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Revision as of 03:16, 27 February 2020
| ML20010A676 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/07/1981 |
| From: | Schmidt H TEXAS UTILITIES SERVICES, INC. |
| To: | Burwell S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 TXX-3384, NUDOCS 8108120017 | |
| Download: ML20010A676 (56) | |
Text
{{#Wiki_filter:_ c,. s TEXAS UTILITIES SERVICES INC. Log # TXX-3384 ami nnyas Towen . n4u.as. Texas 7320, Mle # W.5 August 7, 1981 g% $pnHsW N One.anth
- Mr. :Spottswood. Burwell e A Licensing Project Manager \ %
U. S. Nuclear Regulatory Comission / f Office of Nuclear Reactor Regulation , , y9') Washington, D.C. 20555 , #j C.
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SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION ' a, f CONTROL 0F HEAVY LOADS: NUREG-0612 b/;7,. (\(/
Dear Mr. Burwell:
Please find attached the response to Enclosure 3 of NRC letter dated December 22, 1980. If you have any questions, please call. Sincerely,
,n .. b / $m H. C. Schmidt Attachment l
cc: R. D. Calder l J. T. Merritt l J. C. Kuykendall ! R. A. Jones R. E. Ballard A. T. Parker l Vc,Ml , F10912OO17 PDR 810807"i ADOCK 0500044S PDR
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' CONTROL OF HEAVY LOADS: NUREG-0612 1
s i .. ! RESPONSE TO ENCLOSURE 3 of '- NRC LETTER DATED DECEMBER-22, 1980 I' 1 t a f i
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INTRODUCTION 4
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In'a letter dated December 22,-1980, the NRC requested applicants for i operating licenses to submit a report documenting their compliance with-NUREG-0612, " Control of Heavy Loads at Nuclear Power Plaats." This report should include the information idettified in Section 2.1 thru 2.4 of Enclosure 3 of the letter (Request for Additional Information on Control ~ ,- of Heavy Load). The letter specified that the report be submitted in two { parts according to the following schedule: Part I - Submit Section 2.1 information within six months from the date on the letter. Part II - Submit Section 2.2, 2.3 and 2.4 information within nine months. In addition, applicants are to complete necessary changes and modifications to plant equipment within two years of submittal of Section 2.4 of Part II above. This submittal provides the response to Part I of the requirement,' which consists of information on compliance with Section 5.1.1 of NUREG-0612. i
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Pagn 1 of 43 COMMENT: 1. Report the results of your review of plant arrangements to identify all overhead handling systems from which a load drop may result in damage to any system required for plant shutdown or decay heat removal (taking no credit
. for any interlocks, technical specifications, operating procedures, or detailed structural analysis).
RESPONSE: The overhead handling systems at CPSES from which a heavy load drop could result in damage to systems required for I plant shutdown or decay heat removal are summarized in Table 1. Also listed in Table 1 are cranes which are capable of carrying loads in or near spent fuel storage areas. l l l l l
- _ . ,_ ,-_~ _. . _ . . . . _ _ _ . . , _ _ . _ , , _ _ _ , _ _ _ _ , . - , _ _ . , , _ _ _ . _ . ,
4 Page 2 of 43 COMMENT: 2. Justify the exclusion of any overhead handling system from the above category by verifying that there is sufficient physical separation from any load-impact point and any safety-related component to permit a determination by inspection that no heavy load drop can result in damage to any system or component required for plant shutdown or decay heat removal. RESPONSE: Table 2 lists the overhead handling systems at CPSES l which maintain sufficient physical separation from j- systems required for plant shutdown or decay heat removal to prevent damage to these systems, as determined by visual inspection. Therefore, these overhead handling systems have been excluded from the category of load handling systems listed in Table 1. l l l l r I l l t I l l 2
1 Pags 3 of 42 COMMENT: 3. With respect to the design and operation of heavy-load-handling systems in the containment and the spent-fuel-pool area and those load-handling systems identified in 2.1-1 above, provide your evaluation co3cerning compliance
, with the guidelines of NUREG 0612, Section 5.1.1. The
- following specific information (Comments 3[a] through 3[g])
should be included in your reply. RESPONSE: Our evaluation of compliance with NUREG 0612 concerning heavy I load handling systems at CPSES is presented in the responses to the specific requests for. information (Comments 3[a] through 3[g]) listed below. Comment 3(a): Drawings or sketches sufficient to clearly identify the location of safe load paths, spent fuel, and safety-related equipment. Response 3(a): " Safe load areas" (areas serviced by a particular crane in which a load drop will not result in damage to shutdown or decay heat removal equipment or spent fuel) have been identified where applicable for the cranes listed in Table 1. Equipment handled i by these cranes will be transported whenever possible within the identified safe load areas..
" Safe load paths" will be established for equipment handled outside the safe load areas and will be incorporated in the particular j load handling procedures.
l Safe load paths will also be identified for those loads which will require a load drop l analysis in order to saticfy the NUREG-0612 requirements. These safe load paths will be f I 1
i t ' Paga 4 of 43 described and illustrated as part of any load drop analysis performed in response to the Part II requirements of the NRC December 22, 1980 letters. Each crane listed in Table 1 is described
~
' below with a discussion of the safe load areas along with referenced drawings to identify their location within the plant.
A. Fuel Building Overhead Crane - (CPX-MESCFC-01) This crane is shown in Figure 1 along with
-the safe load area illustrated by the cross-hatched region. Although this crane does not travel directly over the spent fuel pools, a safe load area has been defined octside the spent fuel pool areas. The safe load area includes the fuel receipt and inspection areas and the shipping cask ,
receipt and decontamination area. B. Containment Auxiliary Upper Crane - (CP1&2-MESCCA-01) This crane and its assocated safe load
, areas are shown in Figure 2. The area serviced by this crane includes the reactor vessel and ths: fore the potential exists gg for a heavy load drop into the vessel. As a result, the safe load nrea is defined outside of the reactor vessel area as indicated by the cross-hatched area in Figure 2.
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i , 1 Pagn 5 of 43 C. Contain. ment Polar Crane - (cpl &2-MESCCP-01) The area in the containment building serviced by this crane, along with its safe load area, is shown in Figure 3.
. The Polar Crane essentially travels the entire diameter of the Containment Building above elevation 905' and has the potential
. for heavy load drops over the reactor vessel, steam generators, reactor coolant pumps and piping, main steam lines, and the Containment fuel storage area. Therefore, the safe load areas have been defined outside of these areas as shown in Figure 3.
When spent fuel is not being stored in the . Containment fuel storage area, this crane can safely traverse this area with a heavy load. D. Containment Fuel Handling Bridge Crane - (CP1&2-MESCCF-01) This crane is designed for lifting a 7uel assembly and component and associated handling tool. These loads are excluded from consideration as " heavy loads as defined in NUREG 0612 and therefore safe load areas are not required. E. Containment Building Refueling Machine - (TBX-FHSCMC-01) This crane is shown on Figure 2. This crane is specifically designed to handle fuel assemblies and therefore does not handle
" heavy loads" as defined in NUREG 0612.
1 A
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6 Paga 6 of 43 F. Containment Dome Rotating Platform Hoist - (cpl &2-MESCRP-01) This hoist traverses over the same areas covered by the Containment Polar Crane and therefore has the same safe load areas as
. illustrated in Figure 3.
G. Service Water Intake Structure Crcnc - (CPX-MESCSW-01) This crane is shown on Figure 4 along with the safe load areas. Since most of the equipment serviced by this crane is safety related Service Water pumps and piping, only small portiors of the intake structure can be considered as safe load areas as illustrated in the cross-hatched areas in Figure 4. H. Fuel Building Fuel Handling Bridge Crane - (TBX-FHSCFB-01) This crane is shown on Figure 1. The crane is designed to handle a fuel assembly and components with its assocated handling tool and therefore does not carry " heavy loads" as defined in EUREG 0612. No safe load areas are therefore required. For the hoists listed in Table 1, the establish-ment of safe load areas is not practical since the hoists generally travel along a single mono-rail which allows the hoist to follow only one possible path. Locations of the hoists with respect to plant shutdown equipment, decay heat removal equipment, or spent fuel storagt areas are shown in the figures listed below for each hoist identified in Table 1.
\
Pega 7 of 43
- 4. Moderating HX and Letdown HX Figure 5 Hoist (CP1&2-MEMCH-16)
B. Component Cooling Water Pump Figure 6 Hoist (CPX-MMHCH-01) C. Safety Related Chiller Figure 7 Hoist (CP1&2-MEMHCH-04) D. Centrifugal Charging Pump Figure 6 Hoist (cpl &2-MEMHCH-01,02) E. Safety Injection Pump Hoist Figure 8 (CP1&2-MEMHCH-06,07) F. Residual Heat Removal Pump Hoist Figure 8 (CP1&2-MEMHCH-08,09) G. Auxiliary Feedwater Pump Hoist Figure 8 Electric - (cpl &2-MEMHCH-13,14) H. Auxiliary F2edwater Pump Hoist Figure 8 Turbine - (CP1&2-MEMHCH-12) I. Auxiliary Building Filters Hoist Figure 9 (CrX-MEMHWR-04) J. Diesel Generator Hoist Figure 10 (cpl &2-MEMHCH-37,38) K. Spent Fuel Pool HX Hoist Tigure 11 (CPX-MEMHCH-43,44) L. Service Water Traveling Figure 4 Screen Hoist (CPX-MEMHCH-12) l i
6 Pega 8 of 43 M. Residual Heat Removal and Containment Figure 5 Spray HX Hoist (cpl &2-MEMHCH-47,59) N. Main Steam Safety Valve Hoist Figure 12
, (cpl &2-MEMHCH-48,49,50,51)
O. Service Water Intake Stop Gate Hoist Figure 4 (CPX-MEMHCH-61) P. Reactor Coolant Pump Hoist Figure 3 (CP1&20MEMHC-42) (See Note Below) Note: Reactor Coolant Pump Hoist (CP1&2-MEMHCH-42) is attached to the Containment Polar-Crane duringcertainReactorCoolant$ ump maintenance operations. i 1 y , _
Pasa 9 of 43 Comment 3(b): A discussion of measures taken to ensure that load-handling operations remain within safe load paths, including pro-cedures, if any, for deviation from these paths. Response 3(b): Through the use of administrative centrols, heavy loads will be transported whenever possible within " safe lo ad areas" established in response to Ccament 3(a) above. The " safe, load areas" will be clearly identified for each crane by a combir ation of placards, procedures, and marked off areas near plant shutdown and decay heat removal equipment or where spent fuel is stored. However, for some heavy loads, it may be necessary to operate outside the " safe load areas" and transport the heavy load over or near plant shutdown or decay heat removal equipment or spent fuel. In that event, special precautions or procei as will be utilized with the purpose of minimizing the risk of a heavy load drop in these areas. The procedures will consist of load drop prevention uea-sures such as a list of required equipment, inspectic as, acceptance criteria for the movement of the load, sequence of steps, etc. " Safe load paths" will also be establisned with the purpose of transporting ecnfoment over safe shutdown or decay heat removal equipment or spent fuel via the safest and shortest route to the nearest " safe load ares". The equipment will then be transported within the
" safe load area" to its final destination.
The " safe load paths" will be clearly defined in the load I handling procedures that will be written for loads handled over safety equipment or spent fuel. As stated in response to Commenc 3(a), " safe load paths" will be defined and illustrated as necessary as part of any load drop analysis performed in response to Part II requirements of the NRC December 22, 1980 letter concerning "Ileavy Loads at Nuclear Power Flants". i
s Psg2 10 of 43 Comment 3(2): A tabulation of heavy loadc to be handled by each crane which includes the load identification, lead weight, its designated lif ting device, and verification that the handling of such load is governed by a written procedure containing, as a minimum, the information identified in
. NUREG 0612, Section 5.1.1(2).
Response 3(c): Table 4 lists the cranes and hoists identified in Table 1 including the major loads projected to be lif ted by each handling system. Also included is the approximate weight of each of the loads identified. As stated in the response to Comment 3(b), special precautions and pro-cedures will be utilized when handling these loads over or near safe shutdown equipment, decay heat removal equipment, or spent fuel storage areas. 9
6 i Page 11 of ? Comment 3(d): Verification that lifting devices identified 1 2.1.3(c) above comply with the requirements of ANSI NJ 6-1978, or ANSI B30.9-1971 as appropriate. For lifting evices where
- these standards, as supplemented by NUREG 0612, Section 5.1. l(4) or 5.1.1(5), are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability.
Response 3(d): Lifting devices for the loads identified in response to Comment 3(c) above will comply with ANSI B30.9-1971 where applicable. Although'a special lifting device for a spent fuel shipping container weighing 10,000 pounds or more has not as yet been procured, ANSI N14.6-1978 will be invoked when this special lifting device is obtained. Although it is anticipated at this time that tne standards for the lifting devices will be met, it may later be determined that alternatives to the standard are required. In that event, written notification will be made to the Nuclear Regulatory Commission describing the alternatives and their equivalency in terms of load handling reliability. CPSES and Westinghouse Nuclear Division are currently reviewing the design and construction specifications of the Reactor Vessel Head and Reactor Internals lifting rigs. The results of this review will be submitted with the Part II response of CPSES compliance with NUREG-0612.
i l
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Pzgs 12 of 43 Comment 3(e): Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspection, testing, and maintenance. Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency of proposed alternatives. Response 3(e): ANSI B30.2-1976, Chapter 2-2, will be invoked with respect to crane inspection, testing and maintenance. With respect to Section 2-2.1.1.1 of ANSI B30.2-1976, cranes located within Containment will be inspected per the required visual inspection schedule only during the periods of crane operation (generally during refuelings and cold shutdowns). This is necessary because periodic inspections during power operations are impractical due to high radiation levels in Containment. a No other exceptions to the standard are anticipated at this time, however, if it is later determined that exceptions are required, written notification will be made to the Nuclear Regulatory Commission.
Pcga 13 of 43 Comment 3(f): Verification that crane design complies with the guidelines of CMAA Specification 70 and Chapter 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements for instances where speciric compliance with these standards is not provided. Response 3(f): Table 3 lists the load handling systems identified in Table 1 and their applicable codes and standards as specified in the CPSES Equipment Purchase Specifications. 2 In all cases the cranes design complies with the guidelines of CMAA Specification 70 and chapter 2-1 of ANSI B30.2-1976. Exception is taken for " Fuel Building Fuel Handling Bridge Crane", (TBX-FHSCFB-01) and " Containment Building Refueling Machine", (TBX-FHSCMC-01), because this equipment is designed for the handling of a fuel assembly and its associated handling tool. By definition in NUREG-0612, this load is not considered as a " heavy load". i l l 1 9
Pags 14 of 43 Comment 3(g): Exceptions, if any, taken to ANSI B30.2-1976 with respect to operator training, qualification, and conduct. i Response 3(g): No exceptions to ANSI B30.2-1976 with respect to operator training, qualifications, and conduct are anticipated at
- this time, however, if it is later determined that exceptions are required, written notification wf11 be made to the Nuclear Regulatory Commission.
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Page 15 of 43 1 TABLE 1 OVERHEAD LOAD HANDLING SYSTEMS WITH POTENTIAL FOR LOAD DROP DN SPENT FUEL OR SYSTEMS REQUIRED FOR PLANT SHUTDOWN OR DECAY HEAT REMOVAL Equipment and/or Piping Crane /Holst Name Crane /Holst I. D. No. Location Elevation Capacity (Tons) Along The load Path
- 1. Fuel building overhead CPX-MESCFC-01 Fuel building Above 860' 130-17-5 Spent fuel pool coollag piping crane. Spent fuel transfer area l
- 2. Containment auxillary CP1-MESCCA-01 Containment Above 905'-9" 5 Reactor vessel upper cranes CP2-MESCCA-01 building
- 3. Containment polar CP1-MES CCP-01 Containment 950'-7" 175-20 Reactor vessel cranes CP2-MESCCP-01 building Steam generator Reactor coolants pumps Reactor coolant piping
?
4 Moderating HX. and CPI-MEMHCH-16 Safegv?rds 831'-6" 2 Train "A" electrical tray letdown chiller HX CP2-MEMHCH-16 building (cabling for AUX
- Feedwater holst.* System Component Cooling Water System Motor operated valves) located near the monorail
- 5. Component cooling CPX-MEMHCH 01 Auxillary 810'-6" 4 Component cooling (CCW) water l water pump hoist building pump and associated piping 4
- 6. Safety related CPI-ME MHCH-04 Auxillary 718' 1 1/2 CCW piping connected to the chiller hoist CP2-MEHHCH-04 t.:lding chiller, j Chiller, i
*HX. = Heat Exchanger, AUX = Auxillary
- Page 16 of 43 e d 1
TABLE 1 (continued) Equipment and/or Piping Crane /Holst Name Crane /Holst 1. D. No. Location Elevation Capacity (Tons) Along The Load Path
- 7. Centrifugal charging CP1-MENtDI-Cl, 02 Auxiliary 810'-6" 4 Centrifugal charging pump pumps holst. CP2-M MICH-01, 02 building and associated piping and j
valves. 8 Containment fuel CP1-MESCCF-01 Containment - Above 860' 1 1/2 Containment fuel transfer handling bridge crane CP2-MESCCF-01 building area and fuel rack.
- 9. Safety injection CP1-MEMICH-06, 07 Safeguards 773' 3 Service water piping.
pumps holst. CP2-M MICH-06, 07 building
- 10. Residual heat recoval CPI-MENICH-08, 09 Safeguards 773' 3 RHR pump and associated pumps holst. CP2-MENIOl.08, 09 building piping and valves.
- 11. Auxillary feedwater CPI-MENICH-13, 14 Sa feguards 790'-6" 4 Motor driven auxillary feed-pump holst. (electric CP2-MMICH-13,14 building water pumps, piping and valves motor driven pump) i
- 12. Auxillary feedwater CP1-ME' NIDI-12 Safeguard 790'-6" 3 Tubine driven auxillary feed.
pump holst. (turbine CP2-MMIDI-12 building water pump, piping and valves. driven pump)
- 13. Auxillary building CPX-MEMMR-04 Auxillary 852'-6" 8 Various systems filters.
. filters holst, building
- 14. Reactor coolant CP1-MEMICH-42 Containment 905'-9" 40 Same as pc or crane, pumps holst. CP2-ME NICH-42 building See Note 1.
Page 17 of 43 l .< i. f . TABLE 1(continued) j - j Equipment and/or Piping 1 Crane /Holst Name Crane /Holst 1. D. No. locati on Elevation Capacity (Tons) Along The load Path a 15 Diesel generator CPI-MEMHCH-37, 38 Sa feguards 810'-6" 1 Diesel generator and i (plston) holst. CP2-MEMHCH-37, 38 building its associated piping j and instrumentation. f l 16 Spent fuel pool CPX-MEMHCH-43, 44 Fuel 838'-9" 4 Spent fuel pool heat HX. holst.* building exchangers, pfptng and valves. 17 Service water CPX-MENCH-12 Outside of 8 38 ' 20 Traveling screen.
, traveling screen service water holst. structure.
- 18. Residual heat remova' CPI-MEMHCH-47, 59 Sa feguards 831'-6" 10 RHR & CSS heat exchanger and (RHR) HA. and Contain. CP2-MEMRCH-47, 59 building- its associated piping and ment Spray System (CSS) valves, holst.
, 19. Main steam safety CPI-MEMHCH-48, 49, 50, 51 Safeguard 880'-6" 1 Main steam safety valves.
- f valves holst. CP2-MEMHCH-48, 49, 50, 51 building j 20. Se vice water intake CPX-MESCSW 01 Service water Above 796' 71/2 Service water pumps and its
, structure crane. structure associated piping and valves. 1 4 21 Containment done CP3 -P.ESCRP-01 Containment 1000' 1 Reactor vessel. l access rotating CP2-MESCRP-01 building Fuel storage rack. Steam
- platform holst, generator. Reactor coolant pumps. Reactor coolant piping l
l
4 Page 18 of 43 i i i 1 TABLE 1 (continued) Crane /Holst Name Equipment and/or Piping Crane /Holst I . D. No. Location Elevati on Capacity (Tons) Along The load Path i
- 22. Fuel building TBX-FHSCFB-01 Fuel building Above 860' Fuel handling 2 Spent fuel pool
; Bridge crane Refueling canal New fuel storage pit l 23. Containment building TB X-FHSCMC-01 Containment Above 860' 2 Refueling machine Reactor vessel building Containment fuel transfer area.
4 4
- 24. Service water intake CPX-ME MH CH-61 Service water 789' - 9" 8 Service water pumps, stop gate holst. Intake structure i
I l NOTE: 1. Reactor Coolant Pumps Holst is attached to the Polar Crane Hooks during the maintenance operation of the Reactor Coolant Pump. I j 1 I i i i t 4 3 n 1 ? 9 I
Page 19 of 43 4 l . TABLE 2 DVERHEAD LOAD HANltlNG SY$TEttS CRANES AND HOISTS WHIOl DO NOT REQUIRE ADDITIONAL REVIEW AND EVALUATION 2 Crane /Holst Mart p) Crane /Holst I.D.No. Loc ation Elevation Capacity (Tons)
- 1. Drunning storage CPX-MESCDS-01 Fuel building 831' 15 area crane.
- 2. Maintenance building CPX-MESCMI-01 mintenance building N/A 25 bridge crane.
i I
- 3. Turbine build hg CPI-MESCTC-01 Turbine butiding 830' Main hoist - 210 gantry trane. CP2-MESCTC-01 Aux. hoist - 50
, 4. Circulating water CPI-MESCCW-01 Circulating water- 810' Main holst:
- intake structure intake structure. Inside span - 25 gantry trane. Outside span - 12 Auxiliary holst
- 5
- 5. Equipment hatch CP1-MEMHCH-41 Containment building 832'-6" 10 door holst. P 223' i
; 6. Waste gas compressor CPX-MENIDI-05 Auxillary building 831'-6" 1 ! holst.
.t
- 7. Positive displacement CPI-MEMHCH-03 Auxiliary building 810*-6" 6
, charging pump holst. CP2-MEMHOi-03
- Equipment in or near the load path is not required for safe shutdown or decay heat removal.
Also the load does not travel in or near spent fuel storage area. 1 f ,1
Page 20 of 43 TA8tE 2 (continued) Crane /Holst Name* Crane Aloist I .D. No. Loc ation Elevation Capacity (Tons)
- 8. H2 Recombiner holst. CPX-MMIDI.07 Auxiliary building 831' 6" 1
- 9. Letdown chiller CPI-MEMtOI-05 Auxiliary building 85? '- 6" 2 package holst. CP2-MENICH-05
- 10. H&V chiller hoist CPX-M MICH 09 Auxiliary building 873' 6* 6 (near H-A line). ,
l
- 11. H&V chiller hoist CPX-MMIOi-10 Auxillary building 873'-6" 1 l
(near J A Ilne).
- 12. Let down HX. and** CPI-MMICH-15 Safeguard building 810'-6" 1 1/2 seal water HX. holst. CP2-MEMtOt-15 l
- 13. Condenser vacuum CPI-MENICH 25 Turbine building 778' 4 1 pumps holst. CP2-MENIDI-25 l 14 Turbine plant cooling CPX-MEMiOI-11 Turbine building 778' 6 water pump holst.
l 15 . eater drain pump CP1-MEMt04-28 Turbine building 778' 4 l holst. CP2-MEMHCH-28
- 16. Control fluid tank CP1-MENICH-29 Turbine building 778' 3 pumps holst. CP2-MENICH-29
- 17. Personnel lock hoist CP1 KMidi-30 Safeguard building 831'-6" 2 CP2-M Mful-30 9 317'
**HX - Heat Exchatger l
Dage 21 of 43 TA8tE 2 (continued) Crane /Holst Name Crane /Holst I.D. No, locati on Elevation Capacity (Tons) 18 Reactor vessel studs CP1-MEMlJC-01 Containment building 905'-9" 1/2 holst. CP2-MENHJC-01 See dwg. - Al-0505
- 19. Steam generator feed CPI-E MHOC-01 Turbine building 803' 10 water pump and turbine CP2-MEMHOC-01 drivers holst.
- 20. Equipment hatch & CPI-MEMIQl-45 Safeguard building 790'-6" 4 790'-6" for mis'. CP2-EMICH-45 equipment hoist
- 21. Equipment hatch 9 CPI-MMICH-46 Safeguard building 810'-6" 4 810*-6" for misc. CP2-MEMHCH-46 equipment holst.
- 22. Equipment hatch 9 CPX-MEftlOI-52 Auxillary building 873'-6" 1 87-6" for alsc.
ver.tllation equipment holst.
- 23. Equipment hatch 9 CPX-MENICH-53 Auxillary building 886*-6" 1 886'-6" for misc.
ventilation equipment holst. 24 Decontamination of CPX-ME 41CH-54 Unit 2, turbine 81 0' 2 misc. equipment holst, building (see drawing A2-0403) 25 Decontamination of CPX-M MlOI-55 Unit 2, turbine 8.0'-6" 1/4 misc. equip. holst. building Lm -
4 Daqe 22 of 4? l TABLE 2 (continued) Crane /Holst Name Crane /Holst I .D. No. Location Elevation poacity(Tons) l t 26 Dry waste compactor CPX-EMICH-56 fuel building 810'-6" 2 l holst.
- 27. Chlorine containers CPX-MMIDI-57 holst* Service water 823'-9" 2 chlorination building l
28 Chlorine containers CPI-EmiOf-58 C c, water 809'-6" 2 holst. chlorina tion building
- 29. Auxillary steam CPX-EmiO4-60 Auxillary building. 778' I condensate cooler l holst.
i
- 30. Containment equip. CPX-MCMICH-67 Outside containment -
40 hatch holst. CPX-MEMHCH-68
- 31. Wall puller for CPI-flEMitH-01 Safeguard building 831'-6" 3/4 let down secl water CP2-EMILH-01 HX and let down chiller HX.
< 32. Demineralizers holst. CPX-MEMfWR-05 Auxillary building 852'-6" 8
- 33. Radial are stud TB X-FilHCN1-01 Containment building Below 860' 2 tensioner holsts.
Page 23 of 4? TABLE 1 OVERHEAD LOA 0 HANDLING SYSTEMS APPLICA8LE CODE AND STANDARDS 1 Crane /Hofst Name Crane /Holst I. D. No. Location Elevation Capacity (Tons) Code and Stanaerd j
- 1. Fuel building overhead CPX-MESCFC-01 Fuel building Above 860' 130-17-5 CMAA* Spec. No. 70 crane. and ANSI 830 2-1976, Chapter 2-1,
- 2. Containmeat auxillary CPI-MESCCA-01 Containment Above 905'-9" 5 CMAA Spec. No. 70 upper tranes. CP2-MESCCA-01 building and ANSI 830.2 1976, Chapter 2-1.
- 3. Containment polar CP1-MESCCP-01 Containment 950'-7" 175-20 CMAA Spec. ho. 70 cranes. CP2-MESCCP-01 building and ANSI 830.2-1976 Chapter 2-1.
- 4. Moderating HX. and CP3-MEmiO1-16 Safeguards 8 31 '- 6" 2 CMAA Spec. No. 70, I letdown chiller HX CP2-MEMf01-16 building l holst.*
- 5. Component cooling CPX-MEMHCH-01 Auxiliary building 810'-6" 4 CMAA Spec. No. 70.
water pump holst.
- 6. Safety related CP1-MENICH-04 Auxiliary building 778' 1 1/2 CMAA Spec. No. 70.
chiller holst. CP2-MENICH-04
- 7. Centrifugal charging CPI-MDtfCH-01, 02 Auxillary butiding 810*-6" 4 CMAA Spec %. 70.
pumps holst. CP2-MDtiOI-01, 02
*HX. = Heat Exchanger, AUX = Auxiliary, CMAA = Crane Manufactures Association of America.
Page 24 of 43 j TABLE 3 (continued) Crane /holst Name Cranc/Holst I.D. No. Location Elevation Capaci ty (Tons) Code and Standard 8 Containment fuel CP1-MESCCF-01 Containment Above 860' 1 1/2 CMAA. Spec. No. 70 handling bridge crane. CP2-MESCCF 01 ' As t iding ANSI 830.2-1976, Chapter 2-1. i 9 Safety injection CPI-MENICH-06, Os Safeguards 773' 3 CHAA Spec. No. 70. pumps holst. CP2-MENICH-06, 07 building i
- 10. Residual heat removal CPI-MEMICH-08, 09 Sa feguards 773' 3 CMAA Spec. No. 70.
- pumps holst. CP2-MENICH-08, 09 buildfr.;
- 11. Auxillary feedwater CP1-P UICH-13,14 Safeguards 790'-6" 4 CMAA Spec. No. 70.
., pump holst. (Electric CP2-MEMHCH-13,14 building
- motor driven pump).
1
- 12. Auxiliary feedwater CP1-MEMh01-12 Safeguards 790'-6" 3 CMAA Spec. No. 70.
pump holst. (Turbine CP2-MENICH-12 building
! driven pump),
t l 13. Aux 111ary building CPX-MEMiWR-04 Auxiliary 852'-6" 8 CMAA Spec. No. 70 filters holst. building 14 Reactor coolant CPI-MENICH-42 Containment 905'-9" 40 CMAA Spec No. 70. I pumps holst. CP2-MENICH-42 building i
- 15. Diesel generator CP1-MEMf01-37, 38 Sa feguards 810' 6" 1 CMAA Spec. No. 70 (plston) holst. CP2-MENICH-37, 38 building i
[ 4 1
Page 25 of 43 ,, TABLE 3 (continued) Crane /Holst Name Crane /11oist I .D. No. Location Elevatton Qpacity(Tons) Code and Standard l l Fuel building 8 3." -9" 4 CMAA Spec. No. 70
- 16. Spent fuel pool CPX-MEHICH-43, 44 l HX. holst.*
Outside of 838' 20 CMAA Spec. No. 70 l 17. Service water CPX-MEMHOI-12 l traveling screen service water hoist, structure. l l CPI-MENICH-47, 59 Safeguards 8 31 '- 6" 10 CMAA Spec. No. 70 l 18 Residual heat removal (RHR) HX. and Contain. CP2-MEMICH-4 7, 59 building l i ment Spray System (CSS) I holst. CP1-MEMtOf-48, 49, 50, 51 Safeguard 880'-6" 1 CHAA Spec. No. 70.
- 19. 11ain steam safety valves holst. CP2-MEMICH-48, 49, 50, 51 building
[ Service water Above 796' 71/2 CHAA Spec. No. 70 20 Service water CPX-MESCSW-01 i structure and ANSI B30.21976, l Intake structure Chapter 2-1. crane. l Containment 1000' 1 CMAA Spec. No. 70 f 21 Contaf e r.c dome CP1-MESCRP-01 ' l access rotating CP2-MESCRP-01 building l
. platform holst.
Fuel building Above 860' 2 CMAA Spec. No. 70.
- 22. Fuel building (**) TBX-FilSCFB-01 fuel handling bridge crane.
**This equipment is designed for handling a fuel assembly and its associated handling tool.
u
i j Page 26 of 43 j .- i I i l TABLE 3 (continued)
- J Crane /Holst Name_ Crane /Holst I .D. No. Location Eleva ti on Capacity (Tons) Code and Standard i
1
- 23. Containment building (**) TBI-FHSCMC.01 Containment Above 860' 2 CMAA Spec. No. 70 refueling machine, building 24 Service water intake CPI-MEMHCH-61 Service water 8 CMAA Spec. No. 70 i stop gate holst, intake structure ' 789'.9" --
i i a
; NOTE: 1 Reactor Coolant Pumps Holst is attached ot the Polar Crane Hooks during the maintenance operation of the Reactor Coolant Pump.
l i i i l a i I i ) l 1 I 4 I a s i 0
Paae 27 of 43 TABLE 4 OVERHEAD LOAD HANDLING SYSTEM PROJECTED LOADS AND WEIGHTS Approx.
- Anticipated Crane /Holst Equipment I.D. Number Location Elevation Projected Loads Load Wts. Lifting Devices
- 1. Fuel Building Overhead CPX-MESCFC-01 Fuel Building 860' A. Spent Fuel Cask 250,000 lbs. SLD Crane B. New fuel Assembly asd Handling Tool 1,700 lbs. NR C. New Fuel Shipment Cas.- 6,700 lbs. S D. Fuel Transfer Canal 12,000 lbs. 5 i Stop Gates. 12,000 lbs. S l
- 2. Containment Auxillary CPI-MESCCA-01 Containment 90S' A. Reactor Vessel Stud
! Upper Crane CP2-MESCCA-01 Tensioning Device 4,000 lbs. S . t B. Reactor Vessel Stud I I Transport Baskets 4,440 lbs. S i i l C. Reactor Vessel Studs 740 lbs. S l l 3. Containment Polar Crane CPI-MESCCP-01 Containment 950' A. Reactor Vessel Head and l l . CP2-MESCCP-01 Lifting Rig 260,000 lb=. NR B. Internals Lifting Rig 150,000 .a. NR C. Reactor Vessel Upper Internals 132,000 lbs. SLD D. Reactor Vessel Lower i l Internals 280,000 lbs. SLD l E. Reactor Coolant Pump Internals 55,200 lbs. S
- 1. Pump Stator 47,600 lbs. S
- 2. Rotating Element 7,600 lbs. S F. Reactor Coolant Pump Motor and Lifting Rig 87,500 lbs. SB
- 1. Stator 4A,000 lbs. S
- 2. Rotor 31,500 lbs. S
- 3. Fly Wheel 16.125 lbs. S
- 4. Air Coolers 1,000 lbs. S G. Reactor Coolant Pump Motor Stand 11,000 lbs. 5 H. Fuel Storage Area Stop 12,000 lbs.
Gate S
Dage 3 of 43 . l .e TABLE 4 (CONT.) Approx.
- Anticipated Crane /HolstEquipment_ I.D. Number location []g.yalign ,ftgjgitedJppdi JD4d_RL. Lifting Device
- 4. Moderating Ileat Exchanger CPI-MEMICH-16 Safeguards 831' A. Moderating HX Channel i Holst CP2-M[MICH-16 Head 268 lbs. S B. Moderating HX Tube Bundle 1,515 lbs. S C. Moderating HX Shell 2.558 lbs. S
- 5. Component Cool- . Water CPX-MENICH-01 Auxtilary Bldg. 810' A. Component Cooling Pump Holst Water Pump 6,500 lbs. S B. Component Cooling Water Pump Base 3.300 lbs. S C. Component Cooling Water
( Pump Motor 7,500 lbs. 58 1 D. Vah es - 24 In. 1,040 lbs. 5 E. Emergency Fan / Coll Unit S Motor 200 lbs. l 6. Safety Related Chiller CPI-MEMHCH-04 Auxiliary Bldg. 778' A. Processing Tank 2,900 lbs. SB i Holst CP2-MENICH-04 B. Acid Tank & Pump 1,000 lbs. S f C. Chiller 2,300 lbs. S j D Electrical Cabinr4 1,500 lbs. S i E. Motor & Compres'or 300 lbs. 5 F. Precooler Her'. Exchanger 2.465 lbs. 5 i 7. Centrifugal Charging CPI-MERICH-01, 02 Auxiliary Bldg. 810' A. Centrifugr Charging
, Pump Holst CP2-MEMHCH-01, 02 PM (CCr) (Total) 7,500 lbs. S B. CCP Cear Assembly 2,700 lbs. S C. CCP Motor (Total) 5,830 lbs. SB D. CCP Motor Rotor 1,760 lbs. S E. Lube Oil Cooler (Shell) 260 lbs. S F. Emergency Fan / Coll Unit Motor 140 lbs. S t
- 8. Containment Fuel Handling CPI-MESCCF-01 Containment 860' A. Fuel Assembly and Lifting 1,700 lbs. NR Bridge Crane CP2-MESCCF-01 Tool 4
4 a
Pa0e 29 of 43 .
.c TABLE 4 (CONT.)
- Approx.
- Anticipated Crane /Holst Equipment I.D. Number Location Elevation Projected Loads Load Wts. Lifting _pevice
- 9. Safety injection Pump CPI-MEMHCH-06, 07 Safeguard Bldg. 773' A. S.I. Pump 6,000 lbs. 5 Holst B. S.I. Pump Motor 4,800 lbs. SB
- 10. RHR Pump Holst CPI-MEMHCH-08, 09 Safeguard Bldg. 773' A. RHR Pump 4,400 lbs. SB CP2-MENHCH-08, 09 B. RHR Pump Motor 5,100 lbs. SB C. RHR Pump Casing 1,815 lbs. S D. RHR Pump Rotor 2,585 lbs. S ,
E. RHR Pump Motor Assembly 9,500 lbs. SB . j
- 11. Auxiliary feedwater CPI-MENHCH-13, 14 Safeguard B1dg. 790' A. Aux. Fdwtr. Pump . 4,000 lbs. 5 Pu.np Holst (Motor CP2-MEMHCH-14, 14 8. Aux. Idwtr. Pump Motor 7,100 lbs. SB Driven) C. Aux. Fowtr. Pump Rotor 1,224 lbs. 5 D. Aux. Idwtr. Pump Upper 1,200 lbs. S Casing
- 12. Auxiliary Feedwater Pump CPI-MEMHCH-12 Safeguard Bldg. 790' A. Aux. Fdwtr. Pump 4,000 lbs. 5 Holst (Turbine Driven) CP2-MEMHCH-12 B. Turbine Driver 2,800 lbs. SB C. Aux. Fowtr. Pump Rotor 1,150 lbs. 5 D. Aux. Fdwtr. Pump Casing 1.300 lbs. S
- 13. Auxiliary Building CPX-MEMPWR-04 Auxiliary B1dg. 852' A. Filter Element Transfer Filter Area Holst Cask 6,800 lbs. S B. Filter Compartment Concrete Floor Plugs (MAX) 16,000 lbs. S
- 14. Reactor Coolant Pump CPI-MIMHCH-42 Containment 905' A. Reactor Coolant Pump Holst CP2-MEMHCH-42 Internals 55,200 lbs. S
- 1. Pump Stator 47,600 lbs. S
- 2. Pump Rotating Ela. 7,600 lbs. 5 B. Reactor Coolant Pump Motor and Lifting Rig 87,487 lbs. SB
- 1. Stator 48,003 lbs. 5 i
- 2. Rotor 31,484 lbs. S
- 3. Fly Wheel 16.125 lbs. S
- 4. Motor Air Coolers 1.100 lbs. S C. Reactor 7901 ant Pump Motor Stand 11,000 lbs. 5 s
Page 3n of 43 .
. .e l
4 . TABLE 4 (CONT.) Approx.
- Anticipated Crane /Holst Equipment I.D. Number Location Elevation Projected Loads Load Wts. Lifting Device 4
- 15. Diesel Generator Holst CPI-MEMCH-37, 38 Safeguard Bldg. 810' A. Various Piping And Struc-
] (Piston) CP2-MEMCH-37, 38 tural Components on or Near { Diesel Generator Set 2,000 lbs. S ); 16. Spent Fuel Pool Heat Exchanger Holst CPX-MEMHCH-43, 44 Fuel Bldg. 838' A. Spent Fuel Cooling Pump 2,500 lbs. 5 B. Spent Fueld Cooling Motor 2,100 lbs. 5 C. Spent Fuel Heat Exchanger j
- 1. Shell 7,600 lbs. SB
; 2. Tube Bundle 7,400 lbs. SB D. Concrete Floor Plugs (MAX) 8,000 lbs. S i 17. Service Water Traveling .PX-MEMICH-12 Service Water Intake -
A. Miscellaneous Parts, Trays, Screen Holst
- Chains, Housing, Chain Guides (Max.) 3,500 lbs. SR I
- 18. RHR and CSS Heat CP!-MEMHCH-47, 59 Safeguard Bldg. 831' A. Containment Spray Exchanger Holst CP2-MEMICH-47, 59 Heat Exchanger
- 1. Shell Body 1.300 lbs. 58 i I. Tube Bundle 17,000 lbs. 58 B. RHR Heat Exchanger
- 1. Shell Body 7.750 lbs. SB
- 2. Tube Bundle 16,600 lbs. 58 C. Compartment Concrete Floor Plugs (MAX) 20,000 lbs. S
, 19. Main Steam Safety CPI-MEMHCH-48 thru 51 Safeguard Bldg. 880' A. Main Steam Safety Valves 1,550 lbs. S j Valves Holst CP2-MENICH-48 thru 51 i 20. Service Water intake CPX-MESCSW 01 Service Water intake - A. Service Water Pump Motor 9,700 lbs. S I Structure Bridge Crane B. Fire Pump Jockey Pump 525 lbs. S C. Fire Pump Jockey Pump Motor 235 lbs. S j,
D. Fire Pump Diesel Driven Pump 4.730 lbs. 5 E. Fire Pump Diesel Driven Pump 4 i Driver 3,450 lbs. SB F. Fire Pump Diesel Drive Pump Ibs.
; Gear 1,450 lbs. 5 G. Fire Pump Diesel Coupilng 181 lbs. 5 ' H. Fire Pesnp Elec. Driven Pump 4,730 lbs. S I. Fire Pump Elec. Driven Pump Mtr. 4,800 lbs. S l
n i l 1 i
l Page 11 of 43 -- i
.a 4
TABLE 4 (CONT.) i
! Approx.
- Anticipated Crane /Holst Equipment I.D. Number Location Elevation MjectedLoads Load Wts. Lifting Device i
- 21. Containmant Done Accest CPI-MESCRP-01 Containment 1000' A. Misc. Tools 200 lbs. S Rotating Platform Holst CP2-MESCRP-01 B. Welding Equipment 300 lbs. 5
- 22. Fuel Building Fuel TBX-FHSCFB-01 Fuel Building 860' A. Failed Fuel Assembly and i Handling Bridge Crane Lifting Tool 3,000 81bs. NR B. Fuel Assembly and Tool 2,000 lbs. NR
- 23. Containment Building TBX-FHSCMC-01 Containment 060' A. Fuel Assemly 1.500 lbs. NR Refueling Machine
, 24. Service Water Intake CPX-MEMHCH-61 Service Water - A. Service Water Pump S Stop Gate Holst intake Structure Compartment Stop Gates. 16,000 lbs. i t 4 4 4
- Lifting Device Sy bois S- Sling or Cable Arrangement SB - Sling and Spreader Bar Arrangement SLD - Special Lifting Device NR - None Required i
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.' .' P TEXAS UTILITIES SERVICES INC. Log # TUS-3193 OFFICE MEMOR ANDU M File # 903.11 To J. S. Marshall Dallas, Texas August 6: 14R1 Subject COMANCHE PEAK STEAM ELECTRIC STATION WORKING MEETING WITH SEISMIC AND DYNAMIC LOADS SECTION On August 4,1981, a working meeting was held on the CPSES dockets with the Seismic and Dynamic Loads Section of the Equipment Qualification Brnch of the NRC Staff. The meeting was held in the Westinghouse conference room in Bethesda, Md., and a list of those that attended the meeting is attached.
Ed Bond of Gibbs and Hill gave an overview presentation on B0P seismic qualification and copies of his slides are attached. John McInerny and Vic Miselis of Westinghouse gave an overview of the NSSS seismic qualification. The SQRT Review Forms and the seismic qualification documentation for 6 B0P pieces of equipment (see attached slides) and 3 NSSS pieces of equipment (Charging Pumps, PAMS Recorders, and Accumulators) were examined by the NRC staff. The SQRT Review Forms
~ are enclosed.
Although the depth of review was by necessity rather shallow, many aspects of the seismic qualification for CPSES were discussed. No outstanding areas of disagreement were identified between the staff's requirements and the way the seismic qualification program for CPSES was being implemented and documented. In the staff's opinion, if significant problems existed they should have been discovered during this meeting. On this basis, the CPSES seismic qualification program can be considered acceptable pending a final confirmatory audit. A stenary of this working meeting shall be written by the staff in about one month to be followed by an input for the SER Supplement on 9-15-81. During the meeting, the staff had the following specific comments:
- 1. The table of qualification data should be submitted about 2 months prior to the confirmatory audit. The G8H Status Report would be adequate if it were changed to include (a) locations (buildings and elevation), (b) natural frequencies,
' (c) status of installation, and (d) test data such as multiple versus single frequency and multiple versus single axis.
- 2. For equipment selected for the audit, documentation should be available that shows:
(a) That the seismic qualification documentation is applicable to the CPSES equipment, (b) That the seismic qualification documentation as been accepted (i.e. , is not preliminary and has no outstandingcomments),and (c) That any deficiencies identified during testing were resolved and modifications, if required, were made to the CPSES equipment.
- 3. The SQRT Review Foms should include:
(a) Specific mounting configurations and important test results which are clearly stated to avoid confusion or misunderstandings, (b) Multiple sheets (2 thru 4) when multiple reports are referenced, and (c) Completed sheets (2 thru 4) for each device or component when a piece of equipment includes multiple devices or components. In general the staff said that thav were pleased with what they saw. I highly recommend that Gibbs and Hiil continue updating their Status Repert and expats this report to include the infccmation requested by the staff. This report will be extremely valuable for the audit with respect to both time and man-hours by having an updated status rather than trying to go back and remove data from previously reviewed reports. It shall also be valuable if (as the staff projected may be required by rulemaking), TUSI is required to establish a separate seismic file similar to the environmental qualification file. CPSES should be ready for the final confirmatory audit in the first or second quarter of next year. The staff will perform the audit when about 90% of the equipment is qualified and installed. The staff does not include piping or structures in this 90% number but does include all other Category I equipment such as valves, pumps, instrumentation, panels, etc. Please call me if you have any questions. D. R. Woodlan DRW/grr Attachment Enclosure I cc: File (w/ encl) A. T. Parker [ .R. E. Ballard
- S. B. Buneell-R. A. Jones J. C. Kuykendall J. T. Merritt L. M. Popplewell J. L. Montgomery (w/ encl)
R. D. Calder
ATTENDANCE MEETING ff/)Mf) Y DATE / Q , Y/[ffff f f , /ff / TIHE f!$0i2f)L.- !OD9? PLACE h Q g/lg7,9 hp_f//
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t COMANCHE PEAK STEAM ELECTRIC STATION SQRT/TUSI/W/G&H MEETING AUG. 4, 1981 NRC OFFICES, BATHESDA, MD. BOP SEISMIC CATEGORY I EQUIPMENT QUALIFICATION OUTLINE
- 1. CLASSIFICATION OF EQUIPMENT
- 2. SEISMIC QUALIFICATION CRITERIA
- 3. EQUIPMENT QUALIFICATION STATUS
- 4. EQUIPMENT QUALIFICATION DOCUMENT FLOW
- 5. STATUS FORM
- 6. RESPONSE TO NRC QUESTIONS Q150.1 THROUGH Q150.6 - GENERAL DISCUSSION
- 7. PRESENTATION / REVIEW 0F SQRT QUALIFICATION FORM (Q150.6) i 8. GENERAL QUESTION / ANSWER - THROUGHOUT MEETING l
l l l l l ! AUGUST 4, 1981 PAGE 1 l l
i ~ CLASSIFICATION OF EQUIPMENT SEISMIC CATEGORY I (CLASS IE AND NON-CLASS 1E) EQUIPMENT. COMPONENTS AND PARTS THEREOF REQUIRED TO REMAIN FUNCTIONAL TO ENSURE:
- 1. THE INTEGRITY OF THE REACTOR COOLANT PRESSURE BOUNDARY;
- 2. THE CAPABILITY TO SHUTDOWN THE REACTOR AND MAINTAIN IT IN A SAFE SHUTDOWN CONDITION; OR
- 3. THE CAPABILITY TO PREVENT OR MITIGATE TH5 CONSEQUENCES OF ACCIDENTS THAT COULD RESULT IN POTENTIAL OFFSITE EXPOSURES COMPARABLE TO THE GUIDELINES OF 10 CFR, PART,100.
FUNCTIONAL
- 1. STRUCTURAL INTEGRITY ABILITY OF EQUIPMENT TO FUNCTION BY RETAINING ITS STRUCTURAL STRENGTH BY MAINTAINING STRESSES DEFLECTIONS, CLEARANCES, WITHIN SPECIFIC LIMITS
- 2. OPERABILITY ABILITY OF EQUIPMENT TO EXCECUTE AND RETAIN A DESIGN FUNCTION.
- 3. COMBINATION OF 1 & 2 NOTE:
NON-SEISMIC CATEGORY I EQUIPMENT WHOSE FAILURE COULD ADVERSELY AFFECT THE FUNCTION OF CATEGORY I EQUIPMENT IS QUALIFIED AS SEISMIC CATEGORY I EQUIPMENT. l l AUGUST 4, 1981 PAGE 2 l l
EQUIPMENT SEISMIC QUALIFICATION CPITERIA OVERALL GENERAL GUIDE FOR SEISMIC QUALFICATION: 1EEE STD. 344 - 1975: IEEE RECOMMENDED PRACTICES FOR SEISMIC QUALIFICATION OF CLASS IE EQUIPMENT FOR MUCLEAR POWER GENERATING STATIONS NRC REGULATORY GUIDES , 1.29 SEISMIC DESIGN CLASSIFICATION 1.48 DESIGN LIMITS AND L3ADING COMBINA~i10NS FOR SEISMIC CATEGORY I FLUID SYSTEM COMPONEhTS - 1.60 DESIGN RESPONSE SPECTRA FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS . 1.61 DAMPING VALUES FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS 1.89 QUALIFICATION OF CLASS IE EQUIPMENT FOR NUCLEAR POWER PLANTS 1.92 COMBINING MODAL RESPONSES AND SPATIAL COMPONENTS IN SEISMIC RESPONSE ANALYSIS 1.100 SEISMIC QUALIFICATION OF ELECTRICAL EQUIPMENT FOR NUCLEAR POVER PLANTS 1.122 DEVELOPMENT OF FLOOR DESIGN RESPONSE SPECTRA FOR SEISMIC DESIGN OF FLOOR - SUPPORTED EQUIPMENT OR COMPONENTS NRC BRANCH TECHNICAL P0SITION PAPERS CODES AND STANDARDS ASME B&PV CODE, SECTION III AISC SPECIFICATION ANSI STANDARDS AUGUST 4, 1981 PAGE 3
l I 1 G&H EQUIPMENT SPECIFICATIONS ELECTRICAL MECHANICAL HVAC INSTRUMENTATION AND CONTROLS STRUCTURAL ARCHITECTURAL G&H SEISMIC SPECIFICATION 2323-SS-20: SEISMIC CRITERIA FOR EQUIPMENT DESIGN
- METHODS OF QUALIFICATION
- 1. ANALYSIS .
- 2. TESTING
- 3. COMBINATION OF TESTING AND ANALYSIS AUGUST 4, 1981
' AGE 4 ,
TEXA5 UTILITIES GENERATION COMPANY COMANCHE PEAK STEAM ELECTRIC STATION SPECIAL ANALYSIS
~
SEISMIC CATEGORY I EQUIPMENT QUALIFICATION (CLASS 1E AND NON-CLASS 1E) A. IEEE 344 (CLASS 1E) PLANS REPORTS TOTAL ESTIMATED 111 196 TOTAL RECEIVED 100 - 164 TOTAL APPROVED 66 116 TOTAL UNDER REVIEW 1 1 TOTAL AEN 33 47 NOT RECEIVED 11 32 B. SEISMIC CATEGORY I (NON-CLASS 1E) PLANS REPORTS t TOTAL ESTIMATED 66 229 f l TOTAL RECEIVED 53 210 l TOTAL APPROVED 45 147 l . TOTAL UNDER REVIEW 0 0 TOTAL AEN 8 63 NOT RECEIVED 13 19 AUGUST 4, 1981 PAGE 5
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, REVISES I PLAtt BOP EQUIPMENT QUALIFICATION FLOW DIAGRAM AUGUST 4, 1981 PAGE 6 i
1
r--____ _ _ _ _ _ ._ s . SPEC.: ES-1D.1 TEXAS UTILITIES GENEHATING CONPANY SHEET 2 P.O.s CP-0411A COMANCHE PEAK ST4 FAN ELECTHIC STATION TITLE: SERVICE NATER PUNP NOFORS C6H PROJECT NO. 2323 DATE: SEISNIC CATEOORY ! EQUIPNENT OUALIFICATION STATUS REPORT VENDORS SIENENS-ALLIS, INC. INCLUDING CLASS IE EQUIPMENT IEEE STD 344-1975 QUALIFICATION NUCLEAR SAFETT BELATEDs (S-A) lui ves i I No l C. I I i 1 1 EQUIPMENT l LI QUALIFICATION PIAN l QUALIFICATION NETHODOIDGY l QUALIFICATION REPORT I 1 l ll A1. l l l l t i SI i e i i i i i l RENARES I l COsePONENTS/ 1SI FIAN l PLAN 1 DYN l STAT 1 TEST I PAST 1 REPORT l REPORT I i l STATUS I I IDENTIFICATIOff I STATUS 1 ANAL i ANAL l I HIST l IDENTIFICATION 1 STATUS I l . I 118 1 l 1 1 1 1 l i l l 8 I I I I I I I I I I l l Service Mater Pump lYeelpeport includes plan i I i I I I lS-A Report 'Eqpt. Qual. LAPP l l lNotors (900 H.P.) I 1 l l l l 1 l Form-Nound Motors,* S-A ICTM-33847 l l l l l l l l l l lorder No. 3-5017-90244 12-5-79 l l l Plan - APP l l l l l l l lIssue 2, 9-25-78, 5-A 1 1 l l Report - APP l l l l 1 1 l l Cover Letter 12-4-79 I I I I i 1 1 l l l 1 1 1 I i
,1 1 1 l i I I I I I I I I I i i i : I i 1 i l I I I i 1 1 1 i 1 1 1 1 I I i i 1 i 1 i i i l i I i 1 1 1 1 1 1 1 I ! I I i l I 1 1 1 1 I i l i i l l ll l 1 1 1 I i 1 1 1 1 1 1 1 1 I I I I I I I I i i 1 I i 1 1 1 1 1 1 1 I i 1 i l 1 ) 1 I I I I I i i l I I I L 1 1 1 h l l l 1 I . I i i 1 H I 1 1 1 1 1 1 1 I
. 1 1 ll l l 1 l l I I I I i i i I i 1 I i 1 1 I I P H I 1 l l l 1 I I 1 1 i l 1 1 .1 1 1 I I I I i l 1 1 I i 1 1 1 l l 1 1 I i i 1 1 1 1 1 1 I l
1' 1 1 1 1 1 1 1 1 I I I I I 1 1 1 1 1 1 I I i 1 1 I 1 I 1 1 i 1 I I i 1 I I I I i i 1 i l I i i l 1 i 1 i l l l l 1 3 I I l l l ' l I l
- l. I l i I I I i 1 1 1 1 I I I I i 1 1 1 1 1 1 l i I I i 1 1 I 8I I i 1 LEGEND: APP - APP. NED NRC - SUSNITTED TO NRC (LETFER NO. AND lbATE AS NOTED)
AEN - APPRb'" A. PT AS 100 FED, NAY PROCEED NITN FABRICATIOGR N/A - NOT APPLICABLE F10 - FOR INFO N- .f * - REVISED SINCE LAST ISSUE RFC - RETURNF". TIOst, NAY NOT PROCEED NITN FABRICATION AUGUST 4, 1981 PAGE 7 ,
( Q150.6 QUALIFICATION
SUMMARY
OF EQUPMENT SPEC. NO. DESCRIPTION OF EQUIPME'NT
~
- 1. 2323-ES-10.1 SERVICE WATER P. UMP MOTORS (900 HP)
- 2. 2323-ES-6 480 V LOAD CENTER UNIT SUBSTATIONS '
l - TRANSFORMERS l l
- 3. 2323-ES-24 SOLID STATE ISOLATION EQUIPMENT CABINETS
- 4. 2323-MS-13 SPENT FUEL POOL COOLING WATER PUMP MOTORS (250 HP)
- 5. 2323-MS-80B COMBINATION STARTERS
- 6. 2323-MS-605 MAIN CONTROL BOARDS - UN'IT CB-09 AUGUST 4, 1981 PAGE 8
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