washoff by the containment spray may be assumed if such effects can be justified and quantified by anal-ysis or experiment.
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| 1.4.6 For unshielded equipment located The gamma dose in containment is that in the containment, the gamma dose dose calculated at the centerpoint of and dose rate should be equal to the containment. Shielding effects are the dose and dose rate at the considered for equipment located out-m centerpoint of the containment side the crane wall and in the accumu-plus the contribution from loca- lator rooms.
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| IC)' tion dependent sources such as the sump water and plate-out, un-less it can be shown by analyses that location and shielding of the equipment reduces the dose and dose rate.
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| 1.4.7 For unshielded equipment, the beta Beta dose calculations are consistent doses at the surface of the equip- with the gamma dose calculations as ment should be the sum of the air- discussed above. Also see the response borne and plate-out sources. The to 1.4.8 below.
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| airborne beta dose should be taken as the beta dose calculated for a point at the containment center.
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| 1.4.8 Shielded components need be All Class 1E equipment located in-qualified only to the gamma radi- side containment that is required to ation level required, provided mitigate a LOCA, MSLB, or HELB in-an analysis or test shows that side the containment has sufficient the sensitive portions of the shielding to prevent the exposure of n
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| (J) 6
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| * CATAWBA NUCLEAR STATION NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4.8 (Continued) (Continued) component or equipment are not ex- any organic materials associated posed to beta radiation or that with this equipment to a beta ra-the effects of beta radiation diation environment.
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| heating and ionization have no deleterious effects on component performance.
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| 1.4.9 Cables arranged in cable trays See the respense to 1.4.8 above.
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| in the containment should be as- Additionally, armored cables are used sumed to be exposed to half the in safety-related applications inside beta radiation dose calculated containment at Catawba; therefore, for a point at the center of the beta radiation effects on cable insula-containment plus the gamma ray tion is considered negligible.
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| dose calculated in accordance with Section 1.4(6). This reduction in beta dose is allowed becau e of the localized shielding by other cables plus the cable tray itself.
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| pl
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| \
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| V 1.4.10 Paints and coatings should be See the response to 1.4.6 and 1.4.7 assumed to be exposed to both beta above.
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| and gamma rays in assessing their resistance to radiation. Plate-out activity should be assumed to remain on the equipment surface unless the effects of the removal mechanisms, such as spray wash-off or steam condensate flow, can be justified and quantified by analysis or experiment.
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| 1.4.11 ' Components of the Emergency Radiation levels outside containment Core Cooling System (ECCS) lo- following a design basis LOCA are cated outside contain' ment (e.g., based on the release fractions dis-pumps, valves, seals, and elec- cussed in 1.4.1 above. This released trical equipment) should be quali- activity is assumed to be retained fied to withstand the radiation in and diluted by water from safety
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| CATAWBA .1UCLEAR STATION s NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES- POSITION 1.4.11 (Continued) (Continued) equivalent to that penetrating injection and ice bed melt. Where the containment, plus the exposure appropriate, radiation penetrating from the. sump fluid using assump- the containment is included. This
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| -tions consistent with the require- analysis is consistent with that re-ments statec in Appendix K to 10 quired by.NUREG 0578, Item 2.1.6b.
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| CFR Part.50.
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| 1.4.12 ~ Equipment that may be exposed to Class 1E equipment that is exposed radiation doses below 104 rads to a-radiation environment is evalu-should not be considered to be ated for proper radiation qualifica-exempt from radiation qualifi- tion.
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| cation, unless analysis supported by test data is provided to verify that these levels will not degrade the operability of the equipment
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| :below acceptable values.
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| -1.4.13 The Staff will accept a given The calculated radiation environ-p)'
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| i
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| (
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| component to be qualified pro- ments for Catawba are comparable vided it can.be shown that the to those values presented in component has-been qualified to Appendix D.
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| integrated beta and gamma doses
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| .which are equal to or higher than
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| , those'. levels resulting from an .
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| analysis similar in nature and scope l
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| < to that included in Appendix D f
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| ; '(which uses the source term given l
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| in item-(1).above), and that the l component incorporates appropriate factors pertinent to the plant design and operating characteristics, l- as given in'these general guidelines.
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| 1.4.14 When a conservative analysis has See the response to 1.4.13 above.
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| not been provided by the applicant . Additionally, detailed radiation -
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| a~~
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| for staff review, the staff will calculations are available for-
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| .use the radiation environment guide review at Duke Power Company. A I' Ulines contained in Appendix D, suit . brief summary of the-radiation l ably corrected for-the differences in calculation including a sample
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| . reactor power level, type, contain-
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| ~
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| l calculation is provided as an L
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| '~
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| ment size,'and other appropriate appendix to the position.
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| factors. .
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| .n
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| . 8
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| , - . i.. . _ , , . _ . _ _ . - , _ . _ _ . _ , _ . _ . - , _ _ _ . _ . _ _ _.-.
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| CATAWBA NUCLEAR STATION v NUREG 0588 CATEGORY II
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| ~
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| DUKE POWER COMPANY GUIDELINES POSITION 1.5 Environmental Conditions For Out-
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| -Side Containment
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| ;1.5.1 ~ Equipment-located outside con- Equipment located outside the con-tainment that could be subjected to tainment that could be subjected to high-energy pipe breaks should be a postulated pipe break environment
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| -qualified-to the' conditions result- and that is required to either miti-ing from the accident for the dur- gate the break or bring the unit to ation required. The techniques a safe shutdown condition is qualified to calculate the environmental for the pipe break environment.
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| . parameters described in Sections
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| ' 1.1 through'1.4 (Category 10 above The methods employed to evaluate pipe should be applied. breaks and to determine the resulting environmental parameters are discussed in the Catawba FSAR, Section 3.6.
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| 1.'5.2L Equipment located in general. Equipment located in-general plant
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| ' plant areas outside containment areas outside containment and not where~ equipment is not subjected exposed to a DBA environment is
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| :to a design basis accident envi- considered to be in a mild environ-g . ronment should be-qualified to ment. The equipment in this area is the normal and abnormal range of designed and/or qualified for the environmental conditions postu- environmental conditions postulated lated to occur at the equipment to occur at the equipment location
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| ~ location. as derived from the plant environ-mental design basis.
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| 11,5.3 Same-as Category I; or, there - General plant areas outside contain-may be designs where a loss of the ment not exposed to a DBA environ-environmental support' system may ment is considered a mild environment expose some equipment to environ- area. Equipment located in these ments that exceed the qualified areas is selected and applied con-limits. For.these designs,-appro- sistent with the plant environmental priate' monitoring devices should design basis. See the response to be provided to'. alert the operator item 1.5.2.
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| -that abnormal conditions exist and to permit an assessment of the con-
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| -ditions that~ occurred in order to determine if corrective action, such as replacing any affected equipment, is warranted.
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| O 9
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| CATAWBA NUCLEAR STATION
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| C'j NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION
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| ' 2. 0 . QUALIFICATION METHODS 2.1 Selection'of Methods 2.1.1 Qualification methods should a. For equipment required to perform conform to the requirements de- a safety function in a postulated fined in IEEE Std. 323-1971. LOCA, MSLB, pipe rupture, or post-LOCA recirculation radiation environment, the environmental quali1ication methods meet the intent of IEEE 323-1971 requirements,
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| : b. For the equipment not regt 'ed to operate in a harsh accident environment, environmental testing per IEEE 323-1971 was not required. Rather, the equipment was designed and p) g analyzed to assure that it maintains its required perfor-mance capability for the environmental conditions postu-lated to occur at the equipment location as derived from the environmental design basis.
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| In general, factory performance /
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| functional testing at ambient conditions is completed on equipment prior to shipping and, for some items of equipment, a production unit may be tested at the specified maximum ambient temperature. These production tests together with the desig' specification for the equipment, which specifies the environmental design parameters, and engineer-ing analysis, provides sufficient assurance of equipment capability in accordance with the Staff position under Item 2.1.4.
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| 2.1.2 The choice of the methods selected For equipment located inside con-is'largely a matter of technical tainment that is required to perform
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| .(N
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| () judgement and~ availability of in-formation that supports the a safety function in a pt.,tulated LOCA, MSLB, or HELB environment, 10
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| 'f
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| 'd ;
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| .{
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| y -
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| CATAWBA NUCLEAR STATION
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| .NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.1.2' (Continued) (Continued) conclusions reached., Experience environmental qualification is has shownLthat. qualification.of in general by testing.
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| ' equipment subjected to an accident '
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| _ enviroment without' test data is not. For equipment located outside
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| ~
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| adequate to demonstrate functional containment that is required to operability. In general', the staff . perform a safety function in a will not_ accept analysis in lieu of postulated pip'e rupture or post-
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| : test data unless (a) testing of the LOCA recirculation radiation environ-component is impractical due to ment, qualification is in general
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| . size : limitations, and (b) partial by testing, analysis, manufacturer's
| |
| -type test data is provided to sup- specific design, and/or combinations
| |
| . port theLanalytical assumptions of these methods.
| |
| and conclusions reached.
| |
| The specific qualification method for each equipment type is identified in the equipment tables.
| |
| 2.(1. 3 ' -The environmental qualificat. ion of
| |
| -s equipment exposed to DBA environ-M- 'ments;should conform to the follow-ing positions:
| |
| ~
| |
| .The basis should be provided for The required duration of operability the time interval. required for is based on assumptions in the FSAR
| |
| : operability of this' equipment. ~
| |
| ~ accident analysis, system requirements, and/or the time the' environment is expected to remain outside its normal range following a DBA.
| |
| The required and demonstrated duration of the safety function for equipment subject to'a LOCA, MSLB, pipe rupture, or post-LOCA recirculation radiation environment is identified in the equipment. tables.
| |
| -The. operability and failure cri- The primary purpose of equipment quali-
| |
| , -teria should'be specified and the. fication is to reduce the potential safety margins defined.
| |
| ~
| |
| for common mode failures due to postu-1ated environmental conditions.
| |
| Equipment will therefore be con-sidered to have failed the test and/or analysis if the functional require-
| |
| , ments cannot be met ~, unless an 11
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| CATAWBA NUCLEAR STATION
| |
| '(3
| |
| 'd NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.1.3 (Continued) (Continued) investigation can establish that the failure mechanism is not of common-mode origin or that plant specific analyses can demonstrate that the reduced capability is acceptable.
| |
| In certain cases, failure criteria, per se, was not specified prior to qualification testing; however, the failure of the equipment would have been an obvious failure (i.e.,
| |
| equipment would not function).
| |
| Margin is discussed in Section 3.0.
| |
| 2.1.3a Equipment that must function in Equipment that must perform a order to mitigate any accident safety function in a LOCA, MSLB, fm should be qualified by test to pipe rupture, or post-LOCA recircu-(') demonstrate its operability for the time required in the environ-lation radiation environruent, is qualified by test and/or analysis.
| |
| mental conditions resulting from The acceptance criteria for the test that accident. and/or analysis is that the safety-related function must be demonstrated for the specified duration of opera-bility in the postulated accident environment.
| |
| 2.1.3b Any equipment (safety-related In general, the failure of safety-or non-safety-related) that need related equipment that is not re-not function in order to mitigate quired to perform a safety function -
| |
| any accident, but that must not in a postulated harsh accident envi-fail in a manner detrimental to ronment is not detrimental to plant plant safety should be qualified safety.
| |
| by test to demonstrate its capa-bility to withstand any accident The effects and consequences of environment for the time during adverse environments on non-safety which it'must not fail. related equipment has been identified as a Category I item under NUREG-0585 "TMI-2 Lessons Learned Task Force Final Report" and will be resolved as part of the action plan set up to address Recommendation #9. Addition-ally, the subject of non safety-OC/
| |
| related control systems was addressed in IE Information Notice 79-22.
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| 12
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| CATAWBA NUCLEAR STATION
| |
| ()
| |
| V NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.1.3c Equipment that need not function Where an item of safety-related equip-in order to mitigate any accident ment is located in an area such that and whose failure in,any mode in it may be exposed to a LOCA, MSLB, any accident environment is not pipe rupture, or post-LOCA recircula-detrimental to plant safety need tion radiation environment but is only be qualified for its non- not required to perform any safety-accident service environment. function as a result of the breaks, the failure of such equipment, due Although actual type testing is to the adverse environment, has been preferred, other methods when determined not to prejudice the safety justified may be found acceptable. functions of other equipment claimed The bases should be provided for in the accident analysis.
| |
| concluding that such equipment is not required to function in order to mitigate any accident, and that its failure in any mode in any accident environment is not detri-mental to plant safety.
| |
| fs 2.1.4 For environmental qualification of As stated in the response to Item i') equipment subject to events other 2.1.lb, the design specification re-than a DBA, which result in abnor- quirements for equipment not required mal environmental conditions, act- to function in a harsh environment ual type testing is preferred. together with factory performance /
| |
| However, analysis or operating functional tests and engineering history, or any applicable com- analyses (including some cases.where bination thereof, coupled with the testing is performed at maximum partial type test data may be ambient conditions) provide the re-found acceptable, subject to the quisite assurance for equipment ca-applicability and detail of in- pability, formation provided.
| |
| 2.2 Qualification by Test 2.2.1 The failure criteria should be The response to Item 2.1.3 is appli-established prior to testing. cable for equipment required to operate in a LOCA, MSLB, pipe rupture, or post-LOCA recirculation radiation environment.
| |
| 2.2.2 Test results should demonstrate As stated in Item 2.1.la environmental that the equipment can perform its qualification demonstrates the capa-required function for all service bility of equipment to perform safety-conditions postulated (with margin) related functions when subject to the during its installed life. consequential adverse environment of A LOCA, MSLB, pipe rupture, or post-LOCA recirculation radiation. For 13
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| CATAWBA NUCLEAR STATION
| |
| /*
| |
| NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION (Continued) (Continued) equipment not required to operate in a harsh environment, the response to Item 2.1.lb applies.
| |
| The requirement to demonstrate this capability duririg the installed life implies an addressment of aging.
| |
| This subject is discussed under Item 4. The subject of margin is discussed under Item 3.
| |
| 2.2.3 The items described in Section 5.2 In general, the qualification of IEEE Std. 323-1971 supplemented testing of safety-related equipment by items (4) through (12) below at Catawba conforms to the guidelines constitute acceptable guidelines of IEEE-323-1971.
| |
| for establishing test procedures.
| |
| i e 2.2.4 When establishing the simulated In general a single profile, envelop-
| |
| ' {-
| |
| environmental profile for quali-
| |
| ..fying equipment located inside ing both MSLB and LOCA, is used for qualification of equipment located l containment, it is preferred that inside containment which is required a single profile be~used that enve- to perform a safety function to miti-lopes the environmental conditions gate a LOCA or MSLB. The exceptions resulting from any design basis to the use of a single qualification event during any mode of plant envelope for LOCA and MSLB are, in operation (e.g., a profile that general, when:
| |
| envelopes the conditions produced by the main steamline break and a. A component is only required loss-of-coolant accidents), to mitigate against either the LOCA or MSLB. In such a case, j qualification has been completed
| |
| !. to conditions enveloping the possible consequences inside containment from the single event and additionally, it is verified that failure of the l component in any other more limit-ing environment will not prejudice any safety-related function.
| |
| t b. The resulting test conditions l would unjustifiably exceed accept-
| |
| ! able conservatism.
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| D o
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| 14
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| CATAWBA NUCLEAR STATION
| |
| (
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| V NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.2.5 Equipment should be located above In general, safety-related equipment flood level or protected against is located above the maximum postu-submergence by locating the equip- lated flood level. The exceptions ment in qualified watertight en- to this design philosophy are certain closures. Where equipment is instruments, electric valve operators, located in watertight enclosures,
| |
| ~
| |
| limit switches and cables located qualification by test or analysis inside containment. A consequence should be used to demonstrate the analysis of the submergence of this adequacy of protection. Where equipment is provided in response to equipment could be submerged, it FSAR question 440.48.
| |
| should be identified and demon-strated to be qualified by test Additionally, safety-related equipment for the duration required. located outside containment has been evaluated for the effects of flooding.
| |
| 2.2.6 The temperature to which equipment In performing qualification tests for is qualified, when exposed to the equipment exposed to a LOCA, MSLB, or simulated accident environment, pipe rupture environment, the external should be defined by thermocouple environment temperature is measured readings on or as close as prac- as close to the equipment surface as
| |
| -( p) tical to the surface of the compo- practicable.
| |
| '' nent being qualified.
| |
| If there were no thermocouples located near the equipment during the tests, heat transfer analysis should be used to determine the temperature at the component.
| |
| (Acceptable heat transfer analysis methods are provided in Appendix B.)
| |
| 2.2.7 Performance characteristics of Where the safety-related function of equipment should be verified the equipment requires operation in before, after, and periodically the LOCA, MSLB, pipe rupture, or during testing throughout its post-LOCA recirculation radiation range of required operability. environment, the' equipment performance before, during (where practical) and after exposure to the simulated event is verified.
| |
| 2.2.8 Caustic spray should be incor- The response to Item 1.3.1 is appli-porated during simulated event cable for equipment located inside testing at the maximum pressure containment and qualified by test and at the temperature conditions to operate in the LOCA or MSLB that would occur when the onsite environment.
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| spray systems actuate.
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| o 15 l
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| )
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| | |
| L CATAWBA NUCLEAR STATION
| |
| 't
| |
| \ NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.2.9 The operability status of equipment The response to Item 2.2.7 is appli-should be monitored continuously cable, during testing. For long-term testing, however, monitoring at discrete intervals should be justi-
| |
| 'fied-if used.
| |
| .2.2.10 Expected extremes in power supply Class 1E equipment is supplied t>y voltage range and frequency should guaranteed stabilized power supplies.
| |
| be applied during simulated event As a consequence, the range of the environmental testing. electrical parameters is considered to be within equipment capability.
| |
| a4
| |
| -2.2.11 Dust environments.should be Duke has implemented housekeeping pro-addressed when establishing quali- cedures to preclude adverse dust con-fication service conditions, ditions at Catawba. Therefore, dust environments are not considered as a qualification parameter.
| |
| p 2.2.12 Cobalt-60'is an acceptable ga'mma In general, Cobalt-60 sources are Q- - radiation source for environmental qualification.
| |
| used to simulate the effects of gamma radiation for equipment qualified by.
| |
| test to operate in a LOCA/MSLB or post-LOCA recirculation radiation environment.
| |
| 2.3 Test Sequence -
| |
| 2.3.1 Justification'of the adequacy of. In general, when testing is used to the test-sequence selected should qualify equipment required to perform
| |
| .be provided.
| |
| a safety function in a LOCA, MSLB, or pipe rupture environment, the follow-ing test sequence is employed:
| |
| : 1. The equipment is subjected to a calibration and/or veri-fication test at ambient con-ditions. This test included verification of safety related functions.
| |
| : 2. No specific abnormal tests are required since the accident environment envelops the ab-normal condition with margin.
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| a~
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| 16
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| CATAWBA NUCLEAR STATION A
| |
| NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.3.1 (Continued) (Continued)
| |
| : 3. The equipment is irradiated, using a Cobalt-60 source, to the estimated worst case gamma dose obtained from in-service operation and required accident..
| |
| and post accident performance.
| |
| : 4. The same equipment is tested to verify equipment capability during a simulated seismic event.
| |
| : 5. The same equipment is tested under applicable simulated accident and post-accident conditions.
| |
| Completion of the above test sequence (O) '
| |
| gives assurance that the equipment can perform safety-related functions under normal, abnormal and design basis event conditions. The design basis event testing applies extremes of radiation, vibration (seismic), temp-erature, humidity, and chemical spray in a conservative sequence and verifies that the equipment being qualified is not marginal with respect to these parameters. The subject of margin and aging are discussed under Items 3 and 4, respectively.
| |
| 2.3.2 The test should simulate as For equipment that is qualified by closely as practicable the postu- testing, the test environment simulates lated environment. as closely as practicable the postulated environment.
| |
| 2.3.3 The test procedures should in general, the qualification testing conform to the guidelines des- of safety-related equipment at Catawba cribed in Section 5 of IEEE Std. conforms to the guidelines of IEEE 323-323-1971. 1971.
| |
| [~N L) 17
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| CATAWBA NUCLEAR STATION
| |
| -NUREG 0588 CATEGORY II' DUKE POWER COMPANY GUIDEl.INES POSITION 2.3.4 The staff considers that,'for- For equipment which is qualified by vital electrical equipment such testing and which is required to per-as penetrations, connectors,. form a safety fonction in a LOCA, MSLB, cables, valves and motors, and or Pipe Rupture environment, the transmitters located inside con- test sequence identified in the Etainment~or exposed to hostile response to Item 2.3.1 is generally steam environments outside con- employed and as a consequence does
| |
| .tainment, separate effects test- -not, in general, employ separate ing for the most part is not an effects testing. Separate effects acceptable qualification method. testing, if used, is justified.
| |
| The testing of such equipment should be conducted in a manner that subjects the same piece of equipment to radiation and the hostile steam environment sequentially.
| |
| 2.4 Other Qualification Methods
| |
| .i G /-
| |
| Qualification by analysis or operating experience-implemented,-
| |
| ' Duke does not necessarily rely on operating experience to estab!ish as described in IEEE Std. 323-1911 the qualification of safety related
| |
| :and other ancillary standards, may equipment, rather, operating experience be found acceptable. The adequacy- may be included in support of quali-of these methods wil1~be evaluated fication by test and/or analysis. The on the basis of-the quality and equipment tables identify the qualifi-detail of the information submit- cation methodology employed for each ted in support of the assumptions item of safety-related equipment.
| |
| made and specific function and location of the equipment. These methods.are most suitable for. equip-ment'where testing is precluded by physical size of the equipment being
| |
| . qualified. . It:is required that, when these methods are employed, some partial type tests on vital compo-nents of the equipment be provided in support of.these methods.
| |
| 3.0 --MARGINS-3.1- . Quantified margins should be For most plant specific applications, applied.to the design parameters- margins are available between the qual-discussed in Section.1 to assure ification parameters and the plant that.the postulated accident con- specific requirements.
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| ditions have been enveloped during 18 I
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| o
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| ' CATAWBA NUCLEAR STATION
| |
| .p NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES- POSITION 3.17 (Continued) (Continued)
| |
| . .. testi ng. .These margins should be Margins are'as shown in the equipment-applied in addition to any margins tables.
| |
| (conservatism) applied during the .
| |
| derivation of the specified. plant-parameters.
| |
| 3.2 ^The margins provided in the design Same as_3.1
| |
| _w ill be evaluated on'a case-by case basis. Factors that should be considered in quantifying margins are (a) the environmental stress levels induced during testing, (b) the duration of the stress, (c) the number of items tested and
| |
| -the number of tests performed in the hostile environment, (d) the i
| |
| performance characteristics of A the. equipment. while subjected to A}
| |
| l the environmental-stresses, and (e) the specified function of the_ equipment.
| |
| 3.3 When1the qualification envelope in This generic envelope is not speci-Appendix C is used, the only fically employed by Westinghouse or required margins are those account- Duke for qualification testing. -It ing for the inaccuracies in the should be noted that a given manu-test equipment. Sufficient' con- facturer's test curve-may approximate servatism has already been included this generic curve.
| |
| to account ~ for uncertainties such' as production errors and errors L - associated with defining satis-Lfactory performance (e.g., when only a small number of units are
| |
| : tested).
| |
| .3.4a' .Some equipment may be required by In general, equipment required to oper-
| |
| .the: design to only perform its ate in a harsh accident environment is safety function within a short time qualified to perform its safety function
| |
| . period into the event (i.e., within for a period in excess of the calcu-seconds or minutes), and,-'once its lated worst case time to perform the function is complete, subsequent safety functions as derived from the failures are shown not to be detri- . accident analysis. The arbitrary ad-mental to plant safety. Other ditional one hour. time requirement has p equipment may not be required to. not been applied to all equipment. The Q'
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| .19
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| CATAWBA NUCLEAR STATION j%
| |
| NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 3.4a (Continued) (Continued) perform a safety function but must time margins indicated in the equipment not' fail.within a short time period tables are considered acceptable.
| |
| into the event, and subsequent failures are also shown not to be detrimental to plant safety.
| |
| Equipment in these categories is required to remain functional in the accident environment for a period of at least 1 hour in excess of the time assumed in the accident analysis.
| |
| 3.4b For all other equipment (e.g., In qualifying equipment required to post-accident monitoring, recom- operate in a LOCA, MSLB, pipe rupture, biners, etc.), the 10 percent or post-LOCA recirculation radiation time margin identified in Section environment, margin is included in 6.3.1.5 of IEEE Std. 323-1974 may qualification testing by selecting
| |
| ('' be used. conservative qualification parameters i and/or test sequences.
| |
| Some of the areas where margin is usually implicit in a test sequence is as follows:
| |
| : 1. The full radiation dose, simulat-ing effects of in-service and acci-dent radiation doses, is applied in a single step prior to seismic and LOCA/HELB test simulations.
| |
| : 2. The seismic event simulation applies significant mechanical stress to the equipment prior to the LOCA/HELB simulation.
| |
| : 3. The single envelope normally employed for HELB simulation, not only encompasses the effects of LOCA and MSLB accidents, but a whole spectrum of break sizes and locations within these accident definitions. As a consequence, the envelope
| |
| :(9 employed invariably contains sig-
| |
| 'b' nificant margin with respect to 20 t'
| |
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| L CATAWBA NUCLEAR STATION
| |
| [
| |
| V NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 3.4b (Continued) (Continued) the transient for any single break size and location.
| |
| : 4. The single HELB simulation normally employed combines the high irradiation dose associ-ated with the LOCA with the high temperature associated with the MSLB.
| |
| 4.0 AGING 4.1 Qualification programs that are Safety-related valve operators (motor committed to conform to the and solenoid) located inside contain-requirements of IEEE Std. 382-1972 ment and continuous duty motors located (for valve operators) and IEEE Std. inside containment have been mechanic-334-1971 (for motors) should con- ally, thermally, and radiation aged in p)
| |
| (
| |
| C' sider the effects of aging. ~ For this equipment, the Category I accordance with IEEE 382-1972 and 334-1971, respectively.
| |
| positions of Section 4 are appli-cable.
| |
| 4.2 For other equipment, the qualifi- Addressment of aging was not a require-cation programs should address raent in qualification programs.for aging only to the extent that Category II equipment. However, with equipment that is composed, in the wealth of in-service experience part, of materials susceptible to covering a variety of equipment types, aging effects should be identified, no significant in-service aging mech-and a schedule for periodically anisms have been identified which replacing the equipment and/or could prejudice the qualification materials should be established. tests performed on new equipment During individual case reviews, the within a few years from start-up.
| |
| staff will require that the effects of aging be accounted for on selec- Inservice degradation is addressed ted equipment if operating experi- through preventative maintenance ence or testing indicates that the and surveillance programs with equip-equipment may exhibit deleterious ment and component refurbishment aging mechanisms. and/or replacement based on known susceptibility to aging degradation.
| |
| These programs are based on test results manufacturer's recommendations, operating experience, and/or sound engineering practices. Additionally, p- Duke will also evaluate and incorporate
| |
| (
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| 21
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| CATAWBA NUCLEAR STATION O
| |
| i 4 V NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 4.2 (Continued) (Continued) into these programs, as necessary, information from EPRI research, NRC studies, NPRDS information, IE Bulletins and industry research and testing.
| |
| . 5.0 (UALIFICATION DOCUMENTATION 5.1 The Staff endorses the require- Duke Power Company will arrange and ments stated in IEEE Std. 323- maintain in an auditable form suffi-1974 that, "The qualification cient qualification documentation documentation shall verify that that will support the qualification each type of electrical equip- that is required for each type of ment is qualified for its appli- safety-related electrical equipment.
| |
| cation and meets its specified performance requirements. The
| |
| . basis of qualification shall be L -3 j explained to show the relation-
| |
| ! ship cf all facets of proof needed V to support adequacy of the complete equipment."
| |
| i
| |
| " Data used to demonstrate the qualification of the equipment shall be' pertinent to the appli-cation and organized in an audit-able form."
| |
| l 5.2 The guidelines for documentation The qualification test reports in IEEE Std. 323-1971 are ac- referenced in the equipment tables l ceptable. The-documentation for equipment qualified to operate in should include sufficient infor- an accident environment, in general, mation to address the required meet the requirements of Section 5 information identified in Ap- to IEEE 323-1971 by providing certain pendix E. A certificate of con- essential information. For example:
| |
| formance by itself is not accept-l able unless it is accompanied -
| |
| safety-related functional require-by test data and information on ments to be demonstrated the qualification program.
| |
| range of applicable environmental parameters to be considered i
| |
| ,p -
| |
| identification of the test unit O
| |
| 22
| |
| | |
| [
| |
| s CATAWBA NUCLEAR STATION 0- NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION
| |
| : 5. 2 (Continued) (Continued) description of the test facility and monitoring instrumentation description of test unit mounting and interfaces summary of the test procedures summary of the test results O
| |
| O 23
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| y
| |
| ? *
| |
| * t* CATAWBA NUCLEAR STATION Calculational Methodology For Equipment Qualification Radiation Dose r)
| |
| T This report illustrates the model for calculating dose rates and integrated doses for equipment qualification purposes. Infomation pertaining to releases of radioisotopes are from NUREG 0588 and NUREG 0737. The Core isotopic inventory is calculated using the ORIGEN computer code for maximum equilibrium.concen-trations at maximum fuel burnup. See Table 1 for the list of major radioisotopes important to radiation dose.
| |
| .I. Containment 2 I. a. Gamma Dose Inside Containment
| |
| - The source terms used to calculate radiation dose rates inside contain-ment are: 100% noble gases, 50% iodines and 1% remaining fission products both in the containment atmosphere and in the liquid of the containment sump. Concentrations of radioisotopes in the atmosphere and in the sump are listed in Table 1. Source Strengths and energies are included in this table. It is assumed that these fission products are instantaneously released into the containment free volume and distributed throughout upper and lower containment.
| |
| The containment is modeled as a right-circular cylinder 57.50 feet in radius, 97.5 feet in height or a free ' volume of 1.015 x 106 ft3 . For conservatism, the detector point representing equipment inside of contain-
| |
| -ment is chosen at the centerline. (r, z, 0) = 0, 48.75 feet, 00). A dose rate of 5.0 x 106 Rads / hour is calculated using the KAP-VI computer code v asst,ning no credit for decay, shielding, leakage, plateout or washout by sprays. This dose rate is determined to be the maximum value at any location within containment post-accident.
| |
| Source tems and dose rates are generated at this containment location for times following the DBA to account for radioactive decay. Dose rates are normalized to the maximum time-zero value and integrated
| |
| .using trapezoidal methodology for one year post-accident. This integration factor (23.2) times the time zero dose rate represents the one year integrated dose inside of containment (1.1 x 10e Rads). In this way,
| |
| : a. time dependent fraction of the one-year accident dose can be plotted vs. time'for equipment qualification duration lets than one year, see Figure 4, (for 30 days the integration fraction is .71or 71% of the one-year-dose = 8.3 x 107 Rads). The Reactor Building is sectioned into radiation zones to account for variations in the 40-year normal operating dose. The sum of this 40-year dose and the post-accident dose is added to give the total integrated dose to equipment. See Table 2 " Reactor Building," Example 1 and Figure 1 for radiation dose data, n
| |
| t v)
| |
| | |
| f; :.; ,
| |
| t
| |
| - (. : '
| |
| k y I.Lb. Beta Dose In-Containment A beta dose calculation was perfomed assuming an infinite unifonn
| |
| , cloud .containing concentrations equivalent to those used in Section I.a.
| |
| - above. The calculation uses -the beta dose equation 'in ~ Regulatory Guide
| |
| :1.4 with average. beta energies per isotope from ORNL/NUREG/TM-102.
| |
| The one-year. accident dose from beta radiation was calculated to be
| |
| .8.~4 x:los Rads.. Based on guidance from IE Bulletin 79-01B and NUREG-0588,970 mils' thickness of cable insulation is sufficient to reduce
| |
| .the beta dose to approximately one-tenth of the gamma dose and therefore can be considered negligible.
| |
| All Class 1E equipment located inside containment that is required to
| |
| ~m itigate a LOCA, MSLB, or HELB has sufficient shielding- to prevent the exposure of any organi.c materials associated with this equipment to a-beta radiation environment. ,
| |
| II. . Reactor Building Annulus-The! equipment located.in the annulus, i.e., between the. containment shell and Reactor Building wall, will be subjected to radiation
| |
| : exposure from the in-containment atmosphere and from containment
| |
| : leakage-into the Annulus. The source: terms for in-containment exposure are the same as Section I"above. The geometry of the source is separated Ous
| |
| .into three zones: sources inside of the cranewall, sources outside of Ethe cranewall, and sources in the containment dome. Detector points are distributed at various ~ elevations-inside of the annulus to account for.the three source geometries and credit is taken for the 3 feet thick concrete cranewall and the 1" steel containment shell shielding.
| |
| . Annulus gaseous activity is ' determined-a's in Section I above. Radio-Lisotopes are distributed.. equally throughout the annulus volume and a
| |
| . dose rate is. calculated at detector point locations vertically distri--
| |
| buted throughout'the annulus. The total integrated dose to equipment in the ~ Annulus is the sum of exposure.from in-containment activity,
| |
| ~~
| |
| gaseous activity lin the annulus and exposure from 40 years of normal operation.
| |
| :III. Auxiliary Building -
| |
| Sources of exposure in the Auxiliary Building are from recirculating
| |
| - Reactor sump liquids through- the safety injection, containment spray cand residual heat removal systems.
| |
| Fractions of. core radioisotopes in the liquid containing systems are:
| |
| ~
| |
| . 100% noble gases 50% iodines 1%-remaining fission products
| |
| ~
| |
| '(See sump concentrations at T = 0 time in Table 1) 4 i i i sg i
| |
| | |
| .e-Shielding models for piping and components for each room are developed
| |
| /G for use in the computer. codes SHIELD and KAP-VI. (See example 2).
| |
| O A nonnalized dose rate decay curve from a standard geometry model is integrated over the one-year post-accident, the sum of which gives an integrating factor to be applied to the maximum dose rate in each room to give the one-year integrated dose. Figure 4 can be used for equipment qualification times less than one year post-accident for equipment located inside of the Auxiliary Building affected by recirculating sump liquids.
| |
| IV. Areas Affected by In-Containment Radiation Streaming Outside of Containment The Catawba Reactor Building has two personnel access hatches which lack Reactor Building concrete shielding. Personnel access hatches were modeled to reflect radiation streaming exposure to areas adjacent to these " openings." Areas affected are the spent fuel pool area and the lower electrical penetration room. (See Table 4 and Figure 3 for radiation data).
| |
| V. Auxiliary Building Ventilation Sources of activity in Auxiliary Building results from the use of the Annulus Ventilation System. Due to containment leakage, and the need to maintain a negative pressure in the annulus, post-accident periodic (n) purges are necessary through the VE System filter bed. The 4" equivalent carbon bed is assumed to remove 100% of the iodine. The only method of l
| |
| removal is through decay of the isotopes of iodine.
| |
| The second source of activity results from containment bypass leakage into the Auxiliary Building through the Reactor Building concrete wall. A special computer code', BPAUX was developed.to give the Auxiliary Building Ventilation System, VA, filter bed loading as a function of i 4. time post-accident. The resultant equipment exposure is the sum of the l- effects of annulus purge and bypass leakage (SeesTable 3, el. 594 and Figure 2 for radiation dose data.)
| |
| An additional calculation was perfc.wed for a source of activity in the VA filter bed assuming leakage from ECCS components. This source was considered negligible compared to bypass leakage.
| |
| f: VI. 40-Year Normal Operation Reactor coolant design basis activities are based on operation with
| |
| ; defects in cladding resulting in a failed-fuel fraction of 1%. Credit for radioactivity removal is taken in accordance with NUREG 0017. The 40-year normal operation dose in Rads is calculated by multiplying an area dose rate in Rads per hour'by 8760 hours per year and 40 years l per lifetime of the plant.
| |
| f3 m/
| |
| | |
| CATAWBA NUCLEAR STATION Examples of Radiation Data Reported in NUREG 0588 Response
| |
| ^
| |
| l') Equipment ID: Transmitter - Pressurizer Pressure
| |
| ~
| |
| (Table 5, Lower Containment)
| |
| -Manufacturer:-Barton(NSSS)
| |
| Model #: 763 (Lot 2)
| |
| Radiation accident environment for operation time post-accident of 15 minutes. Assuming 1 hour time. duration (see Figure 4 for the fraction of the one year dose).
| |
| Read - 0.035 from Figure 4.
| |
| Next find the radiation zone in which the equipment is located (Table 5).
| |
| Read: Zone 9 Elevation 565 Next, on Table 2 find the Radiation Data.
| |
| Read: Normal Operating 1-Year LOCA-40-Year Dose (Rads) DOSE (Rads) 2.0 x 105 1.1 x 108 Next, multiply the 1-year LOCA dose by.the fraction of the one year integrated dose.
| |
| 1.1 x 108 Rads
| |
| * 0.035 = 3.85 x 106 Rads Add the 40-year normal operating dose to this value to obtain the Total Integrated Dose (TID) for_this piece of equipment:
| |
| 1 Hour Post-LOCA Dose + 40-Year Normal Operating Dose = TID 3.85 x 106 Rads ~ + 2.0 x 105 Rads = 4.05 x 106 Rads which is less than what the equipment is qualified. (from Table 5) n x<
| |
| : 2) Equipment located in the Auxiliary Building (Table 6).
| |
| Equipment ID: Auxiliary Building Filtered Exhaust Fan Motors Manufacturer: Reliance Model #: 1XF882610, 2XF882610 See Table 6 for radiation zone information and elevation.
| |
| -Read Zone 2-Elevation 594 See Table 3 for the radiation data.
| |
| Read: Nonnal Operation DBA - LOCA 40-YearDose(Rads) Dose (Rads) 8.8 x 102 1.1 x 106 This equipment is qualified for the entire 1-year post-LOCA, there-fore add.both values to get the total integrated dose.
| |
| 8.8 x 102 Rads + 1.1 x 106 Rads = 1.1 x 106 Rads which is less than what the equipment is qualified (from Table 6).
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| ALL INPUT ASSUMED IN UCI/ML . INPUT APPROIATE CONFAC = 1*10 /&Ci/Ci
| |
| * INPUT IN Ci l
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| CONTAINMENT FREE VOLUME CONFAC = :::--- 3---~~~~73---- 3-------- = JACi/cc 3.48E-5 .
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| 1.015*10 FT *(30.48) cc/FT OPERATION MODE = 1.0 (DECAY RUN) 2.0 (DEMFIL RUN) 3.0 (DEMFIL-DECAY) 4.0-(DECAY DEMFIL )
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| ? .
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| 1.
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| ARE THERE ANY CHANGES TO RE Y OR H 100% NOBLE GASES
| |
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| 50% HALOGENS 3t.5,20t.01,6t.5,21*.01,22*1. II REMAINING FISSION PRODUCTS ARE THERE ANY CHANGES TO PE? Y OR H N
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| DECAY TIME (HOURS)=
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| 0.0 SPECIFIC ACTIVITY BY ENERGY (GAMMAS /CC-SEC) (MEV) 0.0-0.3 0.3-0.7 0.7-1.2 1.2-1.7 1.7-2.4 >2.4 TOTALS 3.88E+08 6.63E+08 5.34E+08 1.75E+0B 1.75E+08 3.0,?E+07 IN-CONTAINMENT ATHOSPHERIC T=0 ENERGY 1.88E-01 5.15E-01 8.97E-01 1.39E+00 2.02E+00 2.98E+00 HOUR SOURCE TERMS P t. I t'? T All e OF CAL C'_'L ATES ICOTECPIC ACT!'.'! r!Ec' '-YE'
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| 1 DO YOU WISH TO INPUT NEW SAC VALUES? 1=YES 2=NO
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| ?
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| 2 4
| |
| 4 ALL INPUT ASSUMED IN UCI/ML . INPUT APPROIATE CONFAC =
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| * INPUT IN Ci SUMP LIQUID CONFAC =--------3------- 3---- 3------ = ACi/CC 1 3.92E-4 l
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| 90 cc/FT DPERATION MODE = 1.0 (DiCAY Rutl) 2.0 (DEHFIL RUN) 3.0(DEMFIE122FT*(30.18)
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| DECAY) 4.0 (DECAT DEMFIL )
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| , N DECAY TIME (HOURS)=
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| 0.0 SPECIFIC ACTIVITY BY ENERGY i (GANMAS/CC-SEC) (HEV) 0.0-0.3 0.3-0.7 0.7-1.2 1.2-1.7 1.7-2.4 >2.4 TOTALS 4.37E+09 7.47E+09 6.01E+09 1.97E+09 1.97E+09 3.45E+0S CONTAINMENT SUNP T=0 HOUR SOURCE TERMS ENERGY 1.8SE-01 5.15E-01 8.97E-01 1.39E+00 2.02E+00 2.98E+00
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| TABLE 2 ' - .- -
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| o REACTOR BUILDING Radiation Data r ., ,.
| |
| Normal Oper. LOCA1 I, Normal Oper. TIDr Dose Rate 40 Yr. Dose LOCA Dose 1 Yr. Dose
| |
| * Rate (R/Hr.) (Rads) ,(Rads)
| |
| Elevation Zone (R/Hr.) (Rads) 1.0E7 5.0E6 1.1E8 1.2E8 523 + 11 1 2.85El _
| |
| i 1.0E6 5.0E6 1.1E8 1.1E8 552 + 0 2 2.85 1.]ES 5.0E6 1.1E8 3 2.85E-1 2.85E-2 1.0E5 1.0E4 5.5ES 1.3E7 1.3E7 4
| |
| 5.0E6 5.0E6 1.1E8 1.1E8
| |
| ) 565 + 3 5 1.4E1 1.3E8 5.7El 2.0E7 5.0E6 1.1E8 6 1.1E8 2.85E-l 1.0E5 5.0E6 1.1E8 7 1.1E8 2.0E4 5.0E6 1.1E8
| |
| ~.
| |
| * 8 5.7E-2 ,
| |
| 1.1E8 5.7E-1 2.0E5 5.0E6 1.1E8
| |
| ? 9
| |
| ' *2.85E-2 1.0E4 6.5E5 1.5E7 1.5E7 N 10 .
| |
| l 5.0E6 ' 5.0E6 1.1E8 1.1E8 595 + 10 3/4 11 1.4E1 1.1E8 l
| |
| ' 5.7 2.0E6 5.0E6 1.1E8 12 1.1E8 1.3E8 13 5.7El 2.0E7 5.0E6 1.0E5 5.0E6 1.1E8 1.1E8 14 2.85E-1 1.1E8 l 9.99 3.5E6 5.0E6 1.1E8 i 15 1.1E8 1.1E8 16 1.4E-1 5.0E4 5.0E6 j
| |
| 2.85E-2 1.0E4 7..lE5 1.7E7 1.7E7
| |
| ! 17 3.5E6 5.0E6 1.1E8 -
| |
| 1.1E8 605 + 10 18 9.99 1.1E8 2.85E-l 1.0E5 5.0E6 1.1E8 19 '
| |
| 1.1E8 1.1E8 20 1.4E1 S.CE6 5.0E6 2.0E6 5.0E6 -
| |
| 1.1E8 1.1E8 21 5.7 1.1E8 l 5.7E-2 2.0E4 5.0E6 1.1E8
| |
| ! 22 l ,. -
| |
| | |
| l Y
| |
| " TABLE 3 -
| |
| AUXILIARY BUILDING Elevation 594 + 0 t
| |
| Radiation Data -
| |
| 1 1
| |
| j -Integrated LOCA Dose Max. LOCA Dose Rate (R/Hr) .(Rads) Normal Oper.
| |
| Sys. VA Sys. VE Sys. VA' Sys. VE2 40-Yr. 0,ose TIDS j ZONE Filters. Filters Filters Filters (Rads) (Rads) 2 2.6E3 -----
| |
| '1.1E6 -----
| |
| 8.8E2 1.1E6 l 3 -----
| |
| 1.1E6 --- ,,- .6.0E8 8.8E2 6.0E8 i 4 4.5E-2 2.1E-4 4.1E0 1.3E-1 . 8.8E2 8.8E2 1 5 3.2E-2 1.7E-4 2.8f0 1.0E-1 8.8E2 8.8E2 i ,, 6 -
| |
| 2.4E-3 6.7E-9 I.4E-1 3.4E-5 8.8E2 8.8E2 r- 7 2.2E0 9.5El 6.4E2 4.9E4 8.8E2 5.1E4 in 8 5.6E0 2.1E2 1.7E3 1.1E5 8.8E2 1.1ES
| |
| : 5) 9 2.5E0 1.7E2 7.8E2 8.7E4 8.8E2 8.9E4 i' o' 10 '2.5E0 1.7E2 7.8E2 8.7E4 8.8E2 8.9E4 11 2.1E0 9.5El 6.4E2 4.9E4 8.8E2 5.1E4 12 5.6E0 2.1E2 1.5E3 1.1E5 8.8E2 1.1E5 4 13 Refer to Elevation 577 + 0 Zone 83, Table 5.0-2 .
| |
| ; 14 7.1E0 1.6E3 2.3E3 8.1E5 8.8E2 8.1E5 15 1.3E0 2.0E4 2.8E3 1.0E7 5.2E3 1.0E7 l 16 1.0E0 1.5E4 3.2E2 8.0E6 5.2E3 8.0E6 17 4.0E1 5.9E2 1.5E4 3.0E5 8.8E2 3.2E5
| |
| ! 18 4.1E-4 4.9E-5 2.2E-2 9.9E-2 8.8E2 8.8E2 l 19 7.5E0 4.1E3 2.3E3 2.1E6 8.8E2 2.1E6 i 20 6.8E0 8.7El 2.1E3 4.5E4 8.8E2 4.8E4 ~
| |
| 5 21 5.8E0 1.7E2 1.8E3 8.8E4 8.8E2 9.1E4 l 22 4.0E1 5.9E2 1.3E4 3.0E5 8.8E2 3.1ES
| |
| ; 23 4.1E-4 4.9E-5 2.2E-2 9.9E-2 8.8E2 8.8E2
| |
| ; 24 7.1E0 1.6E3 2.3E3 8.1ES 8.8E2 8.1E5 25 1.3E0 2.0E4 2.8E3 1.0E7 5.2E3 1.0E7
| |
| ! 26 1.0E0 1.EE4 3.2E2 8.0E6 5.2E3 8.0E6 i
| |
| i .
| |
| l .
| |
| | |
| .O O TABLE 4 O
| |
| FUEL BUILDIltG Radiation Data Norial Oper.
| |
| Max. LOCA Do'se DBA-LOCA1 40-Year Dose TID 2 Elevation Zone Rate (R/Hr) Dose (Rads) (Rads) (Rads)-
| |
| 595+0 99 9.8E1 2.3E3 8.8E2 3.2E3 605+10 46 4.0E4 9.3E5 l 8.8E2 9.3E5 47 5.8E3 1.3E5 ' 8.8E2 1.4E5 48 2.4E3 5.6E4 8.8E2 5.7E4 97 1.6E3 3.7E4 8.8E2 3.8E4 98 9.8E2 2.3E4 8.8E2 2.4E4 631+6 100 9.4E0 2.2E2 7.0E2 9.2E2 l
| |
| Notes: IUse Figure 5.0-1 to determine fraction of 1-year dose.
| |
| 2 TID = Total Integrated Dose. Equal to total 40-year normal operating dose plus 1-year LOCA dose.
| |
| i 1
| |
| 1 l
| |
| | |
| ~~
| |
| * ~' " ~~
| |
| V
| |
| , TABLE 5 CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 2
| |
| | |
| ==SUMMARY==
| |
| OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 763 '
| |
| i (1) Pressurizer Pressure (HSSS) (Lot 2)
| |
| '(Lower Containment) l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT ,,
| |
| (% OF SPAN) (% OF SPAN)
| |
| ENVIR0fMENT(3),.
| |
| Temp: 327 F Temp: 380 F SI Initiation >5 minutes + 10% Max. error 7.7%
| |
| Press: 14.4 psig Press: 75 psig (<5 minutes) post DBE 1H: 100% RH: 100%
| |
| (5 minutes)
| |
| Tad: 1X107R Rad: SX107R Thea Spray: Boric Chem Spray: Boric icid and sodium acid and sodium
| |
| :etraborate soln. hydroxide soln.
| |
| 2750 ppm Boron 8.5 pH !
| |
| \ ;
| |
| }
| |
| ]UALIFICATION REPORT (4): WCAP 9885 Radiation Zone: 9 Elevation: 565 4ETH00: Test ECSE e
| |
| i
| |
| | |
| +
| |
| O O TABLE 6 O
| |
| CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 20 t SUt94ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT k
| |
| . EQUIPMENT 10: Auxiliary Building Filtered MANUFACTURER: Reliance MODEL #: 1XF882610, 2XF882610 (1) Exhaust Fan Motors i.
| |
| ' RECIRCULATION RADIATION i RADIATION LEVEL TO WHICH ,
| |
| ENVIRONMENT
| |
| * QUALIFIED
| |
| , . (TID) (2) (TID) ,
| |
| i 8
| |
| i 1.1X10 RAD 2X108 RAD i
| |
| 1
| |
| ., t
| |
| ]
| |
| 1 QUALIFICATION REPORT: NUC-9 (CNM-1320.00-0003) l METil00: Test / Analysis -
| |
| Radiation Zone: #2 Elevation: 594 EPSR k
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| . s-Radiation Zone Map -
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| Auxillary Building Elevation 594+0 i.
| |
| '-'u. .
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| ''~
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| CATAWBA NUCLEAR STATION ~
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| ~ '
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| Figure 2
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