ML19332B088: Difference between revisions
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Revision as of 11:26, 27 February 2020
| ML19332B088 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/22/1980 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML19332B085 | List: |
| References | |
| NUDOCS 8009240513 | |
| Download: ML19332B088 (275) | |
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History (A30-00-G-900-SA-003) A30-06-0-000-SA-001 L H. iCXSON .?. AUG19 bou Title ! O DESIGN SPECIFICATION 1 NUCLEAR CLASS 2 & 3 SMALL PIPING AND TNRTRUMENT AND a)NTROL PIPING AND TUBING ENRICO FERMI POWER PLANT, UNIT 2 l l l Project l Design l Spec.fication i : O ; i 1 t Edison
\
l 3071-525 Number Rev. A . O Date MARCH 1980 l-l -_. . . _ . - . L_ l
Specificction 3071-525 Prsp rsd by Enrico Ferni II Project Management Organization Issued: 12-10-75 n
%J Rev. A: 3-21-80 DETROIT EDISON SPECIFICATION DESIGN SPECIFICATION FOR NUCLEAR CLASS 2 AND 3 SMALL PIPING AND INSTRUMENT AND CONTROL PIPING AND TUBING Enrico Fermi Atomic Power Plant - Unit 2 DATE WRITTEN BY:
~
, f 80 R . J . ADLER /
CHECKED BY: / d / G' J [H. CASIGLIA - P.E. O S ERV S NG NG R dA/2/7c7 ~/M
~
R. W. ' BARF & M. G. />IGETICH PROJECT SYSTEM f/
/ ,
ENGINEER:
> W 7- 6 -80 D. F. LEHNERT, P.E.
9 gy h} 7 - 3. / - 70 T . H . DICK' SON , J R . REVIEWED: PROJECT ENGINEERING ASSURANCE ffIlb A. D. SMART ' SPECIFICATION CONTROL . LJ // f/ 6 /VO GENERATION ENGINEERINM DEPARTMENT - STAFF SPECIFICATION CONTROL - Generation Engineering Department - Staff t O 3071-525A.1 i l
MpecSUSectSen 27/h-kn3 Prcp;r:d by Enrico FGrmi 11 Proj:ct Managsment Organization Issued: 12-10-75 Rev. A: 3-21-80 DETROIT EDISON SPECIFICATION DESIGN SPECIFICATION FOR NUCLEAR CLASS 2 AND 3 SMALL PIPING AND INSTRUMENT AND CONTROL PIPING AND TUBING Summary of Revision A Section Description of Revision Effective Date
- 3. Revised to incorporate Addendum A 10-31-79 and changed temperature limitation from 300 F to 575 F.
8.1.A Revised to agree with Specifica- 3-01-76 tion 3071-032 Revison B. 9.3 Second paragraph on design thermal 3-21-80 and pressure displacements. 9.4.1 Revised to incorporate Addendum A 10-31-77 g and operating temperation condi- W tions. 9.4.2 Revised to incorporate Addendum A. 3-01-78 9.6 Changed section title to pipe 10-31-77 supports. 9.6.1 Revised second paragraph to 10-31-77 incorporate Addendum A. 9.6.4.3 Revised reference from 9.7.5.1 and 1-22-80 97.5.2 to 9.6.4.1 and 9.6.4.1. Changed means of attaching plates from Phillips Red to wedge anchor. 9.6.4.7 Removed entire article 10-31-77 9.6.4.8 Renumbered to 9.6.4.7 due to N/A deletion of old section 9.6.4.7. I I 3071-525A.2 l l
0 0 DETROIT EDISON SPECIFICATION DESIGN SPECIFICATION FOR NUCLEAR CLASS 2 AND 3 SMALL PIPING AND INSTRUMENT AND CONTROL PIPING AND TUBING ENRICO FERMI ATOMIC POWER PLANT UNIT 2 l l l l l l l 3071-525A.0 O
MjosROMOGIFGi1DXl/H937#
- Pr:parcd by Enrico Farmi 11 Project Managtment Organization Issued: 12-10-75 Rev. A: 3-21-80 DETROIT EDISON SPECIFICATION DESIGN SPECIFICATION FOR NUCLEAR CLASS 2 AND 3 SMALL PIPING AND INSTRUMENT AND CONTROL PIPING AND TUBING Summary of Revision A Section Description of Revision Effective Date 9.6.5 Added new section on variable 5-01-78 spring and mechanical snubber design.
9.6.6 Changed section of article from 10-31-77 10.3 and revised second paragraph to incorporate Addendum A. 9.10 Changed title of article, rewrote 3-31-80 paragraph on flexibility require-ments. . 9.11 Added paragraph five on maximum 2-09-78 allowable span for vertical pipe runs. 10.1.B Revised design temperature 10-31-77 10.2.B Revised design temperature 10-31-77 10.2.C Revised material specifications 3-02-78 10.3 Changed to article 9.6.6. N/A 14.1 Added to References, Specification 4-16-79 3071-527, 3071-528, and 3071-529 14.12, 14.13, 14.4 Additions to References. I 1 !O 3071-525A.3 i _ _I
Specific.itien 3071-525 Prspared by Enrico F.tr=i II Projset :tnsgsment Organiza: ion Issued: 12-10-75 Rev. A: 3-21-80 0 DCRs and DCNs Cleared By Rev. A DCR I-0002 DCN 0219 DCR P-0563 DCN 0355 DCR P-0570 DCN 0469 DCN 0534 DCN 0566 DCN 1305 Rev.A Revision A Incorporates Addendum A Note: The above DCR's and DCN's are not retroactive. O I 3071-525A 4 i I
Sp;cificcticn 3071-525 Prsp red by , Enrico Ferni II i ProjIct Managsment l Organization i Issued: 12-10-75 )
,, Rev. A: 3-21-80 i
\# DETROIT EDISON SPECIFICATION DESIGN SPECIFICATION FOR NUCLEAR CLASS 2 AND 3 SMALL PIPING AND INSTR.UMENT AND CONTROL PIPING AND TUBING Enrico Fermi Atomic Power Plant - Unit 2 INDEX ARTICLE CODE ARTICLE PAGE
- 1. SCOPE .................................. NA-3250 .......... 1
- 2. CERTIFICATION .......................... NA-3250 .......... 1
- 3. CLASSIFICATION ......................... NA-2000 .......... 2
- 4. DOCUMENTATION .......................... NA-3256 .......... 2
- 5. DESCRIPTION ............................ NA-3252 (a).......... 4
(]) 6. APPLICABLE DOCUMENTS ................... NA-3254 .......... 4
- 7. DESIGN ................................. NA-3252 (b).......... 6
- 8. SYSTEM DESIGN BAS IS . . . . . . . . . . . . . . . . . . . . NB-3111 .......... 8
- 9. COMPONENT DESIGN BASIS ................. NB-3112 .......... 9
- 10. COMPONENT CHARACTERISTICS .............. NB-3112 .......... 19
- 11. CLASSIFICATION ......................... NB-2140 .......... 20
- 12. HYDROSTATIC AND LEAK TESTS . . . . . . . . . . . . . NB-6000 .......... 21
- 13. IN-SERVICE INSPECTION .................. 10CRF50 .......... 22
- 14. REFERENCES ........................................................ 23 Attachment Appendix A, ANSI-Rating, Material Table 3071-525A.5 O
Specificction 3071-525 Issu:d: 12-10-75 R2v. A: 3-21-80 A30-00-G-900-SA-00 DISTRIBUTION OF CONTROLLED COPI"S OF SPECIFICATION 3071-525 lll No. of Copies Recipient 1 A. Alexiou, QA for Transmittal to State of Michigan 1 Documentation Control, Fermi 2 1 Fermi 2 Site, W. M. Everett 1 Project Engineer, E. G. Sliper 1 (ea.) Originacors: R. J. Adler, J. H. Casiglia 1 Reviewer of Stress Report and Certifying Professional Engineer: J. H. Casiglia 1 Enc,ineering Organization: Sargent and Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Attention: Mr. F. P. Tsai 2 Installer and Inspector: General Contractor, EF2 Site Note: Uncontrolled copies may be distributed as needed. i 3071-525A.6 lh
Specificcticn 3071-525 Prspersd by Enrico Ferci II Project Management Organization Issued: 12-10-75
^ Rev. A: 3-21-80 U
DETROIT EDISON SPECIFICATION DESIGN SPECIFICATION FOR NUCLEAR CLASS 2 AND 3 SMALL PIPING AND INSTRUMENT AND CONTROL PIPING AND TUBING
- 1. SCOPE This document constitutes the Design Specification required by Article NA-3200 of ASME Boiler and Pressure Vessel Code, Section III,1971 issue,
" Nuclear Power Plant Components," for Nuclear Class 2 and 3 Small Piping and Instrumention and Control Tubing, to be install.e'. as part of the Nuclear Steata Supply System of the Enrico Fermi A'.omic Power Plant-Unit 2.
- 2. CERTIFICITION The undersigned registered Professional Engineer, competent in the field of design of piping and related nuclear energy system requirements, certifies th.2t this design specification together with the referenced documents complies with the requirements of Article NA-3250 of the ASME-Code, Section III and is correct and complete with respect to functions and operating conditions as required to provide a complete basis for design, construc-tion, and certified inspection in accordance with the code.
Juar 9. M80 DATE 0% SIGNATgkE
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BRANCH ZG$/2 WMEW t REGISTRATION', STATE , and NUMBER or STAMP .
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f4 / JOSEPH H. *., 4 CASfGLIA j c$ f i ce 2iEN 3i NO. G I /N E E R j eo '+, 3071-525A.7 Q'*..20842
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Specificcticn 3071-525 Rs,v. A: 3-21-80 Pega 2
- 3. CLASSIFICATION h The piping systems referred to in this specification are limited to Nuclear Class 2 and 3 piping and Instrument and Control System Piping and tubing 4 inches and smaller in nominal diameter.
Process and Instrumentatien and Control piping systems whose designs are controlled by this specification are divided into two distinct classifica-tions. Those piping systems 4" and less in noninal diameter with design temperatures of 575 F or less and with design pressures of 1750 psig or less , which are connected to the pressure boundary 'at piping systems or equipment classified as Clase 2, are also classified as Class 2. These systems shall be designed in accordance with the requirements of the ASME III Code, Subsection NC, 1971 issue, including addenda thru Winter 1971. Those piping systems 4" and less in nominal diameter with design temperatures of 575 F or less and design pressures of 1750 psig or less, which are connected to the pressure boundary of piping systems or equipment classified as Class 3, are also classified Class 3. These piping systems shall be designed in accordance with the requirements of ASME III, Subsection ND, 1971 issue, including addenda thru Wihter 1971. In those cases where field designed small piping connects to systems or equipment of different code classifications, the more stringent design requirements will be applied out to the first anchor or normally closed g valve on the small pipe line. All Nuclear Class 1 and that Nuclear Class 2 and 3 sinall piping whosa design temperature exceeds 575 F and/or design pressure exceeds 1750 psig is not within the scope of this specification, and must be designed to the criteria specified by the System Design Specification for the system under consideration. (Reference 1)
- 4. DOCUMENTATION
- 1. The Owner and User of the system will be: -
Detroit Edison 2000 Second Avenue Detroit, Michigan 48226 3071-525A.8 l
Specificoticn 3071-525 R v. A: 3-21-80 Pcgs 3
- 4. DOCUMENTATION (cont'd)
- 2. The piping will be installed in the ENRICO FERMI ATOMIC POWER PLANT-UNIT 2 6400 N. Dixie Highway Stony Creek, Monroe County, Michigan - 48166 (P.O. Newport, Michigan)
- 3. The installer of the system will be designated by the Owner.
- 4. The enforcement authority having jurisdiction ht the location of the piping systems is:
l THE STATE OF MICHIGAN I DEPARTMENT OF LABOR BUREAU OF SAFETY AND REGULATION DEPARTMENT OF LABOR BUILDING 300 E. Ifichigan Avenue Lansing, Michigan 48913
- 5. Communications between the installer or manufacturer and the enforcement authority will be through the Owner unless specifically required by the code to be otherwise. In the latter case, prior approval r ' obtained and advance copies of the correspondence directed ,wner's documentation of fice and the cerfifying Professu . Engineer (s) of this document.
- 6. The Owner will comply with Article NA-3256 in filing a copy of this design specification with the enforcement authority before the piping is placed in service.
- 7. The manufacturer and/or installer shall identify the authorized inspection agency to the Owner on or before the contract date and shall provide the inspection agency with all required documentation, including the Quality Assurance Manual and this~ design specification.
- 8. A design report will be prepared for the piping systems within the scope of this specification. This report will be reviewed by those responsible for the design specification. The design report will be prepared by the Owner or his designated agent. The design methods, procedures, and records required by this specification and its attachments and references will form the basis for the preparation of the design report.
O l 3071-525A.9 ,_ l
Specificction 3071-525 R_v. A: 3-21-80 Pcg] 4
- 4. DOCUMEfffATION (cont 'd)
- 9. Each manufacturer and/or installer shall furnish the Owner with a copy of the appropriate certificate of authorization not later than the date of contract, (Article NA-3330).
- 10. Upon completion of the contract each manufacturer and/or installer shall complete the appropriate certificate of compliance and submit a copy of the certificate to the Owner for inclusion in the Owner's data report form N-3, (Article NA-3270)
- 5. DESCRIPTION (This is a functional description and not a code requirement.)
The field designed small piping within the scope of this specification is grouped into two general categories. 5.1 Instrumentation and Control Piping and Tubing The instrumentation and control piping and tubing is used to convey pressure signals and/or fluid samples from the process lines to the instrumentation for subsequent measurement or analysis. It is also used to convey a control medium (air, water, nitrogen) to an actuating device such as a hydraulic or pneumatic operator, hydraulic cylinder or diaphragm operator. Although the instrumentation and control piping and tubing may be connected to the process piping g pressure boundary, it is not considered to be functionally part of the process stream. 5.2 Small Process Piping The small process piping typically serves as an interconnection between a main process pipe header and an individual piece or small group of equipment or components. A typical example of a small process pipe is the interconnecting pipe between a main cooling water header and a locally mounted compartment fan-coil cooler. The small process piping constitutes an extension of the system process boundary.
- 6. APPLICABLE DOCUMENTS The design, material, fabrication, installation, inspection, and testing of the system and the system components shall be in accordance with the following:
O 3071-525A.10
Specificati:n 3071-525 R3v. A: 3-21-80 Page 5 () 6. APPLICABLE DOCUMENTS (cont'd)
- 1. This specification with the attachments.
- 2. The System Process and Instrumentation Diagrams 6M721-2000 Index and Legend of Abbreviations 6M721-2001 Legend of Symbols and Instr. Ident. for Plant System Diagrams 6M721-2002 Diagram - Main and Reheat Steam Systems 6M721-2015 Diagram - Station and Control Air - Unit 2 6M721-2017-1 Diagram - Off Gas Process System, Recombiner Chains I and II, Sheet 1 of 2 6M721-2017-2 Diagram - Off Gas Process System, Activity Reduction Chain, Sheet 2 of 2 6M721-2023 Diagram - Feedwater System 6M721-2027 Piping Diagram - Reactor Building Closed Cooling Water and Emergency Equipment Cooling Water Systems 6M721-2034 Diagram - Core Spray (C.S.S.)
6M721-2035 Diagram High Pressure Coolant Injection System - Reactor Building Unit 2 6M721-2043 Diagram - High Pressure Coolant Injection System - Barometric Condenser (HPCI) - Reactor Bldg. Unit 2 6M721-2044 Diagram - Reactor Core Isolation Cooling System 6M721-2045 Diagram - Reactor Core Isolation Cooling Barometric () 6M721-2046 Condenser (RCIC) Diagram - Reactor Water Clean-up, Reactor Bldg. (RWCU) 6M721-2047 Diagram - Reactor Water Clean-up, Filter /Demin., (RCiC) 6M721-2081 Diagram - Control Rod Drive System (CRD) 6M721-2082 Standby Liquid Control System 6M721-2083 Diagram - Residual Heat Removal (R.H.R. ) Division I 6M721-2084 Diagram - Residual Heat Removal (R.H.R.) Division II 6M721-2087 P&ID - Combustible Gas Control System 6M721-2088 Diagram - Reactor Water Clean-up Phase Separators 6M721-2089 Diagram - Nuclear Boiler System 6M721-2090 Diagram - Nuclear Boiler System 6M721-2833 Diagram - Reactor Recirculation System - Nuclear Boiler System 6M721-2985 , Diagram - Drips and Drains from
- team Lines and Mair Turbine 6M721-3445 Diagram - Nitrogen Inerting Diagram 6M721N-2046 P&ID Diesel Generator System - Division I-R.H.R. Complex 6M721N-2047 P&ID Diesel Generator System - Division II-R.H.R. Complex 6M721N-2048 P&ID Diesel Fuel Oil System and Lube Oil System '
Division I - R.H.R. Complex 6M721N-2049 P&ID Diesel Fuel Oil System and Lube Oil System I Division II - R.H.R. Complex O 3071-525A.11 1 -.
Specificcticn 3071-525 Rov. A: 3-21-80 P;g2 6
- 6. APPLICABLE DOCUMENTS (cont'd) h
- 2. (cont'd) 6M721N-2054 P&ID Service Water, Make-up, Decant and Overflow Systems - R.H.R. Complex 6M721N-2056 P&ID Diesel Cenerator Ventilation - R.H.R. Complex-Division 1 6M721N-2057 P&ID Diesel Generator Ventilation - R.H.R. Complex-Division 1 6M721N-2058 P&ID Diesel Generator Ventilation - R.H.R. Complex-Division II 6M721N-2059 P&ID Diesel Generator Ventilation - R.H.R. Complex-Division II 6M721-2028 Process Diagram - Radwaste System 6M721-2031 Sump Pump Diagram Sheet 1 - Radwaste System 6M721-2032 Sump Pump Diagram Sheet 2 - Radwaste System 6M721-2215 Chemical Waste System Diagram - Radwaste System 6M721-2263 Evaporator Feed Diagram - Radwaste System 7M721-2709 Diagram - Standby Gas Treatment and Primary Containment Purge System - Reactor Building SM721-3435 Diagram - Evaporator Drains hetering System to Drum Disposal Radwaste Building 6M721-4127 Reactor Drywell Cooling System Flow Diagram (P&ID) 6M721-4325 Control Center Air Condition System - Water Side 61721-2400-1 6I721-2400-2 Plant Sampling Data Plant Sampling Data R.W.B. g 61721-2400-3 Plant Sampling Data T.B.
61721-2400-4 Plant Sampling Data R.B. 61721-2649-1 Standby Gas Treatment System Diagram 61721-2181-1 Process Radiation System Diagram 61121-2181-2 Process Radiacion System Diagram 61721-2181-3 Process Radiation System Diagram
- 3. Other reference documents as listed under Article 14.
- 7. DESIGN 7.1 System Design Life The system shall be designed for an effective design life of 40 l years, accounting for corrosion, erosion, and fatigue. The corrosion l allowance to be used is: 1 0.120" for steam in carbon steel piping 0.080" for water in carbon steel piping 0.0024" for stainless steel piping 0.000 for gas filled lines 3071-525A.12 O
- Specificctien 3071-525 Rsv. At 3-21-80 Pego 7
- 7. DESIGN (cont'd) 7.2 Normal and Upset Environmental Conditions The small Piping Systems, situated in the primary containment will be exposed to the following condition during the life of the plant:
External Pressure = 0.0 to 2.0 psig External Temperature = +105 to 150 F (Range) Relative Humidity = 40 to 90% Atmosphere = 97% N2 , 3% 02 External Radiation - Gamma 50 Rads / Hour Neutron 140,000 N/Cm2 _ see, 7.3 Faulted Environmental Conditions in Drywell (one time only) External Pressure - -2 to 56 psig for 1 minute at 340 F.
-2 to 35 psig for 3 hours at 340 F.
-2 to 35 psig for 6 hours at 320 F.
O to 25 psig for 1 day at 250 F. O to 20 psig for 100 days at 200 F. O a 1 tive n" taitF - iooz Radiation = 2.6 x 107 RADS (gamma) 7.4 System Fluid Those piping systems within the scope of this specification will l contain the following fluids. , l Media: demineralized water, steam, air, and nitrogen I Radioactivity: 0.07 micro curie /mL at zero decay time ph 0 25 C: 6.0 to 8.5 ) Suspended Solids: <10 ppb Dissolved Oxygen: <200 ppb Halogens: <1.0 ppm O 3071-525A.13
Specifiestien 3071-525 Rev. A: 3-21-80 P g2 8
- 7. DESIGN (cont'd) 7.5 Environmental Conditions of Secondary Containment g Those piping systems within the scope of this specification situated in the secondary containment will be subjected to the following conditions:
External Pressurc = atmospheric External Temperature = winter minimum of 40 F faulted maximum of 148 F (for 8 hours) average operating of 70 F Relative Humidity = 50 to 90% Radiation = 7.9 x 103 RADS (gamma), (includes faulted dose)
- 8. SYSTEM DES 1CN BASIS 8.1 Deformation Limits
- a. Piping Components Cold working, cold forming, or bending of the Class 2 and 3 piping components within the juristiction of this specification is permitted.
- b. Pipe Suspension Components Pipe suspension components may be cold formed during fabrica-tion. Subsequent heat treatment is not required.
8.2 Cold springing is not permitted in the design of the piping. In esses where mismatches due to fabrication tolerances exist during the installation the size of the closure piece shall be field adjusted to provide the required fit. 8.3 Dimensional Limits Piping components shall be fabricated in accordance with the Fabrication Specification 3071-30 and the fabrication tolerances shall be per P.F.1. Standard ES-3. Dimensional standards for fittings shall be per ANS1 B16.9 for butt welding fittings and B16.11 for socket-welding fittings, unles: otherwise specified on the Piping Isometric Drawings. 3071-525A.14
Specificati n 3071-525 R2v. A: 3-21-80 Pcgs 9
- 8. SYSTEM DESIGN BASIS (cont'd) 8.4 Temperature Limits The metal and fluid temperature for cleaning, flushing, and decontaminating shall be above +60 F, but not exceeding 200 F for small piping systems.
- 9. COMPONENT DESIGN BASIS 9.1 Equipment Nozzle Interface Loads 9.1.1 In the case where piping designed in accordance with this specification is connected to process connections (nozzles on pumps, heat exchangers, etc. ) consideration as to the maximum loading imposed upon the equipment is required. The maximum loadings for piping designed in accordance with this specification are given in Table I. The system Design Specification (Reference 1) for the system in question must be consulted and a determination made that the maximum loads from the piping do not exceed the allowable nozzle loads specified for the piece of equipment under consideration.
9.1.2 In case of non process line small piping connections to equipment (i.e. instrument taps, bearing cooling water connections, etc.) the maximum loads imposed on the equipment are negligible, and need not be considered. 9.2 Major Piping Connection Interface Loads In those cases where piping designed in the field, in accordance with this specification, connects to main process piping, the maximum probable loads imposed by the small piping will be considered in the design of the main process piping, and no further consideration of these effects is required. 9.3 Equipment Nozzle and Primary Containment Penetration Thermal Deflection Process equipment nozzles which connect to piping designed under this specification are considered as anchor points and are not subject to significant thermal deflection. Unless provided elsewhere, design thermal and pressure displacements for smali pipe penetrations on the drywell shall be assumed to be 1.92-in. vertical and 1.11-in. radial. Des?.gn thermal displacements for small pipe penetrations on the sunpression chamber (torus) shall be assumed to be 0.43-in. vertical and 1.30 in. radial. 307b 525A.15
Specificati:n 3071-525 R v. A: 3-21-80 P:ga 10
- 9. COMPONENT DESIGN BASIS (cont'd)
O TABLE I MAXIMUM PIPING TERMINAL LOADS Pipe Size Schedule Moment Load (ft-lb) Shear Force (lb) 1/2 40 85 72 80 100 78 160 110 99 3/4 40 147 103 80 178 128 160 209 145 1 40 277 170 80 335 207 160 396 246 1-1/4 40 489 270 80 607 329 160 713 383 1-1/ 2 40 679 342 80 160 858 1060 427 529 lll 2 40 1170 536 80 1520 683 160 2040 912 2-1/2 40 2220 903 80 2790 1120 160 3410 1360 3 40 3590 1360 80 4630 1680 160 5990 2200 4 40 6690 2250 80 8890 2920 160 12300 3950 1 1 3071-525A.16 l l
Specificction 3071-525 Rev. A 3-21-80 Page 11
- 9. COMPONENT DESIGN BASIS (cont'd)
C) ' 9. 4 Thermal and Seismic Deflection of Major Process Piping Connections 9.4.1 Thermal Deflections of Major Process Piping Connections Small pipe connection points on major process piping linea are subject to the thermal deflections of the major process pipe . The design of the small pipe must incorporate suffi-cient flexibility to accommodate these thermal deflections. This flexibility will be provided by incorporating of f-set legs in the small pipe, oriented in a direction perpendicular to the direction of movement of the process pipe. The meth-ods of designing and sizing the thermal of fset legs in the small pipe shall be as given in Appendix D of Reference 2. Thermal deflections of the major piping systems are available in the computerized piping stress analysis, and will normally be supplied by Edison's Project Design Organization. In lieu of using the above information, the thermal deflection of the major process pipe connection may be calculated using the below listed formulae: (1) For carbon steel process pipe: AXT = 8.68 x 10~$ X AT AYT = 8. 68 x 10-5 Y AT Aa7 = 8. 68 x 10-5 I AT Where AX = the thermal movement of the process pipe in the east-wes t direction. AY = the thermal movement of the process pipe in the vertical direction. X = the distance g feet along an east-west line between the small pipe connection on the process pipe and the first anchor on the process pipe. i' = the dif ference in elevation in feet between the small pipe connection on the process pipe and the fits t anchor on the process pipe. 3 = the distance, in feet, along a north-south line, between the small pipe connection on the process pipe and the first anchor on the ,3 process pipe. b 3071-525A.17
Specificcticn 3071-525 Rav. A: 3-21-80 Pcgg 12
- 9. COMPONENT DESIGN BASIS (cont'd) 9.4 fcont'd) 9.4.1 (cont'd)
AT = the operating temperature of the major piping system minus -70 F. (2) For stainless steel process pipe: AXT = 1.18 x 10-4 ~X AT AYT = 1.18 x 10-4 Y AT AET = 1.18 x 10-4 5 AT Where all terms are as previously defined. In those cases where the connection point on the major process line is between two anchors, the distances to the farther anchor shall be used in the equations above. 9.4.2 Seismic Deflections of Major Process Piping The seismic deflections of major piping systems are available in the computerized piping erress analysis, and will normally be supplied by Edison's Project Design Organization. In the absence of the above information, the maximum probable seismic deflections of main process piping at points of intersection with field-designed small pipe withing the scope of this specification is 1/4 inch in each of three mutually perpendicular directions. These deflections shall be added to the thermal deflections calculated in paragraph 9.4. I and used as the basis for design of the offset legs, as described in Appendix "D" of Reference 2. 9.5 Seismic Deflection of Process Equipment The equipment attached to those Category I Piping systems within the scope of this specification, shall be considered as a rigid anchor, subjected to the seismic displacements of the supporting floor slab or other building structural component. The maximum probable seismic dispincements for the various major structural elements in the Reactor / Auxiliary Building and the RHR Complex are given in Tables 2 and 3 respectively. 3071-525A.18
i Specificcticn 3071-525 l Rsv. A: 3-21-80 l Page 13
- 9. COMPONENT DESIGN BASIS (cont'd)
[) TABLE 2 SEISMIC DISPLACEMENTS OF j RECTOR / AUXILIARY BUILDING STRUCTURAL COMPONENTS I Component Seismic Displacements (2*0.B.E.) East-West North-South Up-Down l 1st Floor Slab 0.024 in. 0.024 in. 0.0032 in. 2nd Floor Slab 0.056 in. 0.06 in. 0.0064 in. 3rd Floor Slab 0.08 in. 0.08 in. 0.0084 in. I 4th Floor Slab 0.096 in. 0.095 in. 0.0094 in. j i Sth Floor Slab 0.107 in. 0.102 in. 0.014 in. Biological Shield Wall 0.108 in. 0.104 in. Negligible Reactor Pedestal 0.21 in. 0.02 in. Negligible O TABLE 3 SEISMIC DISPLACEMENTS OF THE RHR COMPLEX STRUCTURAL COMPONENTS Component Seismic Displacements (2*0.B.E.) East-West North-South Up-Down Grade Floor Slab 0.012 in. 0.042 in. Negligible Upper Floor Slab 0.028 in. 0.056 in. Negligible Roof Slab 0.045 in. 0.059 in. Negligible f ( 3071-525A.19 l
Sp;cificatien 3071-525 R3v. A: 3-21-80 Pcgs 14
- 9. COMPONENT DESIGN BASIS (cont'd) 9.6 PIPE SUPPORTS O
9.6.1 Design Stress Limits or Load Ratings Supports shall be designed to resist the loads and permit the calculated piping movements determined by field calculations made in accordance with Reference 2, Appendices B thru D. Design stress limits and/or components standard support load ratings shall be determined in accordance with American National Standards Institute, Standard ANSI B.31.1.0 Paragraphs 120 and 121. 9.6.2 Column Design Structural members such as columns and struts may be long in proportion to their diameter or lateral dimensions. The slenderness ratio, K1/r, of compression members used in the design and fabrication of guides, sway braces, snubbers, seismic restraints and supplementary structural attachments shall not exceed 120. 9.6.3 Anchor Design Anchors, limit stops and rigid ties shall be provided for directing expansion away from equipment, control of line g behavior during temperature changes and for protection of elements in the system against excessive expansion travel. Provision must be made to assure that the anchor, limit stop or rigid tie is designed and proportioned to resist the absolute sum of the forces and/or bending moments in the pipe at either side of the anchorage location. 9.6.4 Structural Attachment 9.6.4.1 Wherever possible component support beam attachments shall be welded to major structural l steel or embedded steel plates as detailed on Detroit Edison Standard Drawing SP732 (see 9.7.8 for welding requirements). l l i l 3071-525A.20 i
Specificcticn 3071-525 Rsv. A: 3-21-80 Page 15 () 9. COMPONENT DESIGN BASIS (cont'd) 9.6 PIPE SUPPORTS (cont'd) 9.6.4.2 Continuous Inserts (cont'd) Continuous steel " Gateway" inserts are provided for situations where the pipe is to be supported from concrete slabs and/or walls. A design load limit of 3000 lb, within any l'-0" section of the insert has been established. Point loading within the first 6" of the ends of any insert is to be avoided. 9.6.4.3 Self-Drilling Concrete Anchors Where it is not possible to erect supports per 9.6.4.1 or 9.6.4.2, steel plates may be attached to concrete structures by use of concrete expansion anchors. Acceptable anchor types and allowable load ratings are provided in Specification 3071-226. Threading of hanger rods directly to anchors that have been installed overhead is not permitted. A
positive method of providing a moment-free connec-tion must be used for attachment of hanger rods to the structure.
9.6.4.4 Floor Attachment All base plates of solid or spring stanchion sup-ports must be leveled and anchored to the struc-ture. 9.6.4.5 Support of Valve Motor Operators and By-Pass Piping All motor operators attached to valve stems must be supported independently of the pipe line supports. By pass or warmup piping around valves shall be supported from the main process pipe with appropriate supplemental supports. Consideration shall be given to insure that vibration of the by pass piping-relative to the main process can not occur. s-3071-525A.21
Specificcticn 3071-525 Rev. At 3-21-80 Prg2 16
- 9. COMPONENT DESIGN BASIS (cont'd)
- 9. 6 PIPE SUPPORTS (cont'd) 9.6.4.6 Seismic Supports Piping classified as ASME III, Class 3 (Group C),
Seismic II does not require seismic supports. Other piping within the scope of this specification requires restraint against uplift and sway during earthquake conditions. Computions of pipe line supports requiring seismic considerations must ensure that valve accelerations will be limited to 5.0 g horizontal and 3.0 g vertical (simultaneously) during the Safe Shut-down Earthquake (SSE) event. 9.6.4.7 Assembly of Supports Where possible, support and hanger assemblies shall be assembled using standard and production parts, completely prefabricated in the conventional designs of good engineering practices specified in the Ibnufacturers Standardization Society Guides SP-58 and SP-69. 9.6.5 Variable Spring and Mechanical Snubber Design O Variabie springs or mechanical snubbers shall be used at support or snubber locations where the calculated movement is in excess of .125" except where indicated below:
- 1) Variable springs or snubbers should be added to the first support or restraint located near equipment where the calculated movement in the direction of the load is in excess of .02 inches.
- 2) Variable springs or snubbers should be added to the first support or restraint located near pipe changes in direction where the calculated movement in the direction of the load is in excess of .06 inches.
O 3071-525A.22
Sp;cificatien 3071-525 Rav. A: 3-21-80 Peg 2 17
- 9. COMPONENT DESIGN BASIS (cont'd) 9.6 Pipe Supports (cont'd) 9.6.5 Variable Spring and Mechanical Snubber Design (cont'd)
Variable springs should have a spring variability factor equal to or less than the values shown in the table below: Spring Variability Selection Chart
~
System Pipe Runs At Nozzle Conn. QA Level 1, Class B & C 25% 25% All other systems 25% 25% Spring = Pipe travel (IN) x spring rate (lbs/in) Variability Operating (Hot) Load (lbs) 9.6.6 Pipe Supports
- a. Design Load:
The design load shall be taken as the algebraic sum of the dead weight, anchor deflection and seismic loads, combined in a manner consistant with the loading conditions specified in Article 11.0.
- b. Materials The selection of construction materials used in the design and fabrication of supports will be based on the conventional theory which gives a linear distribution of stress and strain in the elastic range up to the proportional limit.
9.7 System Line Valves All system line valves used in piping systems within scope of this specification shall be designed in accordance with the requirements of Edison Valve Specification 3071-12, or Edison Control Valve Specification 3071-26, and Design Specification 3071-501. f l 3071-525A.23 l l l I
.1- i
Specificati n 3071-525 Rsv. A: 3-21-80 Pcg2 18
- 9. COMPONENT DESIGN BASIS (cont'd)
O 9.8 Seismic Analysis of Piping Thermal Insulation Piping systems within the scope of this specification will be either uninsulated or will be insulated with approximately one inch of fiberglass insulation having an average density of 3 lb/f t 3, It shall be assumed for purposes of design that all pipes are insulated in order to conservatively maximize calculated piping system stress and support loading. 9.9 Seismic Analysis of Piping Piping designed to the requirements of this specification shall be seismically analyzed using a simple beam as the analytical model. The assumed seismic excitation shall be based upon the most energetic seismic response spectra for the building in which the piping is to be installed. Seismic restraints shall be designed and seismic spans determined such that the maximum fiber stress, in bending, does not exceed 7000 psi for the Operating Basis Earthquake (OBE) and 14,000 psi for the Safe Shutdown Earthquake (SSE). Additionally, the seismic restraints shall limit the deflection of the pipe to two inches during the SSE event, independent of stress level. Piping classified as ASME III, Class 3 (Group C), Seismic 11 does not O require seismic analysis, however, the applicable portions of paragraphs 9.10 and 9.11 will still apply. 9'.10 Consideration of Piping Flexibility Requirements The piping system shall be designed to limit the sum of the stress range variations due to thermal expansion and dif ferential terminal movement to 15,000 psi. Thermal expansion analysis shall be based upon the operating temperature of the piping system (process piping) and/or the operating temperature of the source connection (1&C tubing). For piping and tubing with an operating temperature of 150 F and below, no detailed thermal expansion analysis is required. 9.11 Dead Weight Analysis of Piping Dead weight analyses shall be conducted for all piping which is to be field designed to the taquirements of this specification. In conducting the dead weight analysis, the analytical model assumed shall be a simply-supported beam, subjected to a uniformly distributed load. 3071-525A.24 O t l
Specificatien 3071-525 Rev. A 3-21-80 Page 19 () 9. COMPONENT DESIGN BASIS (Cont'd) 9.11 Dead Weight Analysis of Piping (Cont'd) The analysis shall consider the weight of the pipe and its contents. All piping shall be assumed to be insulated, as specified in paragraph 9.8. Consideration shall be given to the inclusion of concentrated loads , such as valves , flanges, flow sections, etc. , to the piping spans between supports. Pipe support spacing shall be determined by analysis, so as to limit the maximum weight-induced bending stress to 3000 psi. The maximum allowable span between gravity supports on vertical pipe runs shall be three (3) times the values shown in Table B-1 of Sargent and Lundy Report SL-3159. On Seismic Class 11 Piping Systems a guide should be added between supports whose span is greater than two times the normal spans in Table B-1.
- 10. COHPONENT CHARACTERISTICS 10.1 Process Piping Characteristics
- a. Design Pressure: 1750 psig (maximum assumed for purpose of design).
l (~~) s_ b. Design Temperature: per the system Isometric Drawings
- c. Materials : Process piping materials and weights are listed in Appendix "A", Tables 1 and 2, as a function of ANSI pressure classification and material type. Pipe sizes may be determined from the System Process and Instrumentation Diagrams (Paragraph 6.2). ANSI pressure ratings and material !
types are determined by reference to the pipng fabrication (-1) drawing for the connected main process piping. 10.2 Instrumentation and Control Tubing and Piping
- a. Design Pressure: 1750 PSIG (maximum assumed for purpose of design)
- b. Design Temperature: per the system Isometric Drawings
- c. Material:
- 1. Class 2: (inside containment only)
Pipe - 3/4" SCH 80S Scamless - ASME SA 312, T316L A O 3071-525A.25 1
Specificcti:n 3071-525 R;v. A: 3-21-80 Pcg2 20
- 10. COMPONENT CHARACTERISTICS (cont'd) 10.2 Instrumentation and Control Tubing and Piping (Cont'd) O
- c. 1. Class 2: (inside containment only) (Cont'd)
Fittings: Socket welded 3000# ASME SA 182, Grade 316L Pipe - 1" SCH 160S - Seamless - ASME SA 312, T316L Fittings - Socket Welded, 6000# ASME SA 182, Grade 316L
- 2. Class 2 & 3: (outside primary containment)
Tubing - 5/8" x 0.083 Wall Seamless ASME SA 213, Type 304, 316 or 321 Tubing - 3/8" x 0.049 Wall Seanless ASME SA 213, Type 304, 316 or 321 Fittings - Socket Welded, 3000# ASME SA 182, T316 (shall be used with 5/8" tubing). Fittings - Compression, ASME SA 403, T316 Swagelok, Parker Hannifin or equivalent (shall be used with 3/8" tubing).
- d. Unique Characteristics:
To determine the size and class of instrument piping required refer to the Master Instrument List.
- 11. CLASSIFICATION OF CONDITIONS 11.1 Operating Conditons The operating conditions for the piping systems within the scope of this specification vary, and asy be determined from the applicable System Design Specification (Ref. 1). In no case do the operating conditions exceed the design conditons specified in Paragraph 10.1.
11.2 Earthquake Loadings For analysis of all Class 2 and 3 components the SSE shall be considered to occur concurrently with all other normal and transient loads, and the combination shall be considered as an emergency condition. One SSE shall be assumed to occur during the life of the plant. 3071-525A.26 O i i
Specificatien 3071-525 Rav. A 3-21-80 Pega 21
- 11. CLASSIFICATION OF CONDITIONS (cont'd)
O 11.2 Earthquake Loadings (cont'd) For the analysis of Class 2 and 3 components, the OBE shall be considered to occur concurrently with all normal and transient loads and the combination shall be considered as an upset condition. Two OBE's shall be assumed to occur during the life of the plant. All liquid-retaining piping is considered to be flooded at all times. Gas (air, steam) retaining piping shall be considered unflooded during all operating conditions. 11.3 Pipe Whip and Missile Impact Design criteria of the above nature is not part of this document or the stress analysis required by the ASME Code. The conditions are evaluated in a separate report. 11.4 Jet Impingement Loadings Piping within the scope of this specification does not require analysis for jet impingement loadings. 11.5 Pipe Break Criteria Analytical consideration of pipe breaks between the inner and outer ; isolation valves of Class 2 piping systems is not within the scope of this specification. The requirements for this analysis are given in the applicable system design specifications (Reference 1).
- 12. HYDROSTATIC AND LEAK TESTS 12.1 Process Piping and Connecting Instrumentation and Control Piping and Tubing Process piping and connecting Instrumentation and Control piping and tubing, up to, but not including connecting instruments, which carry steam or water during normal operating shall be hydro-statically tested prior to being placed in service.
Hydronatic testing shall meet the requirements of ASME III Subsection NC-6200. Valve bodies shall be in accordance with ANSI B16.5 or MSS SP-66 for Class 2 and 3 valves. The test pressures and temperatures shall be determined from the applicable system Design Specification (Reference 1). Prior to hydrostatic test, all system valves with leak off connections shall have the connections open-ended. Exercisable O 3071-525A.27 l
Specificcticn 3071-525 Ra y. A 3-21-80 Pcg2 22
- 12. HYDROSTATIC AND LEAK TESTS (cont'd) 12.1 Process Piping and Connecting Instrumentation and Control Piping and Tubing (cont'd) check valves shall be held open with the disc exercisor prior to and during the hydrostatic test. Those check valves which are not exercisable shall have the test pressure applied to the upstream side. System line valves er. cept those providing isolation between different pressure classes shall be open, but not backseated to provide full differential pressure against the stem packings.
During hydrostatic test, examination for leakage shall be made. There shall be absolutely no visible leakage on any of the pressure retaining components, including valve stem packings, relief valve seats and check valve exercising devices. The test medium shall be demineralized water. 12.2 Instrumentation and Control Piping and Tubing Not Connected to_a Process Barrier Process Piping and Instrumentation and Control Tubing which normally carries a gas, other than steam, shall be pneumatically tested prior to being put in service. Pneumatic testing shall be conducted in accordance with the g requirements of ASME III, Subsection NC-6300. W ' The test pressure shall be 150 psig. The test temperature shall be 60 F minimum, 100 F maximum. During the pneumatic test, all valves shall be open, but not backseated to insure that full test pressure is applied across the l stem packings. j During the pneumatic test, all piping and tubing joints and valve stem packings shall be coated with a soapy water solution. There shall be no evidence of bubble formation with the lines at full tes' pressure. The test medium shall be clean dry compressed air or nitrogen.
- 13. IN-SERVICE INSPFCTION The piping systems within the scope of this specification will not be subject to in-service inspection.
3071-525A.28
~
Specificati:n 3071-525 Rev. At 3-21-80 Page 23
- 14. REFERENCES
- 1. The Detroit Edison Company Sys tem Design Specifications, 3071-500 series.
3071-501 Nuclear Valves 3071-502 Core Spray System 3071-503 Residual Heat Removal System 3 071-504 HPCI System 3071-505 RCIC System 3071-506 Control Rod Drive System 3071-507 Standby Liquid Control System 3071-508 Reactor Water Cleanup System 3071-509 Fuel Pool Cooling System 3071-510 Feedwater System 3071-511 Steam Drain Sys tem 3071-512 Emergency Equipment Cooling Water Sys tem 3071-513 Of f-Gas Sys tem 3071-514 Reactor Refueling Bellows and Drywell Seal Bellows 3071-515 Reactor Primary Containment Electrical Penetrations 3071-516 Primary Containment Penetration Assemblies 3071-517 RHR Complex
- 3071-518 Essential Accumulators for Nuclear Class I Air Operated Valves 3071-519 Primary Containment and Reactor Building Equipment and Floor Drainage Sump Disposal Systems O- 3071-520 Station and Control Air Sys tem 3071-521 Liquid Radwaste Sys tem 3071-522 Reactor Drywell Cooling coils 3071-523 Reactor and Auxiliary Building Emergency Equipment Cooling Coils 3071-525 Field Designed Nuclear Class 2 and 3 Small Piping and Instrument and Control Piping and Tubing 3071-526 Hydrogen Recombiner Piping System 3071-527 Condenser Coils for Control Center Air Conditioning Sys tem Chillers ,
3071-528 Mechanical Seismic Shock Suppressors 1 3071-529 Miscellaneous Containment Interface Piping
- 2. "Small Pipe Design Standard" - Enrico Fermi Power Plant - Unit No. 2, l Satgent and Lundy Report No. SL-3159.
- 3. The Enrico Fermi Power Plant - Unit No. 2, Master Valve List.
- 4. BWR Equipment Enviro'imental Requirements General Electric Specification 22A3019,
- 5. The Edison Pipe Erection Specification 3071-31.
- 6. The ASME Boiler and Pressure Vessel Code, Section III,1971 issue.
O
\/
3071-525A.29
Specificsticn 3071-525 Ray. A: 3-21-80 Pego 24
- 14. REFERENCES (cont'd)
O
- 7. The Edison Pipe Fabrication Specification, 3071-30.
- 8. The ASME Boiler and Pressure Vessel Code, Section XI, 1974 issue.
- 9. The Edison Welding Specifications 311, 3071-98.
- 10. Edison Design Calculation No. 526, Enrico Fermi Power Plant - Unit No. 2.
- 11. The Edison Concrete Expansion Anchor Specification 3071-226
- 12. Edison Drawing SC721-2002.
- 13. Letter EF2-48,349 dated March 31, 1980.
O 3071-525A.3C
O I APPENDIX A ANSI Primary Pressure Rating, Materials and Dimensions for Nuclear Piping O O 3071-525A.31
l
. Al i TABLE I
() CARBON STEEL PIPING SYSTEMS ANSI ASTM ITEM PRESSURE RATING SIZE RATING TYPE SPECIFICATION Pipe 900 lbs 3" and Smaller Schedule 160 Seamless A106 Gr B 4" Schedule 120 Seamless A106 Cr B 600 lbs 3" and Smaller Schedule 160 Seamless A106 Cr B 4" Schedule 80 Seamless A106 Gr B 300 lbs 2" and Smaller Schedule 80 Seamless A106 Gr B 2-1/2" - 4" Schedule 40 Seamless A106 Cr B 150 lbs 2" and Smaller Schedule 80 Seamless A106 Gr B 2-1/2" - 4" Schedule 40 Seamless A106 Gr B Fittings 900 lbs 2" and Smaller 6000 lbs S.W. A234 Gr WPB - 2-1/2" - 4" Match Pipe Wall B.W. A234 Gr WPB ( }) 600 lbs 2" and Smaller 3000 lbs S.W. A234 Gr WPB 2-1/2" - 3" Schedule 160 B.W. A234 Gr WPB 4" Schedule 80 B.W. A234 Gr WPB 300 lbs 2" and smaller 3000 lbs S.W. A234 Gr WPB 2-1/2" - 4" Schedule 40 B.W. A234 Gr WPB 150 lbs 2" and Smaller 3000 lbs S.W. A234 Gr WPB 2-1/2" - 4" Schedule 40 B.W. A234 Gr WPB Valves 900 lbs 2" and Smaller 1500 lbs S.W. A105 2-1/2" - 4" 900 lbs B.W. A216 Gr B 600 lbs 2" and Smaller 600 lbs S.W. A105 600 lbs B.W. A216 Gr B 300 lbs 2" and Smaller 600 lbs S.W. A105 2-1/2" - 4" 300 lbs B.W. A216 Gr B 150 lbs 2" and smaller 600 lbs S.W. A105 2-1/2" - 4" 150 lbs B.W. A216 Gr B
- continued -
3071-525A.32 l 1
A2 TABLE I CARBON STEEL PIPING SYSTEMS (cont'd) h ANSI ASTM ITEM PRESSURE RATING SIZE RATING TYPE SPECIFICATION Flanges 900 lbs 2" and smaller 1500 lbs SW, RF A105 2-1/2" - 4" 900 lbs WN, RF A105 600 lbs 2" and Smaller 600 lbs SW, RF A105 2-1/4" - 4" 600 lbs WN, RF A105 300 lbs 2" and Smaller 300 lbs SW, RF A105 2-1/2" - 4" 300 lbs WN, RF A105 150 lbs 2" and Smaller 150 lbs SW, RF A105 2-1/2" - 4" 150 lbs WN, RF A105 Bolts All Bolt Studs A193 Gr B7 Hex A194 Gr 2H O Nuts All Caskets All Flexitallic Style CG 3071-525A.33 9
A3 TABLE 2 STAINLESS STEEL PIPING SYSTEMS
~
ANSI ASTM ITEM PRESSURE RATING SIZE RATING TYPE SPECIFICATION Pipe 900 lbs 3/4" Schedule 80S Seamless A312TP304 or 316L 1" - 2" Schedule 160S Seamless A312TP304 or 316L 2-1/2" & 3" Schedule 160S Seamless A376TP304 or or Seamweld A358TP304 600 lbs 2" and Smaller Schedule 80S Seamless A312TP304 2-1/2" - 4" Schedule 80S Seamless A376TP304 or or Seamweld A358TP304 300 lbs 2" and Smaller Schedule 40S Seamless A312TP304 2-1/2" - 4" Schedule 40S Seamless A376TP304 or or Seamweld A358TP304 150 lbs 2" and Smaller Schedule 40S Seamless A31?TP304 or or O 2-1/2" - 4" Schedule 10S Seamweld A358TP304 Fittings 900 lbs 2" and Smaller 3000 lbs S.W. A182 Gr F304 or 316L 2-1/2" & 3" Schedule 160S B.W. A403 Gr WP304 4" Schedule 120S B.W. A403 Gr WP304 600 lbs 2" and Smaller 3000 lbs S.W. A182 Gr F304 2-1/2" - 4" Schedule 80S B.W. A403 Gr WP304 300 lbs 2" and Smaller 2000 lbs S.W. R2 Gr F304 2-1/2" - 4" Schedule 40S B.W. 3 Gr WP304 150 lbs 2" and Smaller 2000 lbs S.W. A182 Gr F304 2-1/2" - 4" Schedule 10S B.W. A403 Gr WP304 2-1/2" - 4" Schedule 40 B.W. A234 Gr WPB Valves 900 lbs 2 and Smaller 1500 lbs S.W. A182 Gr F304 or 316L 2-1/2" - 4" 900 lbs B.W, A351 Gr CF8M 600 lbs 2" and Smaller 600 lbs S.W. A182 Gr F316 2-1/2" - 4" 600 lbs B.W. A351 Gr CF8M I 300 lbs 2" and Smaller 300 lbs S.W. A182 Gr F316 gx 2-1/2" - 4" 300 lbs B.W. A351 Gr CF8M
\- 150 lbs 2" and Smaller 150 lbs S.W. A182 Gr F316 2-1/2" - 4" 150 lbs B.W. A351 Gr CF8M 3071-525A.34 - continued -
, _ _ 1
A4 TABLE 2 STAINLESS STEEL PIPING SYSTEMS (cont'd) h ANSI ASTM ITEM PRESSURE RATING SIZE RATING TYPE SPECIFICATION Flanges 900 lbs 2" and smaller 1500 lbs SW, RF A182 Gr F304 or 316L 2-1/2" - 4" 900 lbs WN, RRF A182 Gr F304 600 lbs 2" and Smaller 600 lbs SW, RF A182 Gr F316 2-1/4" - 4" 600 lbs WN, RF A182 Gr F316 300 lbs 2" and Smaller 300 lbs SW, RF A182 Gr F316 2-1/2" - 4" 300 lbs WN, RF 182 Gr F316 150 lbs 2" and Smaller 150 lbs SW, RF A182 Gr F316 2-1/2" - 4" 150 lbs WN, RF A182 Gr F316 Bolts All Bol t St ud s Bolt Studs A193 Gr B7 Hex A194 Gr 2H O Nuts All Gaskets All Flexitallic Style CG 3071-525A.35 i 4 III
. = - . _. ,_ _. . - . . - _ _ . _ _ _ _ _ _ _ - _ _ _
m -m-o-o m-si-w3 . Title DERGENCY EQUIPMDIT COOLING WATER (EEI;W) SYSTEM ENRICO FERMI POWER PT ANT; MTT 2 Project Design Specification O Deholt Edison 3071-512 Including Addendum A Number DECDGER 1972 DECEMBER 1974 Date
Specifiestion 3071-512 DETROIT EDISON Prripared By SPECIFICATION Enrico Fermi II ADDENDUM "A" 3*" "*9 " " Organization O' DESIGN SPECIFICATION nue : 11-15-74 FOR EMERGENCY EQUIPMENT COOLING WATER SYSTEM Enrico Fermi Atomic Power Plant Unit #2 i APPROVAL SHEET DATE ^ j
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WRITTEN BY: ( . M 4 7U.O D. LEHNERT CHECKED BY:
. (v / 2 ' / { ! 7 8-/
h F.El GREGOR -P.E. APPROVED: d' PROJ. ENG'G. ,P j 4 .. f, p GROUP SUPERVISOR ,; 6 '
,, LA-g EcJ / /2-G 74-v M. S IGET ICt+'
I APPROVED:
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ASSIST. PROJECT , ENGINEER, SYSTEMS f g //r /;.%f W.F. COLBERT-P.E. / / APPROVED: EN R 2 , u /s/,2/7/ E.G.(gIPER-P.E. O
Specification 3071-512 Prepared By Enrico Fermi II Project Management Organization O Issued: 11-15-74 Addendum "A" P44 0-000 sA,002/ DETROIT EDISON DESIGN SPECIFICATION FOR ENRICO FERMI ATOMIC POWER PLANT UNIT NO. 2 ADDENDUM "A" 0F DESIGN SPECIFICATION FOR EMERGENCY EQU1PMENT COOLING WATER SYSTEM DESIGN SPECIFICATION NO. 3071-512 o .
~
Specification 3071-512 Issurd: 11-15-74 O oeTao'T co'So" DESIGN SPECIFICATION ADDENDUM "A" EMERGENCY EQUIPMENT COOLING WATER SYSTEM
- 1. On Page 2, delete Article 3. (h),
- 2. On Page 2, Article 4.3, revise to read:
The Installer of the System shall be designated by The Detroit Edison Company ,
- 3. On Page 3, Article 4.8, revise 2nd sentence to read:
The Stress Report for the piping components will be provided by the Owner's engineering organization or designated agent.
- 4. On Page 4, Article 5, revise coolant demands to read:
(1) Reactor Recirculating Pump (2) Residual Heat Removal Pumps (2) Core Spray Pumps O (4) - (5) - sPece cooiers: (i) aesideei seet aemevei (1) Core Spray and Reactor Core Isolation Cooling (1) Emergency Equipment Cooling Water Room (1) Hydrogen Control System or (1) High Pressure Cooling Injection (1) Core Spray (1) Residual Heat Removal (1) Emergency Equipment Cooling Water Room (1) Hydrogen Control System (1) Air Conditioning Equipment Unit for the Control Room (2) Switch Gear Room Space Coolers (1) Standby Control Air System (1) Standby Gas Treatment Room Space Cooler (7) Drywell Coolers. O
. Specification 3071-512 Issurd: 11-15-74 Addendum "A" Page 2 O 5- o# e 9 4. ^rtic' 5 r vis 4th P r ar P8 t= < d:
The EECW system, supplying the above equipment, maintains a condensate de-sign temperature of 95 F by heat rejection loop heat exchangers, which are cooled by Emergency Equipment Service Water (see Design Specification 3071-517).
- 6. On Page 5, Article 5, revise the ist and 2nd paragraphs to read:
During normal plant operation, it is essential to test the operation of the EECW system to confirm that the pumps, heat exchangers, make-up tanks and isolation valves will operate as specified wl.an required. Each divi-sion of the System will be individually tested by isolating the division from the RBCCW system by use of the motor operated valves. A complete flow diagram is shown on the Process and Instrumentation Dia-gram Number 6M721 -2027.
- 7. On Page 7, Article 8.2, revise 2nd paragraph to read:
Dimensional standards for fittings shall be per ANSI Bl6.9, unless other-wise specified on the Piping Isometric Drawings.
- 8. On Page 7, Article 9.1, revise ist sentence to read:
The penetration assemblies shall be designed, manufactured, tested and
- Inspected in accordance with Design Instruction DI-2 and Edison Design ! Speci ficat ion 3071-516.
- 9. Page 7, Article 9.1, revise seismic displacements to read:
The horizontal displacement in X or Z direction for GBr. = 1 .012 inches and for the DBE = 1 .0172 inches. The vertleal displacement for the OBE = .00156 inches and for the DBE = t .0024 inches.
- 10. On Page 8, revise Article 9.3 to read:
Piping of above category, which connects to EECW System piping inside the primary containment up to and including the first source valva is classi-fled as Class 2. Piping beyond the source valve up to and including the ter-minal or instrument is classified as Class 3. This piping shall be design and stress analyzed in accordance with Edison Design Specification 3071- 525 O
. Sp;cification 3071-512 Issurd: 11-15-74 Addendum "A" Page 3 O II. On Page 8, revise Article 9.4 to read:
The pumps, heat exchangers and make-up tanks are classified as Class 3 components. Piping connections to these components shall be designed to limit reactions to the following limits: (a ) . For the pump, the allowable nozzle loads shall be governed by the following expression: FI + Mi / 1 Fo Mo Where: F; = the largest of the three actual external orthogonal forces (Fx, F y, and Fz) that may be imposed by the pipe. 1 M; = the largest of the three actual external orthogonal moments. (Mx. M y , and M 2 ) permitted from the pipe , l when they are combinep + simul conditlon. M2+ taneous gz2 ) ) y for any (Mt = { Mx y l Fo = the allowable of F; when all moments are zero. No = the allowable value of M; when all forces are zero. 5 The values of Fo and No are given below: l OBE DBE Fo Ho Fo Mo Lbs. Ft-Lbs. Lbs Ft-Lbs Combined Resultant i168 2340 1500 3000 Suction Nozzle 875 , 1250 1125 , 1575 Discharse Nozzle 1000 l 2000 l 1275 1 2550 (b) For the heat exchanger, the allowabie nozzle loads are given in the
'ollowing tables:
NORMAL & UPSET CONDITION (OBE) Service Water Service Water EECW EECW Inlet Outlet Inlet Outlet Div. I Div. II Div. I Div. II Div. I Div. II Div. I Div. II Fx 680 260 1600 1500 700 700 680 500 hrz 3800 2200 2400 600 175 770 1100 1300 1600 700 1000 400 550 200 400 200 Mx 3950 3400 2500 5500 3200 1300 700 500 My 2100 600 1100 6900 1000 800 1750 1000 Hz 2200 200 3850 7300 3500 3200 1500 400
Sp;cification 3071-512 Issu:d: 11-15-74 Addendum "A" Page 4
) EMERGENCY C0!4DITION (DBE)
Service Water Service Water EECW EECW Inlet Outlet Inlet Outlet Div. I Div. II Div. I Div. II Div. I Div. II Div. I Div. II i
' 1100 1100 800 Fx 1250 400 j 2600 3000 1000 ,
Fy 7300 4500 300 2100 2500 1700 . 600 600 Fz 4200 1200 1300 2500 1300 600 l 400 300 l Mx 7800 6600 l 3600 l 10,300 1 6200 2500 1100 900 My 3600 1000 2000 14,000 1500 1200 i 2600 1600 Hz 3800 300 6300 2100 5000 1700 2400 700 l a Force in Ibs Moment in ft-lbs (c) For the make-up tanks, the allowable nozzle loads are given in Figures 3 thru 5. O Seismic displacements for the DBE are given in global coordinate form where x is east, z is south and y is vertical. The three displacement components 9 of the three mutually perpendicular directions of excitations are expressed . In inches and represent the square root of the stan of the squares of the I displacements of the vibratory modes. The pump, heat exchanger and make-up i tank nozzle connections shall be rigid anchor points for pip'ng. This equip- l ment is subject to sesimic displacements of the supporting floor slab. The anchor movements are as follows: Horizontal Displacement, OBE = .0302 in. DBE = .0442 in. Vertical Displacement, OBE = .00312 in. DBE = .00468 in. End thermal movements of the heat exchanger and make-up tank will be con-sidered as zero because of the negligible temper ature change.
- 12. Oa Page 11, Article 9.7, revised first sentence to read:
Class 2 and 3 piping 5 inch NPS and larger shall be analyzed by use of a 1 multi-degree of freedom dynamic modal response method.
- 13. On Page 12, Article 9.7, 3rd paragraph, revise 1st sentence to read:
p The multiplier for the DBE shall be taken as 1.875 (minimum). O
1 , Sp;ci ficat ion 3071-512 Issued: 11-15-74 Addandum "A" Page 5
- 14. On Page 12, Article 9.7, revise 4th paragraph to read:
Class 2 and Class 3 piping 4" NPS and smaller shall be analyzed per Edison Speci ficat ion 3071- 525. ;
- 15. On Page 13, Article 9.8, revise the seis.nic displacements to read:
Horizontal Displacement, OBE = .0218 in. DBE = .0397 in. Vertical Displacement, OBE = .00312 in. DBE = .0D468 In.
- 16. On Page 13, Article 9.9, revise the seismic displacements to read:
For the Core Spray System and Residual Heat Removal System Pumps; the Core Spray and Reactor Core Isolation Coolant, Residual Heat Removal and High Pressure Cooling Injection Space Coolers, (sub-bas ement ) : Horizontal Displacement, OBE = .0128 in. DBE = .023 in. Vertical Displacement OBE = .00156 in. DBE = .0024 in. For the Standby Control Compressor, (First Floor), O Horizontal Displacement, OBE = .012 in. DBE = .0172 in. Vertical Displacement, OBE = .00156 In. DBE = .0024 in. For the EECW and Switch Gear Room Space Coolers (Third Floor), Horizontal Displacement, OBE = .0416 In. DBE = .0596 in. Vertical Displacement, OBE = .0042 in. DBE = .00624 in.
- 17. On Page 14, Article 9.9, revise the seismic displacements to read:
For the Switch Gear Space Coolers and the Hydrogen Control System Space ! Coolers, (Fourth Floor), l Horizontal Displacement, OBE = .0 475 in. DBE = .0 676 in. Vertical Displacement, OBE = .00467 in. DBE = .00684 in. O I l i
.' l t' Spscificaticn 0071-512 Issurd: 11-15-74 l Addendum "A"
. Page 6 O 17. On Page 14, Article 9.9, revise the seismic displacements to read: (con t inued)
For the Control Room Air Conditioning Equipment and the Standby Gas Treatment Space Cooler, (Fif th Floor), Horizontal Displacement, OBE = .0552 in. DBE = .0762 in. Vertical Displacement, OBE = .00528 in. DBE = .00768 in. l
- 18. On Page 14, Article 10.0, delete reference to 350 F for design temperature of Class 2 piping.
i
- 19. On Page 16, Article 11.1, Cooling Water Supply Line Temperature shall be 850F. j
- 20. On Page 17, Article 13 (1), revise to read: l Seismic Analysis of the Enrico Fermi #2 Reactor Buildirg, Sargent and Lundy Report #5L-2682.
- 21. On Page 17, Article 13, add the following:
s (14) Stress Report, RGFA-NABC-72-190, Emergency Equipment Cooling s Water Make-Up Tank Seismic and Nozzle Loads, for National e Annealing Box Company. (15) Seismic Stress Analysis. Emergency Equipment Cooling Water Heat Echanger, Yuba Reference 72-N-001. 4 (16) Certified Seismic Analysis Report of Crane Deming Horizontal Split Case Pump, Figure 5063 for Emergency Equipment Cooling Water Pump. O V
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e 9 4 9 THE DETR0li EDISON COMPANY :PecaicAfiO= 3071-512 sec,...- .. ::::::= ,, PROJtcT WAmAGEutu? ORG ANIZ Afl04 SYSTEM DESIGN SPECIFICATION Issued: 9-6-72 FOR EMERGENCY EQUIPMENT (X)0 LING WATER SYSTEM Enrico Femi Atomic Power Plant Unit #2 APPROVAL SHEET l l DATE l
/Ib,162//7i/ J t ~b WRITTEN BY: ('N Di LEHNERT ,
CHECKED BY: 'tf W
) .E. GREGOR hO#
l' ( h-7 APPROVED: PROJ. ENG'G Ih - GROUP SUPERVISOR /'/M/hf.Y P.E. M ~ N' b S.H1 NOIG!CZ V APPROVED: PROJECT SYSTEM ENGINEER
, g - ? '"/[ /C -80 ,"f W.'F. COLBERT P.E.
REVIEWED: QUALITY ASSURANCE , h3nr h , ,, c ]y DIRECTOR bh I ' if a JLll \ k QM - N
- l- b /"
A. ALEXIOU APPROVED: PROJECT ENGINEER h)h. 1 b ' 'y l 2 ~ h R.A. VAhCW.E . l .
- Specification No. 3071-512 ,
Iccued: 9-6-72 ) l O i P44-00C0CO&oo$ THE DETROIT EDISON COMPANY r SPECIFICATION i SYSTEM DESIGN SPECIFICATION FOR
- EMERGENCY EQUIPMENT COOLING WATER SYSTEM l o- ENRICO FERMI ATOMIC POWER PIANT UNIT #2 I
i i O
-\
W .
THE DETROIT EDISON COMPANY settineAfion 3071-512 spaCIPICATION " fCo E isi si P90 JECT MANAGEMENT SYSTEM DESIGN SPECIFICATION '",*7' 7 *,'y'" 9-6 -72 FOR EMERGENCY EQUIPMENT COOLING WATER SYSTEM ENRICO FERMI ATOMIC POWER PIANT UNIT #2 INDEX Article Code Article Page
- 1. SC0PE.......................... NA-3250................ 1 2 CERTIFIO4 TION.................. NA-3250................ 1
- 3. C1 ASS IF ICATION . . . . . . . . . . . . . . . . . NA-2000................ 1 4 DOCUMENTATION . . . . . . . . . . . . . . . . . . NA-3256................ 2
- 5. GENERAL SYSTEM DESCRIPTION..... NA-3252 (a)........... 4
- 6. APPLICABLE DOCUMENTS . . . . . . . . .. . NA-3254................ 5
- 7. DESIGN......................... NA-3252 (b)........... 5
- 8. SYSTEM DESIGN BASIS...................................... 7
- 9. COMPONENT DESIGN BASIS................................... 7 Os 1.0 COMPONENT CHARACTERISTICS................................ 14
- 11. CIASSIFICATION OF CONDITIONS . . . . . NA-2140. . . . . . . . . . . . . . . . 16 12 HYDROSTATIC AND LEAK TESTS . . . . . . . NC-6000. . . . . . . . . . . . . . . . 16
- 13. REFERENCES............................................... 17 ATTACHMENTS:
Process Diagram 6M721-2027 Systems Isometric (See References) Boundaries of Code Jur'sdiction Figure #1 4 Local Coordinate System and Convention Figurc #2 Appendix A - ANSI Primary Pressure Rating, Materials and Dimensions i for Nuclear Piping. l i l h O* I l t
^
Sptcification: 3071-512 Issued: 9-6-72 t o THE DETROIT EDISON COMPANY d DESIGN SPECIFICATION SYSTEM DESIGN SPECIFICATION FOR EMERGENCY EQUIPMENT COOLING WATER SYSTEM
- 1. SCOPE This document constitutes the Design Specification required by Article NA-3250 of the ASME Boiler and Pressure Vessel Code Section III, 1971 Issue " Nuclear Power Plant Components" for the Emergency Equipment Cooling Water Piping System to be installed as part of the Nuclear Steam Supply System of the Enrico Fermi Atomic Power Plant, Unit #2.
- 2. CERTIFICATION The undersigned registered Professional Engineer competent in the field of design of piping and related nuclear energy system requirements, certifies that this design specification together with the referenced documents complies with the requirements of Article NA-3250 of the ASME-Code Section III and is correct and complete with respect to functions and operating conditions as required to provide a complete basis for design, construction and certified inspection in accordance
() ' with the Code. 7- 3i- n DATE
//tb n SIGNAIURE Michigan - 18860 BRANCH REGISTRATION, STATE and NUMBER or SIAMP
- 3. CIASSIFICATION (
REFERENCE:
FIGURE #1) The Emergency Equipment Cooling Water (E.E.C.W.) System is divided into two classes. That portion of the E.E.C.W. System supply and return piping which is between the outboard containment isolation valve and the equipment inside the primary containment that requires cooling water shall be classified as a Class 2 system and shall be designed and constructed in accordance with the rules of Subsection NC of the ASME Code Section III,1971 Issue. .O-
Speelfication: 3071-512 Icsued: 9-6-72 Page Two b_qk. 3. CIASSIFICATION (
REFERENCE:
FIGURE #1) (Continued) The remaining portion of the system shall be classified as a Class 3 system and shall be designed and constructed in accordance with the rules of Sub-section ND of the ASME Code Section III, 1971 Issue. The purchase order dates for the components are as follows: (a) Line Valves : July 19, 1971, The Wm. Powell Company (b) Piping and Fittings : March 29, 1972, Dravo Company (c) Penetration Assembly : Spet. 15, 1970, Tube Turns Company (d) Hangers and Supports : Aug. 24, 1971, Power Piping Company (e) Pumps : June 14 , 1972, Crane Deming Pumps (f) Heat Exchangers : Oct. 30, 1972, Yuba Heat Transfer Corp. (g) Make-up Tanks : July 31, 1972, National Annealing Box Co. (h) Inservice Inspection : , W10, Southwest Research Inst.
- 4. DOCUMENTATION
- 1. The Owner and User of the System will be:
THE DETROIT EDISON COMPANY 2000 Second Avenue Detroit, Michigan 48226
- 2. The System will be installed in the:
ENRICO FERMI ATOMIC POWER PIANT, UNIT #2 6400 Dixie Highway Stony Creek, Monroe County, Michigan 48166 (P. O. Newport, Michigan)
- 3. The Installer of the System will be:
THE RALPH M. PARSONS COMPANY of MICHICAP Post Office Box 300 Monroe, Michigan 48161
~ , . l Specificatien; 3071-512 l Iscu:d: 9-6-72 l Page Three
{ (f 4. DOCUMENTATION (Continued) 1
- 4. The Enforcement Authority having jurisdiction at the location of the System is:
THE STATE OF MICHIGAN DEPARIMENT of IABOR ; BUREAU of SAFETY and REGUIATION DEPARTMENT of IABOR BUI1 DING 300 E. Michigan Avenue Lansing, Michigan 48913
- 5. Consnunications between the installer or manufacturer and the enforcement authority will be through the Owner unless specifically !
required by the Code to be otherwise. In the latter case, prior l approval must be obtained and advance copies of the correspondence j directed to the Owner's documentation office and the certifying l Professional Engineer (s) of this document. 1
- 6. The Owner will comply with Article NA-3256 in filing a copy of this Design Specification with the enforcement authority before the system is placed in service.
- 7. The manufacturer and/or installer shall identify the authorized In-spection Agency to the Owner on or before the contreet date and
{}. shall provide the Inspection Agency with all required documentation, including the Quality Assurance Manual and this Design Specification.
- 8. The Stress Report shall be submitted to the Owner, before filing with the required authorities for review by those responsible for the Design Specification as required per NA-3260. The Stress Report for the piping components will be provided by the Owner's engineering organization or designated agent and submitted to the manufacturer. The Owner will certify that the required review has been conducted and will make available a suitable insert page for inclusion into the Stress Report before it is filed with the enforce ment authority by the manufacturer.
- 9. Each manufacturer and/or installer shall furnish the Owner with a copy of the appropriate Certificate of Authorization not later than the date of contract, (Article NA-3330).
- 10. Upon completion of the contract each manufacturer and/or installer shall complete the appropriate certificate of Compliance and submit a copy of the Certificate to the Owner for inclusion in the Owner's Data Report Form N-3, (Article NA-3270).
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Specification: 3071-512 Issu:d: 9-6-72 Page Four ()[ 5. GENERAL SYSTEM DESCRIPTION (This is a functional description and not a design requirement). The E.E.C.W. System consists of two redundant supply and return cooling loops, Division I and Division II. Each loop will consist of one e condensate circulating water pump of sufficient capacity to circulate water thru the system and return the cooling water to a full capacity t heat exchanger. The E.E.C.W. System will be automatically operable upon a loss of A-C off-site power or may be manually initiated on system failure of the Reactor Building Closed Cooling Water System. The E.E.C.W. System will at all times meet the requirements to provide sufficient water at the proper pressure and maximum temperature. In the case of a failure of a single component of one of the Divisions, the other Division will be capable of supplying coolant to the following equipment. (1) - Reactor Recirculating Pump (2) - Residual Heat Removal Pumps (2) - Core Spray Pumps (2) - (3) - Space Coolers: (1) - Residual Heat Removal O (1) - Core Spray and Reactor Core Isolation Cooling (' or (I) - High Pressure Cooling Injection (1) - Core Spray (1) - Residual Heat Removal (1) - Air Conditioning Equipment Unit for the Control Room (2) - Switch Gear Room Space Coolers (1) - Standby Control Air Systen (I) - Post Loss of Coolant Accident, Hydrogen Control System (1) - Standby Gas Treatment Roort Space Cooler I (2) - Drywell Coolers The E.E.C.W. System, supplying the above equioment, maintains a condensate temperature of 95 F by heat rejection loop hea exchangers, which are cooled by Emergency Equipment Service Water (see Design Specification 3071-517) The E.E.C.W. System make-up tank is used as the source of system water make-up. Condensate is supplied from the condensate storage tanks. The make-up tank will be nitrogen capped to prevent leakage of oxygen into the system and to maintain a positive suction head on the closed loop
- l. system.
l h V s
Specificction: 3071-512 Issurd: 9-6-72 Page Five [ 5. GENERAL SYSTEM DESCRIPTION (Continued) During normal plant operation the E.E.C.W. System will be tested once a month. Each division of the System will be Individually tested by isolating the division from the R.B.C.C.W. System by use of the motor operated valves. The test will be perfortred to assure that the division pumps, heat exchangers, make-up tanks and Isolation valves w*ll operate as specified when required. A complete flow diagram is attached in the Appendix, see Process and In-strumentation Diagram Number 6M721-2027
- 6. APPLICABLE DOCUMENTS The design, material, fabrication, Installation, inspection and testing of the system and the system components shall be in accordance with the
- following
1 This Specification with the attachments.
- 2. The Process and Instrumentation Diagram 6M721-2027.
- 3. The Piping Stress Analysis Isometric (See References).
Oi
- 7. DESIGN 7.1 System Design Life The system shall be designed for an effective design life of 40 years, accounting for corrosion, erosion and fatigue. The corrosion allow-ance to be used Is:
0.120" for steam 0.080" for water 0.0024" for stainless steel 7.2 Normal and Upset Environmental Conditions The Class 2 portion of the system, situated in the primary containment will be exposed to the following condition during the life of the plant: External Pressure = 0.0 to 2.0 PSIG External Temperature = + 105 to 1500F (Range) O. Reiative tiemiditv = 40 to sex Atmosphere = 97% N , 3% 0 2 2 External Radiation = Gamma 50 Rads / Hour 2 Neutron 140,000 N/CM - Sec.
t . Specifiestion: 3071-512 Issu;d: 9-6-72 Page Six h 7 DESIGN (Continued) 7.2 (Continued) All Class 2 components are insulated with an all metal reflective type insulation having a heat loss coefficient of approximately 0.15 BTU /HR/Sq. Ft/0 F/ Inch thickness. For the purpose of thermal analysis, this Insulation shall be assumed to be pe-fect (no heat loss). 7.3 Faul ted Environmental Conditions in Drywell (or.e time only) External Pressure =
-2 to 56 PSIG for i minute at 340 F
-2 to 35 PSIG for 3 r.ours at 3400F ,
-2 to 35 PSIG for 6 hours at 3200F 0 to 25 PSIG for i day at 250 F j 0 to 20 PSIG for 100 days at 2000F Relative Humidity = 107/o Radiation = 2.6 x 107 RADS (gamma) 7.4 System Fluid The system will contain the following fluid:
( Medlum: Demineralized Water pH at 25 C: 6.5 to 7.5 Radioactivity: 0.7 Micro Curle/ml @ zero decay time Specific conductivity, mho/cm @ 250c <0.1 Chloride as Cl- <2 ppb Total metallic impurity <10 ppb Silicia as S102 <5 ppb ! l 7.5 Environmental Conditions of Secondary Containment The Class 3 portion of the system, situated in the secondary contain-ment will be subjected to the following conditions: External Pressure = Atmospheric External Temperature = Winter Minimum of 400F Accidental Maximum of 1480F (for 8 hours) Average Operating of 70 F Relative Humidity = 50 to 9&4 Radia t Ion = 7 9 x 10 5RADS (gama - includes faulted dose)
Specification: 3071-512 Issued: 9-6-72 P:;ge Ssven f 8. SYSTEM DESIGN BASIS t i V 8.1 Cold Springing Cold springing is not permitted in the design of the piping. In cases where mismatches due to fabrication tolerances exist during the instal!ation, the procedures for measuring and closing the gap giver in the syste:r. erection specification will be followed. 8.2 Dimensional Limits Piping components shall be fabricated in accordance with the Fabri-cation Specification 3071-30 and the fabrication tolerances shall be per P.F.I. Standard ES-3. Dimensional standards for fittings shall be per ANSI B16.9. 8.3 Temperature Limits The metal and fluid temperature for cleaning, flushing and decon-taminating shall be above + 600F, but not exceeding 2120F for the entire system (Class 2 and Class 3).
- 9. COMPONENT DESIGN BASIS 9.1 E.E.C.W. Penet ration Assembl ies (X-23, x-24 and x-34 A,B)
! The penetration assemblies shall be designed, manufactured, tested and inspected in accordance with Design Instruction DI-2 The stress analysis shall employ a finite element analysis method for the flued head as defined in Appendix A of DI-2 The flued head constitutes a rigid anchor for the attached piping and allows only for normal thermal expansion of the flued head.
The anchor movements are as follows: Seismic Displacement: The horizontal displacement in X cr Z direction for the OBE = i .012 inches and for the DBE - I .022 inches. The vertical displacement for the OBE = ? .0084 inches and for the DBE = t .016 inches. Thermal Movements: In the normal condition the movements of the penetration assembly will be due to vertical and horizontal expansion from 70 0F to 150 F and pressure expansion from 0 to 2 psig of the primary containment. Y Horizontal Displacement =
.327 in j (O
Vertical Displacement =
.045 in
Specification: 3071-512 Issu;d: 9-6-72 Page Eight 9. ( }{ COMPONENT DESIGN BASIS (Continued) 9.1 (Continued) In the accident condition the movement of the penetration assembly will be due to vertical and horizontal expansion from 700F to 3400F and pressure expansion from 0 to 56 psig of the primary containment. The movements shall be as follows: Horizontal Displacement =
.539 in Vertical Displacement =
.170 in Piping reactions acting on either side of the flued head shall be calculated for the local coordinate data points located at the con-nection weld and reported as part of the Piping Stress Report.
The flued head anchor is subject to seismic displacements of the containment shield. 9.2 Class 2 System Line Valves and Isolation Valves All valves shall be designed, manufactured, tested and inspected in accordance with Edison's Valve Specification 3071-501 and 3071-12. 9.3 Piping of 3/4" NPS and Smaller and Instrument Piping Piping of above category, which connects to E.E.C.W. System piping Inside the primary containment up to and including the first source valve is classified as Class 2 and shall be designed in accordance with A.S.M.E. Section III,1971 Edition. Piping beyond the source valve up to and including the ter-inal or instrument is classified as Class 3 and shall be designed in accordance with ANSI B31.1 " Power Piping", Paragraph 122.3, includ-Ing the application of ANSI B31 Code Case 78. Only seamless stainless steel or carbon steel tubine full stress relieved may be used for source connections. Cold forming, tending flaring etc. is not permitted. 9.4 E.E.C.W. System Pumps, Heat Exchanger and Make-up Tanks The pumps, heat exchangers and make up tanks are classified as Class 3 components. Piping connections to these components shall be designed to limit reactions to the following limits: Based on the moment of inertia and the moment arm of reactions, the pump casing and the shell of the heat exchanger and the make-up tank are assuned to accept and transfer their respective loads to their anchor bolts, which present the weakest link. React ions are therefore limited based on the strength of the bolts.
Specification: 3071-512 Issu:d: 9-6-72 Page Nine i OJ' V '
- 9. COMPONENT DESIGN BASIS (Continued) 9.4 (Cont'd)
The stress report shall verify the following formulae: (a). For the Pump, (1). Maximum Bending Moment l 6(Fyj + FY2) - 10.5(FZ1 + FZ2} + "X1 - "X2l ( (Later) and l10.5(F X1 -F X2) - 1.5 Fyj + 25.5Fy2 + MZ1+"Z2l$(Later) (2). Maximum Shear Moment l19(F X2 -F ~M
) - 14FZ1 + 13FZ2 Y1 ~MY d ( %d Where, Fj and M yare the forces and moments imposed on the suction nozzle of the pump and, F and M are the 2 2 forces and moments imposed on the discharge nozzle of the pump.
(- (b). For the Heat Exchanger, (1). Maximum Bending Moment l46(FX2 + FX3) + 12(7(Fyj -F Y2) + 5(Fyg - Fy3))+ MZ1 + "Z2
+M73 + M74l ( (Later) 1 and l13.5(-F;+FY2 y + Fy3 -F yg) + 46(FZ2 + FZ3 ~ X1 - X2
~ "X3 - X4 (Later)
(2). Maximum Shear Moment l-219(FZ1 + Z2)- 195(FZ3 + FZ4) + "Y1 ~ "Y2
-My3 + Myql((Later) i l
l
Specification: 3071-512 Issusd: 9-6-72 Page Ten
- 9. COMPONENT DESIGN BASIS (Continued) 9.4 (Cont'd)
(2). Maximum Shear Moment (Cont'd) Where, Fj and Mj are the forces and moments imposed on the tube side inlet nozzle of the heat exchanger, F 2 and M2 are the forces and moments imposed on the tube side outlet nozzle of the heat exchanger, F and M 3 3 are.the forces and moments imposed on the shell side Inlet nozzle of the heat exchanger, and F gand Mg are the forces and moments imposed on the shell side out-let nozzle of the heat exchanger. (c). For the Make-up Tanks (1). Maximum Bending Moment l14.5F X1 - 25.25 Fyj -MZ1 + 69.5 FX2 + 43.25 FY2
+M Z2l 1.42 x 106 In.-lbs.
and ;
;. l21.5(FY2 -Fyj) + 14.5FZ1 ~ "X1 + 69.5 FZ2 ~
X2 (1.27x106 in.-lbs. (2). Maximum Shear Moment l- Myj + MY2 - 18 FZ2l 8.32 x 105 in.-Ibs. Where, Fj and H jare the forces and moments imposed on the tank supply nozzle and, F2 and M2 are the forces and moments impos d on the condensate supply I nozzle to the tank. In all of the above formulaa the subscripts X,Y and Z are three mutually perpendicular directions referenced to one common axis. The forces and moments F and M are to be taken as the sum of the l forces and moments generated by the computerized stress analysis l due to dead weight and seismic DBE of the piping system,, with due ' consideration of their directions. The direction of the DBE shall be selected to result in the worst combination with dead weight loads. Pr-m
SpIcification: 3071-512 Issurd: 9-6-72 Page Eleven h 9. COMPONENT DESIGN BASIS (Continued) 9.4 (Cont 'd ) Seismic displacements for the DBE are given in the gobal coordinate form where X is east, Z is south and Y is vertical . The three dis-placements components of the three mutually perpendicular directions of excitations are expressed in inches and represent the square root of the sum of the squares of the displacements of the vibratory modes. The displacements for the OBE are defined by multiplying the DBE displacements by 1/1.875. The pump, heat exchanger and make-up tank nozzle connections shall be rigid anchor points for piping. This equipment is subject to seismic displacements of the supporting floor slab. The anchor movements are as follows: Horizontal Displacement, OBE = . 042 in. , OBE = . 079 in. ; Vertical Displacement, OBE = .0096 in. DBE = . 018 !n. End thermal movements of the heat exchanger and make-up tank will l be considered as zero because of the low temperature change. , Q 9.5 Supporting Structures l 1 All support structures for the E.E.C.W. System Class 2 and Class 3 1 components shall be designed for a Class I seismic criteria. Hangers and supports shall be located and spaced in a manner, to limit seismic accelerations for the line valves to 5.0g under DBE condi-tions. Seismic displacement of piping shall be limited to the clearance dimensions of piping where it passes through sleeves in walls and slabs to avoid impact. Anchor movements shall be de-termined from the applicable floor response spectra of the build-ing. 9.6 Insulation I All Class 3 components are insulated with insulation of approximately 1" thickness and a specific density of 15#/cu. f t. 9.7 Seismic Analysis of Pipino l Class 2 and Class 3 piping 8 Inch NPS and larger shall be analyzed j by use of a multi-degree of freedom dynamic modal response method. I i The piping under seismic analysis shall be excited in each of three mutually perpendicular directions, two horizontal and one vertical . T* m. l u
Specification: 3071-512 Issu;d: 9-6-72 Page Twelve V[ I~' 9. COMPONENT DESIGN BASIS (Continued) 9.7 Seismic Analysis of Piping (Cont 'd) The differential seismic movements at interface points between the piping and structures or components as specified in Article 9.0 shall be considered. The effect of seismic reactions from branch piping at piping inter-sections shall be considered if the ratio of the moments of inertia of the piping cross sections, I run/I branch, j{ 7.0. The worst horizontal excitation resulis shall be directly combined with the vertical excitation resul ts for the Operating Basis Earthquake (OBE) and the Design Basis Earthquake (DB E) . The multiplier for the DDE shall be taken as 1.875. The percent of critical damping used in the dynamic analysis shall be 0.5. Class 2 and Class 3 piping 6" NPS and smaller may be subjected to a simplified dynamic analysis employing the independent simply supported beam method. A set of seismic design curves showing period versus span, deflection versus span and seismic load versus span for the first mode seismic deflection of a simply supported beam, employing the respective floor response spectra as input acceleration, shall be used. The method of oad combinations and the allowable stresses shall be as requi red per ASME Code, Section 1 (~} \-- III, 1971 Issue. I ( ! 9.8 Piping Class 2, E.E.C.W. System Equipment Interfaces The movements of the connection weld between the E.E.C.W. System , piping and the Reactor Recirculation Pump nozzles will be due to i the resulting thermal movements (from the hot to the cold position) of the Reactor Recirculation Pump in the Reactor Recirculation ' Piping System. The pump movement i s as fol l ows : 1.43 inches Down 0.265 inches East 1.06 inches South The connection weld between the E.E.C.W. System piping and the Drywell Cooler nozzles shall constitute a rigid anchor. This equipment is subject to seismic displacement of the supporting drywell steel. The anchor movements are as follows:
Specification: 3071-512 Issued: 9-6-72 Paga Thirtsen [{ ~
- 9. COMPONENT DESIGN BASIS (Continued) 9.8 Piping Class 2. E.E.C.W. System Equipnent (Cont'd)
L Horizontal Displacement OBE = . Oil in. DBE = .0206 In. Vertical Displacement OBE = .0034 in. DBE = . 016 in. 9.9 Piping Class 3. E.E.C.W. System Equipment Interfaces The connection weld between the E.E.C.W. System piping out side the primary containment and the equipment (as listed in Section 5) nozzles shall constitute a rigid anchor. This equipment is sub-ject to seismic displacement of the supporting floor slab. The anchor movements are as follows: For the Core Spray System and Residual Heat f.emovat System Pump Motors; the Core Spray and Reactor Core Isolation Coolant and High Pressure Cooling Injection Space Coolers, (sub-ba s ement ) , Horizontal Displacement OBE = .0128 in. DBE = . 024 in. Vertical Displacement OBE = .0084 in. () t DBE = . 016 in. For the Residual Heat Removal Space Cooler and the Standby Control
- Air Compressor, (First floor),
Horizontal Displacement OBE = . 016 in. DBE = . 031'In. Vertical Displacement OBE = .0096 in. DBE = . 018 In. For the Switch Gear Room Space Coolers (Second floor), Horizontal Displacement OBE = . 042 in. DBE = . 079 in. Vertical Displacement ODE = .0096 in. DBE = . 018 in. Or uA. ' t.
. Specification: 3071-512 Issurd: 9-6-72 Paga Fourteen
- 9. COMPONENT DESIGN BASIS (Continued) 9.9 Piping Class 3. E.E.C.W. System Equipment Interfaces (Cont 'd )
For the Switch Gear Room Space Coolers and the Hydrogen Control System (Third floor), Horizontal Displacement OBE = . 056 in. DBE = .106 in. Vertical Displacement OBE = .0096 in. DBE = . 018 in. For the Control Room Air Conditioning Equipment and the Standby Gas Treatment Space Cooler (Fi f th floor), Horizontal Displacement OBE = . 072 in. DBE = .136 in. Vertical Displacement OBE = .0096 in. DBE = . 018 in.
- 10. COMPONENT CHARACTERISTICS 10.1 Class 2 and Class 3 E.E.C.W. System Piping (Weights are given on the referenced piping Isometric drawings),
s Des ign Pressure 150 PSIG Design Temperature 2000F (3500F for Class 2 piping) Material See Appendix "A", Table 7 Dimensions i", li", 2", 2}", 3", 4", 6", 8' & 10" Sch . LO 10.2 Valves As per Valve Specification, Valve List and Valve Design Specif1-cation 3071-501 & 3071-12. 10.3 Pumps Specific pump data is given in Detroit Edison Specification 3071-85 Specific Design Data is as follows: Cl l e-
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l Specification: 3071-512 Issusd: 9-6-72 Paga Fifteen I 10 COMPONENT CHARACTERISTICS (Continued) [' 10.3 Pumps (Cont'd) Design Pressure 120 PSIG Design Temperature 120 F Pump Casing Material A216 WCB Cast Steel Discharge Capacity 1450 GPM Discharge Head 158 Ft. @ 51 Ft. NPSH @ 95 F 10.4 Heat Exchangers Specific heat exchanger data is given in Detroit Edison Specifi-
, cation 3071-88. - Specific Design Data is as follows:
Shell Side Tube Side Design Pressure 120 PSIG 175 PSIG Dest gn Temperature 1200F 1200F Mate rial A-515 Grade 70 Admiralty SB-lli Fluid Condensate RHR Service Water I Quantity 1600 GPM 1450 GPM Temp-In ll00F (890) Temp-Out 950F 102.60F 10.5 Make-up Tanks Specific make-up tank data is given in Detroit Edison Bill of Material S20-17M. Specific Design Data is as follows: Design Pressure 100 PSIG Design Temperature 120 F Material for Shall and Head A-515 Grade 70 Capaci ty 600 Gallons 10.6 Overpressure Protection The E.E.C.W. heat exchangers and make-up tanks are equipped with relief valves.
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Specificat ion: 3071-512 Issurd: 9-6-72 Page Sixteen ( )( 10. COMPONENT CHARACTERISTICS (Cont inued) 10.6 Overpressure Protection (Cont 'd) The set points for the heat exchanger are as follows: Tube Side: 125 PSIG Shell Side: 100 PSIG The set point for the make-up tank is 75 PSIG. II. CLASSIFICATION OF CONDITIONS 11.1 Operating Condition During normal plant operating conditions the E.E.C.W. System will be operating as part of the Reactor Building Closed Cooling Water System. The E.E.C.W. pumps, heat exchangers and make-up tanks j will be in-operative and isolated from the cooling system. This I condition is defined below: Class 2 and Class 3 System Components: l Cooling Water Supply Lines, Pressure 95 PSIA 1 O Temperature 95 F i Flow 8000 GPM j Cooling Water Return Lines, Pressure 95 PSIA l Temperature 1100F I Flow 8000 GPM 11.2 Earthquake Loadings ! A total nunber of one Des ign Basis - Earthquake (DBE) and two Operating Basis Earthquakes (DBE) shall be considered to occur during the 40-year design life. Ve'tical and horizontal seismic excitations will occur simul taneous! ; . The maximum stress re-sulting from horizontal x or z directional excitations shall be added to the stress resultir.g from the vertical excitatien. All pressure retaining componrts are fully flooded at all times.
- 12. HYDROSTATIC AND LEAK TESTS Hydrostatic testing shall meet the requirements of NC-6200, except that the valve bodies shall be tested by the manufacturer in accordance
{ with ANSI Bl6.5 or MSS SP-66 for Class 2 and Class 3 valves.
Specifiestion: 3071-512 Issurd: 9-6-72 Page Seventeen 12 HYDROSTATIC AND LEAK TESTS (Continued) Prior to the hydrostatic test, all valve stem leak-off connections shall be open ended. All line valves, sMil be in the open position, but not bachseated, to provide full differential pressure across the stem pack-Ings. During hydrostatic test, examination for leakage shall be made. There shall be absolutely no visible leakage ,on any of the pressure retaining components, including valve stem packings and check valve exercising devices. The test medium shall be demineralized water. The hydrostatic test pressure for the system shall be 188 PSIG @ 70 0F.
- 13. REFERENCES
( I). Seismic Analysis of the Enrico Fermi #2 Reactor Building, Sargent
& Lundy Report #SI-2682 dated September 2, 1971.
( 2). General Electric BWR Plant requirements Specification 22A1300BC. ( 3). Enrico Fermi Atomic Power Plant Unit #2 PSAR. ( 4). BWR Equ' ment Environmental requirements General Electric g Speci'.c tion 22A3019 ( 5). The ASME Boller and Pressure Vessel Code, Section III,1971 Issue. ( f.) . Edison Pipe Fabrication Specification 3071-30. ( 7). Edison Pipe Erection Specification 3071-31 ( 8). Edison Welding Specifications 311, 512 and 513. ( 9). Edison Valve Specification 3071-12 & 501 (10) . The pr";sure integrity of piping and equipment pressure parts, per FSAR, Appendix A. (II). Edison Specification 3071-85, ti.c E.E.C .W. System Pumps . i (12). Edison Specification 3071-88, the E.E.C.sf. Heat F;. changers. (13) . Emergency Equipment Cooling Water System Isometric Drawings: 6M721-3672 6M721-3368 3351 3337 rs 3347 3336 Q' 3679 3666
Specification: 3071-512 Issutd: 9-6-72 Page Eighteen (( 13. REFERENCES (Cont inued) (13). Emergency Equipment Cooling Vater System Isometric Drawings: (Con 6 *d) 6H721 -3657 6H721-3348 3340 3346 3656 3345 3362 3667 3189 3368 3672 3084 1-O g ([)F-
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O 4 APPENDIX A ANSI Primary pressure rating, materials and dimensions for Nuclear Piping. O . J l l t 1 O l l l l
. t 1ABLE 1 900 LBS ANSI PRESSURE RATING CARBON STEEL PIPING SYSTEMS O
ASIM Trem Size Ratine Tvoc~ Socciffeation Pipe 3" and Smaller Sch 160 Seamless - A106 Gr.
- 4" thru 10" SCH 120 Seamless A106 Gr. B
- 12" thru 14" Sch 100 Seamless or A106 Gr. B
- 16" and Larger Sch 80 Seam Welded A155 Gr. KCF*
Valves 2" and Smaller 1500 lbs. SW' A105
- all 2 1/2" thru 24" 900 lbs. BW A216 Gr. WCB*
Types Fittings 2" and. Smaller 6000 lbs. SW A234 Gr. WPB* 2 1/2" and 10" Match pipe wall BW A234 Gr. WPB* 12"' thru 14" Sch 100 BW A234 Gr. WPB*
,16" and Larger Sch 80 BW A234 C;r. WPB*
() - F1&nge 2" and Smaller 2 1/2" and Larger 1500 Lbs. 900 Lbs. SW, RF WN, RF A105* A105* ( Bolts Bolt Studs A193 Gr. B7* Nuts Hex A194 Gr. 2H3 Class Gaskets Flexitallic Style CG
- For ASME Code Class I the materials must be impact tested per NB-2300 at a temperature of +10 F O
e
TABLE 2 900 LBS' ANSI PRESSURE RATING STAINIESS STEEL PIPING SYSTEMS ASTM Item Size Ratine Tvoe Soecification PIPE 2" and Smaller Sch 160 S Seamless A312 TP304 2 1/2" and 3" Sch 160 S Seamless A376 TP304 4" and thru 6 " Sch 120 S or Seamweld A358 TP304 8" thru 24" Sch 100 S Valves 2" and Smaller 1500 lbs. SW A182 Gr. F304 , all 2 1/2" and Larger 900 Lbs. BW A351 Gr. CF8M Types Fittings 2" and. Smaller 3000 Lbs. SW A182 Gr. F304 2 1/2" and 3" Sch 160 S BW A403 Gr. WP304 4" thru 6" Sch 120 S BW A403 Gr. WP304 ' 8" thru 24" Sch 100 S BW A403 Gr. WP304
~
(:)- l g Flanges 2" and Smaller 1500 lbs. SW, R.F. A182 Gr. F304 )
~
2 1/2" and Larger 903 Lbs. WN, R.F. A182 Gr. F304 1 Bolts Bolt Studs A193 GR. B7 l
, l l
Nuts Hex A194 Gr. 2H. l Gaskets Flexitallic Style CG O d
I TABLE 3 ) l l 600 LBS ANSI PPISSURE RATING CARBON STEEL SYSTDIS )
. ASTM Item Size Ratine Type Soecification
~~
,.. .. \
Pipe 3" and Smaller Sch 160- Seamless A106 Gr. B 4" and Larger l Sch 80 Seamless A106 Gr. B Valves 2" and Smaller 600 lbs. SW A105 all 2 1/2" and larger 600 lbs. BW A216 Gr. WCB Fittings 2" and Smaller 3000 Lbs SW A234 Gr. B l
. 2 1/2"*thru 3"
- Sch 160 BW A234 Gr. B 4" and larger Sch 80 BW A234 Gr. B Flanges 2" and Smaller 600 Lbs SW, R.F. A105 -
21/2" and larger 600 Lbs BW, R.F. A105 Bolting , Bolt Studs A193 Gr. B7 Nuts Hex A194 Gr. 2H,' Gaskets Flexitallic Style CG 4 9
.O-
- 6 l
l -
- l
TABLE 4 rQ . 600 LBS ANSI PRESSURE RATING STAINLESS STEEL PIPING SYSTEMS ASIM Iten Size Ratine Tvoe Sneciffeation Pipe 2" and Smaller Sch 80 S Seamless A312 TP304 2 1/2" thru 12" Sch 80 S Seamless or A376 TP304 or 14" and larger Sch 60 S Seamweld A358 TP304 Valves 2" and Smaller 600 lbs. SW A182 Gr. F316 all 21/2" and larger 600 Lbs. BW A351 Gr. .CF8;; Sizes
. Fittings 2" and Smaller 3000 Lbs. SW A182 Gr. F304 2 1/2"'thru 12" Sch 80 S BW A403 Gr. WP304 14" and larger Sch 60 S BW A403 Gr. WP304 0 - .
( Flanges 2" and Smaller 600 lbs. SW, R.F. A182 Gr. F316 21/2" au1 Iarger 600 Lbs. WN, R.F. A182 Gr. F316 Bolting Bolt Studs A193 Gr. B7 Nuts Rex A194, Gr. 2H, Gaskets Flexitallic Style CG e O.
IABLE 5 300 LBS ANSI PRESSUPI RATING CARBON STEEL PIPING SYSTDIS Item ASIM Size Ratine Tvoo Snecification Pipe 2" and Smaller Sch 80 Seamless A106 Gr. B 2 1/2" and Large r Sch 40 Seamless A10s Gr. B Valves 2" and Smaller 600 Lbs. SW A105 all 2 1/2" and Larger 300 lbs. BW A216 Gr. WCB
, Types Fittings 2" and smaller 3000 lbs SW A234 Gr. B 2 1/2" and Larger Sch 40 BW A234 Gr. B
) Flanges 2" and Smaller 300 Lbs. Sw, R.F. A105 2 1/2" ar.4 Larger 300 lbs. WN, R. F. A105 Bolting Bolt Studs A193 Gr. B7 Nuts Hex A194 Gr. 2H Gaskets Flexitallic**
Style CG
** For non-nuclear piping systems (Group 't") use 1/16" cranite rings (ANSI B31.I).
9 e
i 1 TABLE 6 l O - - l
~
300 LBS ANSI PRESSURE RATING STAINLESS STEEL PIPING SYSID1S
- s. ASIM Item Size Ratine Tvoo ,
Specification Pipe 2" and Smaller Sch 40S Seamless A312 Gr. TP304 2 1/2" thru 10" Seamless or A376 Gr. TP304 c Sch 40S 12" and Larger Std 3/8" Wall Seamwelded A358 Gr. TP304 Valves 2" and Smaller 300 Lbs SW' A182 Gr. F316 all 2 1/2" and larger 300 Lbs BW A351 Gr. CF8M Types Fittings 2" and Smaller
- 2000 Lbs SW A182 Gr. F304
)
2 1/2"'thru.10" Sch 40S BW A403 Gr. WP304 12" and Iarger Std 3/8" Wall BW A403 Gr. WP304
~ ~~
O Flanges 2" and Smaller 300 Lbs. SW, R.F. A182 Gr. F316 ( , 21/2" and larger 300 Lbs. WN, R.F. A182 Gr. F316 Bolting Bolt Studs A193 Gr. B7 Nuts Hex A194Gr.2N' Gaskets Flexitallic Style CG . O. I
l 1 1 TABLE 7 O - 150 LBS ANSI PRESSURE RATING CARBON STEEL PIPING SYSTEMS ASDi Item Size Ratine Tvoe Soecification Pipe 2" and Smaller Sch 80 Seamless A106 Gr. B 2 1/2" thru 10" Sch 40 Seamless A106 Gr. B 12" thru 24" Std 3/8" Wall Seamless A106 Gr. B 26" and larger Std 3/8" Wall Welded A155 Gr. KCF 70
- Valves 2" and Smaller 600 Lbs. SW A105 all 2 1/2" and Larger 150 Lbs. BW A216 Gr. WCB Types Fittings 2" and' Smaller 3000 Lbs SW A234 Gr. B 2 1/2" thru 10" Sch 40 BW A234 Gr. B !
12" and Larger Std 3/8" Wall BW A234 Gr. B 1 l
. . , . i O "
Flanges 2" and Smaller 150 Lb. SW,I.F. . A105 1 ( , 2 1/2" and Larger 150 Lb. WN, R.F. A105 Bolts , Bolt Studs A193 Gr. B7 Nuts Hex A194 2H Gaskets FlexItal1 Ic ** Style CG
- Butterfly valves 4" and larger also used within this pressure range.
** For non-nuclear piping systems (Group "D) use 1/16" cranite rings (ANSI B31.1).
O. - I
TABI2 8
. 150 LBS ANSI PRESSURE - RATING STAINLESS STEEL PIPING SYSEMS AS'Di .
Item Size Ratine Tvoe Soecificotfor Pipe 2" and Smaller Sch 40S Seamless A312 TP304 2 1/2" thru 12" Sch 10S Seamless or 4376 TP304 or 14" and larger Sch 10S Seamwelded A358 TP304 Valves 2" and Smaller 150 lbs. SW. A351 Gr. CF8M all 2 1/2" and Larger 150 Lbs. BW A351 Gr. CF8M Types Fittings 2" and Smaller 2000 Lbs SW A182 Gr. F304
. 2 1/2" and Larger Sch.10S BW A403 Gr. WP 304 O Flanges 2" and Smaller 150 Lbs SW, R.F. A182 Gr'. F316 l
( 21/2" and larger 150 lbs WN, R. F. A182 Gr. F316 i Bolting Bolt Studs A193 Gr. B7 e . Nuts Hex A194 Gr. '2H Gaskets Flexitallic Style CG , 1 O. 4 e
. TABII 9 900 LBS ANSI PRESSURE RATING, CARSON STEEL PIPING SYSTEMS (BRITILE FRACTURE CONTROL)
"SIM A -
Item Size Ratine Tvoe Soccificatior Pipe- 3" and Smaller Sch 160 Seamlers A333 Gt . 6 4" thru 10" Sch 120 Seamless A333 Gr. 6* ! 12" thru 14" Sch 100 A333 Gr. 6* 1 16" and larger Sch 80 ** - A333 Gr. 6* l
. L_
Vilves 2" and Smaller 1500 Lbs SW A350 Gr. LF2 ' s.nd 2 1/2" and larger 900 Lbs BW A352 Gr. LCB Types - or A216 Gr. WCC Fittings 2" and Smaller 6000 Lbs SW A420 Gr. WPL 2 1/2" thru.10" March pipe wall BW A420 Gr. WPI 12" thru 14" Sch 100 3W A420 Gr. WPI 16" and Larger Sch 80** BW A420 Gr. WP1 Flanges 2" and Smaller 1500 Lbs SW, R.F. A350 Gr. LF2 I 2 1/2" and larger 900 Lbs. WN, R.F. A350 Gr. LF2 Bolts 1" Dia and Smaller Bolt Studs A193 Gr. B7 1 1/8" and larger Bolt Studs A320 Gr. L7* Nuta 2" and Smaller Hex A194 Gr. 2H Gaskets Flexitallic Style CG
- Materials must be impact tested per ASME Code Section III, Article NB-2300 at a temperature of (-) 200F.
I
** 20" Feedwater system piping to be schedule 100 ,
-'- ' - ~ ~ ~ ~
. l '-
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TABLE 10 O f 1500 LBS ANSI PRESSURE RATING STAIN 1ESS SIEEL PIPING SYSTEMS ASIM Item Size Ratin? Tvee Soecification Pipe 2" and Smaller Sch 160 Seamless A312 TP304 2 1/2" and 3" Sch 160 Seamless or A376 TP304 Valves 2" and Smaller 1500 Lbs SW A182 Gr. 3N 2 1/2" and 3" 1500 lbs BW A351 Gr. CFI Fittings 2" and Smaller 3000 Lbs SW A182 Gr.304 2 1/2" and 3" Sch 160 LW A403 Gr. WP 304
..3 k ,
Flanges 2" and Smaller 1500 lbs SW, R.F. A182 Gr.304 2 1/2" and 3" 1500 lbs BW, R.F. A182 Gr. 304 1 Bolts . Bolts, Studs A193 Gr. B7 l 1 1 Nuts Hex -A194 Gr. 2H i Gaskets Flexital.lic Style CG l e D -
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, NUCLEAR SAFETY RELATCD AUG5 1977
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NUCLEAR SAFETY RELATED O SMALL PIPING DESIGN STANDARD ENRICO FliRMI ATOMIC POWER PLANT - UNIT 2 REPORT PREPARED FOR DETROIT EDISON COMPANY O REPORT SL-3150 REVISION 1, JULY 29,19T, SA" GENT &LUNDY O ~~~~~~~ - - a
O TABLE OF CONTENTS Rev.1, 7-29-77 PAGE I INTRODUCTION 1 A. Description B. Relationship to ASME Code Requirements C. Scope II DESIGN PRINCIPLES 2 i A. General I B. Weight Analysis O C. Dermal Analysis D. Seismic Analysis III ASME CODE REQUIREMENTS l 7 i A. Sustained Losds i 1 B. Occasional Loads C. Dermal Expansion IV CONCLUSION 11 A. Stresses B. Nozzle Loads O 11 SL-3159
Rev.1, 7-29-77 V REFERENCES 14 APPENDICES Appendix A - Calculations and Equation Derivations Appendix B - Weight Support System Design Appendix C - Seismic Support System Design i Appendix D - Flexibility Support System Design Appendix E - Small Piping Design Worksheet t O l 1 s O 111 SL-3159 l TL
. -..~ __ _. . - _ _ . _ . . . . _ . . _ - - - - - - -
SARGENT & LUNDY ENGINEERS cmcac Rev.1, 7-29-77 O SMAU_ MPING DESIGN STANDARD ENRICO FERMI ATOMIC POWER PLANT - UNIT 2 DETROIT EDISON COMPANY I INTRODUCTION A. Description The Small-Piping Design Standard presents genc al guidelines and specific rules which are to be applied to the design of piping subsystems to locate weight i supports and seismic restraints and to guarantee adequate flexibility for 1 accommodation of thermal expansion and anchor movements. De recommenda- ! tions of the standard are based on weight, thermal expansion and seismic analysis i of simple beams, which represent elements of the piping subsystem. The assumptions used in the analyses insure conservative results: the estimates of stresses and loads for a given design environment exceed the values which could exist in the actual system. O B. Relationship to ASME Code Requirements Adherence to the recommendations of this standard guarantees satisfaction of the applicable requirements of the ASME Code.
- Specifically, stresses due to pressure, weight, thermal expansion, and seismic excitation are combined and checked against the allowables according to the provisions of NC-3650. Also, the method of analysis requirements of NC-3673.1 arc satisfied since use of the standard amounts to design by comparison with analyzed systems. Satisfaction of ASME Code requirements is shown in detail in Sections il and Ill of this report.
C. Scope his standard may be applied to ASME Code Clar 2 and 3 piping of four inches or smaller nominal diameter. It may not be applied to systems whose maximum operating temperature exceeds 300*F or whose maximum operating pressure exceeds 1750 psi. The pipe material is assumed to have a minimum S *b I 15000 psi for Class 2 and 3. c h Q 0ASME Boiler and Pressure Vessel Code, Section 111 PROJECT 5285-16 SL-3159 _ ___ _ M
SARGENT a LUNDY ENGINEER $ occaco Rev.1, 7-29-77 O 11 DESIGN PRINCIPLES A. General A piping system design represents a compromise t'etween two competing design' requirements: 1) the system must be adequately restrained to prevent overstress due to weight and seismic loads and; 2) it must be flexible enough to accommodate thermal expansion and nozzle movements. Unnecessary or poorly located restraints restrict thermal expansion and nozzle movements and so should be avoided, but enough restraints must be used to limit seismic and weight stresses to allowable values. Recommended spans for seismic and weight supports are given in the Tables of Appendices B and C. To increase the flexibility of a system in a given direction, pipe must be added perpendicular to that direction. The length of perpendicular pipe which is required to accommodate thermal expansion and nozzle movements under various conditions is given in the Tables of Appendix D. B. Weight Analysis
'Ihe standard procedure for designing a weight support system .n colves the use of recommended span lengths to limit the weight-induced bending stress. The requirements of ASME Code may be satisfied by this approach even though the governing equations do not directly indicate an allowable weight stress level.
It is only necessary to determine what fraction of the allowable combined stress the weight load should contribute. Recommenaed spans baseJ on this allowable stress can then be calculated by elementary bending theory (See Appendix A). The span recommendations are listed in Tabic ". I cf Appah il for fluid filled and empty pipes. The effect of the weight of standard insulation for 300"F has also been considered. The recommended span length is given by span (ft) = d 2000Z _y l l O
-i SL-3159
{ a
SARGENT e LUNDY EN GIN E E RS CHICAGO Rev.1, 7-29-77 n =
?) ' where Z is the section modulus (in.3) and W is the I!near weight density (Ib/ft).
The allowable weight stress is 3000 psi. His formula is based on the assumption that the pipe element may be '. , - represented as a simply supported beam. The maximum bending moment for a continuous beam or for a beam with other end conditions cannot exceed the maximum for the chosen model. Therefore, although the analytical model may not always accurately represent the actual piping, it does establish an upper limit for bending stress. To accommodate concentrated weiglits, the spans must be shortened to insure that the allowable bending stress is not exceeded. Rules which are to be used to determine span lengths for spans with concentrated weights are listed in Appendix B. C. Thermal Analysis De object of the thermal expansion ar.alysis is to guarantee adequate flexibility so that nozzle movements and pipe expansion do not cause stresses in excess of the allowable. The design rules of Appendix D limit this stress to 15000 psi. As previously stated, flexibility in one direction is dependent upon the amount of pipe which is perpendicular to that direction. For instance, c component of nozzle movement in the X-direelion can be accommodated if the nozzle is separated from the first X-direction restraint by enough piping in the Y- and Z-directions (See Figure 1). It is the bending stress in the perpenaicular legs, B and D, that must be examined. These may be conservatively modeled as a beam with guided ends subjected to a displacement, 6 ,(Sec Figure 2). The model is conservative since it ignores the flexibility of the elbows and imposes more rigid end conditions than the actual supports. SL-3159
- L l
SARGENT c LUNDY ENGINEERS cmcaco REV.1. 7-29-77 A E ~ g s '/ C 1,
/B D jt
/
c URE1 S=S, + 5 s H I
- s. K H I- H l- l I
c- x l l l ;
/
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r I I I I l FIGURE 2 i y/: m O itthe etio edie stressis isooo psi the2easta or erneaaieuiereine n re9uiredto accommodate the component of nozzle movement is 1 1 = 1245 r. r. = outside radius -
'Ihe recommended lengths for various values of 6 and r. are listed in Table D-1 of Appendix D. Also, a graph or r. vs. 6 is included for various values of1 (See Figure 3 on following Page.). Note that it is necessary to check for nozzle movements in three orthogonal directions.
The problem of pipe expansion can be handied in a simite- manner except thut the movement, 6 , is imposed by thc cxpc. c ' a see La. ,f pipe (Sec Figure 4). 1 See Appendix A for derivations of the equations in this section. D* O -
]D *]D
- e au - 'u" 2" - {' h =
SL-3159 1
SARGENT c LUNDY ENGINEER 5 cmcaco REV. 1, 7-29-77 2 25 (,
1 11 t
2 05 7 6 1 85 5 ( 58 1.65 . 4 n
-4 1.45 l O I 1.25 . .
3 t 0 'l s 1.05 . 19 I . 18 0.85
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.5 2!3 s4 '; A 7 0.0 0.5 10 1.5 2.0 25 DEFLECTION FIGURE 3 O. OFFSET REQUIRED TO ACCOMMODATE NOZZLE MOVEMENTS SL-3159 w
SARGENT a LUNDY EN[NEERs REV 1, 7-29-77 4 p*----...,,__ 9_uide i f l FIGURE 4 r7777 The length of pipe required to accommodate the expansion of the length t' , is 1 = 1.475 Y t r. Values for various lengths and radii are listed in Table D-2 of Appendix D. If nozzle movement and pipe expansion occur simultaneously, the total length of perpendicular pipe required is the sum of the lengths required for l each. ' D. Seismic Analysis An adequate number of properly located restraints must be provided to limit the stress and deflection due to seismic excitation to allowable values. Location of supports requires determination of the maximum span (distance between parallel restraints) in each direction, for which the system response is acceptable. To assure satisfaction of ASME Code requiremen's a response shall be considered 2 acceptable if the total stress ( x2y22)l due to bending and torsional moments does not exceed 7000 psi for OBE an,d 14,000 psi for SSE, and the total deflection ( x +y +z) does not exceed two inches. To estimate a system's seismic response it is assumed thrit each section of pipe l 3 between two parallel restraints acts as a simple beam. For the deflection - estimate the beam is assumed to be simply supported and for the natural frequency estimate it is assumed to have one fixed and one simply supported end. - This assures a conservative estimate of the respor.se. O SL-3159 I l'
SARGENT & LUNDY ENGINEERS Rev.1, 7-29-77 O Using the assumed model, seismic deflection versus span length curves are generated. These are based on appropriatt response acceleration spectra. Superimposed on each deflection ( x, y, z) versus span curve is a curve which indicates the deflection at which the stress for each span is 4000 psi. The intersection of these curves indicates the longest span for which the anticipated deflection does not exceed the allowed deflection (See Figures 5 and 6). Note that the deflection is limited to two inches regardless of the stress. The span values taken from these curves are summarized in the span versus pipe size Table C-1 of Appendix C.
'Ihe seismic stresses are determined by using the computer program SIPDA (Sargent & Lundy Document No. 09-5-047-2.0). This program was developed by Mr. E. B. Branch and Mr. M. Nopola of Sargent & Lundy to:
- 1) Enable selection of maximum spans so that the stresses due to each seismic excitation (i.e., N-S, Ver., E-W) are 4000 psi or less for OBE, 8000 psi or less for SSE.
- 2) Provide seismic restraint design loads. I
- 3) Assure that seismic deflections do not exceed two inches. '
III ASME CODE REQUIREMENTS 1 l Class 2 and 3 Systems
)
In the following subsections it is shown that the stress limits which are established by the design rules of this standard satisfy the ASME Code requirements for Class 2 and l 3 piping. A. Sustained Loads
'Ihe effects of sustained mechanical loads must satisfy equation (8) of NC-3652.1:
P, Do+ .751 M, 3 4t n Z t, = wall thickness ( M, = weight induced bending moment Sh = all wable stress in the hot condition. SL-3159 l
SARGENT & LUNDY ENGINEERS REV. 1, 7-29-77 CHICACO SAMPLE SESIMIC DESIGN CURVE SPAN vs DEFLECTION RIGID _ 33 SIR ___ FLEXI3LE _ MAX AL'E.Va_E DEFLECTICN j j l O 2- / s. M ' g1 U ta MAX MID-SRAN CEFLECTION 10 20 ..- v 00
; . .- a i . , r :3 FIGURE 5
! SEISMIC DESIGN CURVES 1 IMPLY SUPPORTED PIPE O SL-3159 l a
SARGENT a LUNDY
'"[ "5 REV. 1, 7-29-77 SAMPLE O 13 .
SEISMIC DESIGN CURVE-SPAN vs REACTION p RIGID 72.3"? - FLEXIE13 _ 11 < 10 . 2 64 6 4 7
- u. .
b O 6 4 3 2 i i f 1- :
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8 10 15 20 30 e so LETETH IN FEET FIGURE 6 SEISMIC DESIGN CURVES SIMPLY SUPPORTED PIPE O SL-3159
~
s SARGENT C 1. UNDY E >lCIN E E R S c>ucAco Rev.1, 7-29-77 O For pipes of 4 inches nominal diameter or less and subject to pressure not exceeding 1750 psi (or the recommended value from Sargent & Lundy Mechanical Engineering Specifications if that value is lower), the first term has a maximum
~
value of less than 5000 psi. For systems within the scope of this standard, the stress intensification factor 1, in the second term, attains its greatest value of 1.532 for a 4-inch schedule 40 socket welding branch connection (weldolet). The weight iduced bending stress is a maximum of 3000 psi. The hot allowable stress for materials and temperatures which is covered by this standard is no less than 15000 psi. Thus, 5000 + .75 (1.532) (3000) = 8447115000 = Sh ; therefore, equation (8) is satisfied. B. Occasional Loads The effects of sust 7ed and occasional loads must satisfy equation (9) of NC-3652.2. , P max D gMR o +.75 -1S 41" h O Since the weight and maximum pressure were considered for evaluation of equation (8) the only additional term is the seismic stress, M /Z = 7000 psi for . R OBE, and 14000 for SSE. Thus: 5000 + .75 (1.532)(3000 + 7000) = 16490118000 = 1.2Sh 5000 + .75 (1.532)(3000 + 14000) = 24533127000 = 1.8S h So equation (9) is satisfied for upset and energency co.sitions. C. Thermal Expansion l l '!he ASME Code requirements for thermal expan. 'on are satisfied if equation (10) I or equation (11) from NC-3652.3 is satisfied. IM [ 1 S, (10) l l M,/Z is the bending stress due to thermal expansion and anchor movements, so ' O 1.532 (15000) = 22980 psi SL-3159
- 1
SARGENT a LUNDY ENGINEERS CHICACO Rev.1, 7-29-77 O But S, = (1.25S, + .25Sh) = (1.25 15000 + .25 15000) = 22500 psi. So equation (10) is not satisfied and equation (11) must be checked. PD M M 4tn + .751 Y +1 j 1 Sh+8a IIII 5000 + .75 (1.532) (3000) + 1.532 (15000) = 31427 psi 137500 psi So equation (11) is satisfied. i IV CONCLUSION For systems within the scope of this standard, application of iis design rules assures satisfaction of the requirements of NC-3650 of the ASME Code. I* These systems must have the fo!!owing characteristics: - Pipe class: 2 and 3 Nominal pipe size: 4 inches and smaller Maxinium operating pressure: 1750 psi Maximum operating temperature: 300*F Allowable stress: Sh > 15000 psi S, 2.15000 psi A. Stresses
'Ihe stresses in a system designed accordin;- to t" - ytendard arc limited to the following values:
Moment loading Max stress (psi) seismic OBE 7000 weight 3000 thermal expansion plus nozzle movements 15000 0 SL-3159 rt
SARGENT a LUNDY ENGINEERS CHICACO Rev.1, 7-29-77 O TABLE 1 NOZZLE ALLOWABLES CR AMCHoA RE%TIO M Pipe Size Schedule Moment Load ( ft-lb) Shear Force (Ib) 1/2 40 85 72 80 100 78 160 110 99 3/4 40 147 103 80 178 128 160 209 145 1 40 277 170 80 335 207 160 396 246 1-1/4 40 489 270 . 80 607 329 160 713 383 : 1-1/2 40 679 342 80 858 O 160 1060 427 529 j 2 40 1170 536 80s 1520 683 160 2040 912 t 2-1/2 40 2220 903 80 2790 1120 160 3410 1360 3 40 3590 1360 80 4630 1680 - 160 5990 2200 3-1/2 40 6690 2250 80 6540 2240 XXS 10300 3490 4 40 6600 2250 80 8890 2920 160 12300 3950 0 SL-3159
~
b l SARGENT e LUNDY - E NCIN E E RS Rev.1, 7-29-77 B. Nozzle Loads
'Ihe loads imposed on nozzles by piping which is designed according to this standard do not exceed the values listed in Table 1.
Sargent & Lundy Prepared by: e. - , .?ev. 1, 7-29-77 P. Ivy, g Project Engineer, Engineering Mechanics Division Reviewed by: b Rev.1, 7-29-77
. . . Hart, F ineering Analyst, Engineering Mechanics Division O ME. B. Branen, aev 1. 7-29-77 Head, Engineering Mechanics Division
( sw_ = Approved by: Rev.1, 7-29-77 R. F.' Scheibel, Project Director O SL-3159
5ARCENT A LUNDY l E N GIN E E R S Rev.1, 7-29-77 [O V REFERENCES l ASME Boiler and Pressure Vessel Code, Section III,1974 ed. New York: American Society of Mechanical Engineers,1974. 3 Kellogg, M.W. and Company. Design of Piping Systems. Revised 2nd ed. New York: John Wiley and Sons, Inc.1965. Oak Ridge National Laborataries and Teledyne Materials Research. Nuclear Piping
]
d D Ae, ORNL-TM-3645. Oak Ridge: Oak Ridge National Laboratory, Feb.1572. Roark, Raymond J., Formulas for Stress and Strain. 4th ed. New York: McGraw- l 11111 Book Company,1965. 1 L Timoshewko, S. and D.11. Young, Elements of Strength of Materiah. 5th ed. Princeton: 1968. [ l - 1 0 SL-3159
h.4 z._a 2 m. , e ., 4 2 w - -' - - - -- - - APPENDICES O . l l l l l
, I l
i l o 9 4 i 1 O 1 m - .- _
Cf ROENT O LUNDY ENGINEEDS APPENDIX A CHICAGO sL-3159 l R E V. 1, 7-29--77 i O 'cAucut ions ^~o EauxTion oERiv4Tions A-1 Weight The recommended weight support spans are based on the following analysis: l The pipe elements between two weight supports may be j l conservatively represented by a simply supported, uniformly loaded beam (fig. lA.). f 1 IY1J 1 V 1 1 i fl 1 1 1 A A g ' x :I fig.1 A 2 fig.1B From symmetry and squilibrium considerations the bending moment at' a cross section X t' nits from A is: O M: Xdx : @ (x I-X' ) R,- p , a : 1incar weight dersity X-f"xo 1 This is a maximum at X = f/2 y - m max- 2 '.!*_ [4,- 62 _ sfe
- The stress due to this moment is 5: *= ^l , 2: se ction m o du'us If S a is the allowable stress sa : a l*/BZ ,so l= fB y '
1 is the maximum span for which the allowable stress is not ! exceeded. j O l A-1 l w-_ - -- -- -
'l
CARGENT Q LUNDY ENOiNEEDS APPENDIX A CM 8C AGO SL-3159 REV.1. 7 29-77 O Ar1 Weight (continued) For an allowable stress of 3000 psi J _F 4x coo; ' For 2 given in (inches) ,3 / in feet, and ee- in lb/ft j = 20032' w g,; ) to allow a construction tolerance of one foot without exceeding the allowable stress, the recommended span is one foot less than indicated by equation (A-1). y: 20,. W -1 m.2) l The maximum support load is calculated assuming that l:fs +1 is used as the span length. Thus LOAD = feu (A-3) This is not the reaction, R,a of fig. 1D. It is the total weight of a full span and represeits the load which would be imposed on an intermediate support of a continuous multi-support system. () l l A-2 l l
3 CARGENT& LUNDY E N C. I N E E N s
> ' " ' " " APPENDIX A SL-3159
- o REV.1, 7-29-77 A-1 Weight (continued)
Span Reduction for Concentrated Weights The maximum total bending moment for a span of length f,,
)
subject to distributed weight, s , and centrally located concentrated weight, W, e is Mmax= + * ,' For a given pipe the allowable maximum moment is where 8 is the recommended span length without the concentrated load. Therefore w8 S. + $ g M S' 4 6 If one half of the recommended span length is used the safe value for We can be obtained. M it?) .y we tit o) S MA'
- 8 4 8
%} g 3 nr f
- 3 32 We 6 3/4 s2 or 75*/. of w l Similarly, if f,:.SR 81ef* 4 _WeL9f) g y .f
- We 6 ,10 t y ) es o .f,og ,)
( l A-3
8 l CARGENTQ LUNDY EN08NEED9 APPENDIX A g cmcaco SL-3159 r RE V. 1, 7-2 9-7 4 ['O A-1 Weight (continued) Span Reduction for Concentrated Weights So, for a concentrated weight of less than 10% of the normal span weight a 10% reduction in span would keep the weight stress below 3000 psi. For a very short span (say 10% of the normal span) a similar analysis shows that a concentrated weight of 2.5 times the normal span support load can be accommodated. Since such concentrated weights are usually very rigid compared to the piping, the length of the concentrated () weight may be ignored in the span length estimate: the 10% span is the pipe length exclusive of the length of the concentrated weight element. A-2 Expansion and Nozzle Movements The recommended offset lengths are based on the following analysis: All segments of pipe in the offset direction are assumed to act as a single guided cantilever, the Flexibility of intermediate elbows and pipes is ignored (see Fig. 2) (2) - A-4
{ CARGENT O LUNDY ENoNEERS C M 6C# GO APPENDIX A SL-3159
~
REV.1, 7-29--77 t' A-2 Expansion and Nozzle Movements (continued) 9 The recommendedc offset lengths are based on the following I analysis: i All segments of pipe in the offset direction are assumed to act as a single guided cantilever. The flexibility of i intermediate elbows and pipes is ignored (see Fig. 2) b-s l "i 's i i , bl #2. - - S
- 5 F I G. 2 Suppose a deflection,d,is caused by a load, W. .
W
- n. ;r
' ~ - - - aa-u W
M Rs U A B IF: j O Q R:W IM:ox 0 > Wf-M a-Mb=O but Ma Mb 50 f-( I Mb ds aW ' M(n) 2 x M*)WY -Wf/ 2 :W( x - f / 2.' v 8: d x' EI M = F.E--( I x -1/ 2 ) dx , A =EI3-.('Y F + c ' dx A :osoc=o 2 2 1 0 W IX* fmai p, Q Y EII'G 4 [+ , y:O at x: O s o C': 0 A-5
CARGENTO LUNDY E N GIN E E AS
"" APPENDIX A SL-3159 o REV. 1, 7-29-77 J
A-2 Expansion and Nozzle Movements ! (cont'nued) . Thus -W y :EI i G M\4 j is the deflection at a distance X from the anchored end. 1 Since Y = -f at X = f - 6.Ef_ i E1 4 _A.',i 4 l W l' , g _12EI - or w:_12SE1 J*
]
The stress due to the defeletion, d , is , r 5 :r.M/t : Wfr- 12 f cI r. JQ 21 29'I
- 9d r. E_ , r. : c u te r radio, f*
If this deflection is the resultant of three equal orthoganal deflections, E' , S: 65 r. E 8:h(S'*) f R' t
= _G66 r.E g GTT 4'r,.r /t 5 5 For an allowable stress of 15000 psi the offset length must be ll _ [ GT3 3 010* r,f
Y2 .
- l 15000 -44(I' 2. ' or ' 2 h , ! r e t '
! I tor r, and E in inches L. 1 i s O ) A-6
i CARGENT O LUNDY ENGINEERS ! C"'C"' APPENDIX A I SL- 3159 m RE V. 1, 7-29-77 U i
.A-2 Expansion and Nozzle Movements (continued)
The def?ection due to pipe expansion is handled in a similar manner except that the imposed deflection is i
=
one-directional. Thus J
- r. E f: :9.129k,[
l
- l For' expansion of a length A' l 0 l 2
j = f' A A T : ( .0261 in/f t )f' for austenitic stee: 70* to 3 O O
- F O e f:9.129 @
a R> 1 29.1291r, (.0 2 51 ) f"
' i 77F - !
f :1. 4751 r. J' ~' for / and [in fee t , r. in inches O l Note that the flexibility of the leng th j and the elbow i I is ignored. 1 6 ! Free Ends: The bending moment cannot_ c::cced thi t for a l 3 cantilever. l
.w 4
u bbbbb[ 1 hbbbb , a v M: ex d x:
- ]** -
=
i s i A-7
~
CARGENTOLUNDY E"fj,",EE"5
. APPENDIX A SL-3159 REV 1, 7-29-77 ]o A-2 Expansion and Nozzle Movements (continued) whichis4timesthe[ofasimplysupportedbeam.
Thus,
. the span should not exceed 50% of the value from table I.
If it does, or if a concentrated weight is on the span, an end support should be provided.
]
T
]
TO [ [ r ; l l I o A-8 e
CAGOENT O LUNDY E"fle",E"#8
,o APPENDIX A SL-3159 R E V. 1, 7-29-77
[O A-3 Nozzle Loads [ The maximum bending stress is that due to simultaneous { action of weight, thermal, and seismic loading. That value is 3000 + 15000 + 7000 = 25000 psi. The [ , bending moment corresponding to this stress is Z 25000 psi l M= = 2083 Z ft.lb. I 12 in/ft , [ where 2 = section modulus (in ) 3 The shear force due to weight is one half the maximum ' lJ weight support load from table B-1, Appendix B. 7 The shear force due to seismic loading may be estimated ; by assuming that it is in the same proportion to the ii
)
weight shear force as the seismic stress is to the weight ', i stress. seismic shear = 7000 weight shear 3000 seismic shear = 2.33 weight shear . The shear due to bending moments is estimated by assuming that it is equal to the force required to cause a 15000 psi bending stress with a moment arm equal to the minimum allowed offset from table D-2. l l O A-9
] SARGENT Q LUNDY ENGINFLH%
i .m a . .. . APPENDIX A SL 3159 REV.1, 7 29 77 (m Derivation of Seismic Analyses Equations
]%
A-4 S_e_i_smic, Des _ign Curves A-4.1 I_ntre duc tion
} To arrive at the equations used to predict the actual deficctions, allowable deflections and restraint reactions, the elements of piping betwccr. rcstraints are modeled } as a simply supported beam as shown in Figure A-4.2a. With the exception that the natural frequencies used are those ] that correspond to a beam aith t.he same dimensions which } has one end fixed and one end simply supported. This assures a conservative estimate of the response. ]tOV All design curves, of which typical examples are shown in ] Figures 3f5.la__and 2,. Lib were calculated using the equa-
. tions shown here and enveloped seismic response spectra covering all elevations in the Reactor, Turbine, and RHR Complex Buildings. For each of the Buildings, separate responses were calculated for the East-West, North-South, and Vertical Direction Excita.. . . .
- a. .f at exci tation in any one building the allowabic deficction of the pipe
. segment modeled and analyzed was based on a 4030 psi bending ~
stress. This criteria limits the maximum bending stress due (] to excitation in all three directions simultaneously to A-10
-a, e
CARGENTQLUNDY EN NEERS c,co APPENDIX A SL-3159 RE V.1, 7-29-77
]O 4000 h psi using the square root of the sum of the squares to combine the responses in accordance with NRC Regulatory Guide 1.92.
A-4.2 Derivation of Equations Figure A-4.2a Models and Nomenclature
] o i
3 e f = o =X g g
.. om ex x, umir """'
Cons &t EX, D, or ]o Model Used for Deflection Functions ] ] % 4= 1 = 3
, Consfant EI,D3m-Model Used for Natural Frcqucncy Det.crminations I
. 11 3
_. . . _ -- a
( CARGENTO LUNDY EN N RS APPENDIX A SL-3159 RE V. 1, 7-2 E-77 lo A-4.2 Nomenclature 60' = weight per unit length of beam a E = Youngs modulus k = I Area Moment of Inertia of Pipe Cross-section D = Outside Diameter of pipe - 1 = Length of span ehg = radian natural frequency of nth mode gg = period of nth mode Ys(t)= absolute support acceleration (a function of time 't') hI(ty= Response spectra acceleration (a function of T*t o r t.d ,t ) O gn (t) = generalized displacement of mode n
, T}g = Modal Participation Factor of mode n y(t) = Beam deflection relative to supports M (x, t) = Moment at beam cross sections V (x, t)= She;.r at beam cross sections ee
][ = Absolute acceleration A-4.2-1 Solution The equation of motion, using Euler Bernoulli Beam Theory and neglecting Shear Effects on curvature and Rotary Inertia can be written as follows for a beam segment
(]) between two supports. A-12 4
q CARGENTQ LUNDY J
""L',c"[,,E"5 APPENDlX A SL-3159 '] A-4.2-1 RE V. 1, 7-29-77 I+- '"
l l = 0 .] The absolute acceleration of any point on the beam can be rewritten as: J y = @) + y;a) (2) T j where f h*@ g = the acceleration of any point on the beam relative to the supports. The equation of motion may then be rewritten as: Y =~ 5 b) (3) [O { It can easily be verified by substitution into the homogeneous form of Eq. 3 that the mode shape for the nth mode of a simply supported beam is (sin "[ ) . The solution to Equation 3 can then be written as: I oo d) [ hn 44at) 3.D (4 )
- 93) .
Substitution of this into the uuation of motion yields: (5) aI *- N) O multiply each side of the equation by (sin ( " [ ) A-13
a l CARGENTO LUNDY E N G1N EE Rs c mc ac, APPENDIX A SL-3159 RE V. 1, 7-29-77 and sum over the m index J ll9? +'DWYy}~q-; =-%>f-~y
- )
Integrate both sides on x between o and f. ij -- t i j t 1 O (7)
.. ee k C-3(f) [ k 2. d,X
,=31 Integration:
-] I O m #m 44.nt> %1YX (a) A M rnTfx A Q=) \ ], O f T""
\
Sum the left hand side over the m index. It becomes
+ ( gw and the index on the right side can be changed to n. The equation can then be rewritte n as:
i 9 ., This will be satisfied if, for all n, Y b h [ / 5 A-14
CARGENTO LUNDY EN INE RS g,,, APPENDIX A SL-3159 A-4.2-1
- }
A. REV. 1, 7-29-77 i
)
Define
]= mwrrXA A
= Modal Participation l
} , Factor I Then the equation of motion for each mode is: ; ] !
} [+ k(* g= -
k(OM
, Using the standard spectral analysis technique bb l VCT4 h (d x2 n. (12) where Y ( Ts ) is the response spectra acceleration.
Therefore:.
-e 1
w o v-~ <x) = 2r .. ) M=/ v13 y _,m (' ) l ** .. 4
=. t Z T 4. Y (T ,d p wwx i
4:s 4 TT'2 y
) 2/ (14)
O ' % Mn 71 = I )=ydu = f, 4 o I, g 9 %. M Substitute:
=f{M M W3 (TN d 9t.#"X (15) n=1, 3, 5...
L I Calculation of Moment Distribution:
- O M cx) = E19. EI y b ,. = ! we n. % 74 gg,), ,,x,y (16) l e 1, 3, S' * =
- A-15 w- .I
CARGENTC LUNDY
} * * $j "do'" APPENDlX A SI..-3159 FE V. 1, 7-2 9--77 Calculation of Shear Distribution ]
3 v_=*El p=tavcu = *nx n = 1, 3, 5...
} The maximum shear occurs at x = 0 and x = 1 Vmax 2 1- q2T{y(Tw) (18) n=1, 3, 5...
} The maximum moment is calculated considering the first mode only.
M max 1 TI (T8} OI 7 # (19) T EL g max _ M o _ EDTF V(td g (19a) ) The maximum deflection is also calculated considering the first mode only. ymM ' d T# ~ g (20) 7T3 Considering Equations 19 and 20 ' 3 ~ frE E D Aas = 2 12 Y""# 7O A-16 l
CARGENT O LUNDY
' " $ c"."c,o* " " APPENDIX A SL-3159
.O i A-4.2-1 RE V, 1, 7-29-77
- ]
or 1 I 1 J Y allowable = 2(OM'Ejg (21) Using E = 30 X 10 6p3;
] G max = 4 X 10 3psi Y allowable =(2.70 X IOS (( D jL (22)
This is the equation of the 4000 psi cavelope.
]
The actual deflection is given by
"" p~N y3 (Td (23)
The maximum shear is calculated as follows. For accelerations ( Tg) on the left side of the response spectra peak as shown balcw.
] h left
=
/
s scle f O e Y m s \
)
t O r
=
.e A-17
CARGENTOLUNDY O E N GIN E E R S CMtC&t O APPENDIX A SL 3159 REV.1, 7 29 77 A-4.2-1 Equation 18 may be conaervatively rewritten as: l EI . . (24) J by = 7g Yed) E x^re n=1, 3, 5... This equation is used to calculate the Restraint Reaction Curves. The natural frequencies of the fixed - simple beam shown in figure A-4.2a are accurately approximated by: (25) a)x : (x+%t)*TT* fy ay JL n = 1, 2, 3... l Therefore,
.1 i 2.n 2 WA
- 1 7* ~
A ~ N + r4)*rr EIg (26) l
'! 1 In summury the following equations are used to form i
the design curves. (21) fE Y allowable = 2.(h E TT,a v for the allowable en.relope a (23) Y actual = T'1 Y(Ti) for the actual dis-O placement "3 A .o P
] CARGENT Q LUNDY
, E N GIN F E R S APPENDIX A SL-3159 REV. !, 7-29-77 (24) Vmax = CD) MT for the restraint loads due to 1 span n = 1, 3, 5...
These values should be doubled to calculate restraint loads because there are generally two adjacent spans being restrained by any one restraint. (25) ! for the natural Tx = Ot+%d Tf V E l } periods.
]O I
l' O I
- o b
LO . s A-19 f ~ Final
._ .._. _ _ _ . - ___.__.u- - _. u - - - -
----------.n_----
CARGENTO LUNDY ENG1NEERS C HIC AGO APPENDIX B SL-3159 RE V. 1, 7-29-77 weiowTsueeoaTs
}O B-1 Procedure for Weight Support System Design Starting from a convenient point (nozzle, structural anchor, header connection, etc.) the piping is traversed in steps, called half-spans, of length equal to one half the recommended span from Table B-1 (normal l ] span). The steps may be shortened to accommodate 1
l special piping components and must be supported on one or both sides according to the rules given below. Only l l 3 one ste;p is made at a time and each is assigned a unique ; integer label which is marked on an isometric of system. The isometric is included in the system design
] documentation along with the weight support system design
)
} work sheets (see sample problems). These worksheets list alJ steps nuvarico11y and include a description of the
] elements in each step, the length and recommended supports
, for each step,and the rules which govern the design l decisions. The worksheet. is t. sci as an ..id to system design and as documentation to show that the requirements l '
- of the standard have been met. Enough information should !
be presented to show that the designer has considered ! " i all relevant system characteristi ;. ) ! ' i t B-1
~ _ . _ . - . - . -_-_ .-__ - . __ _ -____ _
CARGENTG LUNDY E N G I N E E *t 9
*" " APPENDIX B SL-3159 RE V. 1, 7- 29-- 77 B-1 Procedure for Weicht Support System Design (continued)
The steps are made in a consistent direction and branch lines are traversed only after an end point of the main run is reached. Each step has two ends, A and B, where A to B is the direction of traversing. The support system is completely defined by specifying the length m of each step and the ends which require support. Note ) that end A of one step is end B of the preceeding step, but each support is listed only once on the worksheet. That is, if a given step must be supported on end A, it _Qb ]- is not necessary to indicate that end B of the previous step is supported. Similarly, if a support at end B is ; required, it is not necessary to indicate tl.at a support l is required at end A of the following step. The [ ! worksheet only indicates additional supports which i - l are required due to the characteristics of cach successive step. I-This procedure for establishing weight support locations l [ is summarized below. .
- 1. Pick a starting point I
r 2. Follow the line for a distance of one half the normal tO eieht suggort seen (one ster). r k B-2 - 6
- . . . . ~ . _ . CARGENT eLUNDY ENGINEERS APPENDIX B - SL 3159 REV.1, 7 29 77 .O B-1 Procedure for Weight Support System Design (continued)
- 3. Examine the components within this step and determine which ends of the section require support and whether or not a shortening of the span is required by the weight support system design rules.
- 4. Mark the end point of the step on the isometric and number the step. (Number steps with consecutive integers.)
Indicate the type and location of supports on the isometric.
~
- 5. Enter all pertinent information on the worksheet.
- 6. Starting from the end point of this step, go to 2 above and continue this procedure until all lines and branches have been covered.
. O 4
r e I 3 l l i i c l
*I
. CARGENTQ LUNDY GNO1NEEao APPENDlX B CHICAGO RE V. 1, 7-29-77
-() B-2 Rules for Locating Weight Supports
'3
- 1. A half-span of plain pipe must have a vertical support J at one end.
- 2. A half-span which includes an elbow must have a vertical
- ]
J support at both e,nds.
.] 3. The length of a half-span which includes a J concentrated weight of less than 10% of the normal span load (Table B-1) should not exceed 40% of the '] normal span length. It must have a vertical support J on one side. - ] 4. A half-span which includes a concentrated weight of from 10% to 40% of the normal span loa'd must have a vertical support on both sides.
- 5. The length of a half-span which includen a concentrated weight of more than 40% but less than 250% of the
]() nonnal span 1 cad should not exceed 10% of the normal span length and should have a vertical support on both sides. Tbis lenoth does not include the actual
{ length of the concentrated weight.
}
- 6. A concentrated weight which exceeds 250s of the ncrmal
]
span load should be supported directly rather tha:. by the piping to which it is attached.
} 7. The length of a half-span with one free end should not exceed 50% of the normal span length.
I
- 8. A halt-span with a concentrated w,ight should not have a free end.
- 9. Supports not required by taese rules should not be used.
M m l L (~) - 7 r i h B-4 l l t - a
l g CARGENTO LUNDY E N G 1 N E E R *' C H K At*U APPENDIX B l SL 3159 REV.1. 7 - 29 77 _ Tabic B-1 RECOMMENDEO se SPA!!3 FOlt DEAD W1:IGi!T SUPI'OltTS NOM. S'"O
- WATER-FILLED GAS-FILLED ROD DIAM, j
_SCH. S PA_!!* LO-\D (LB) SPAN
- LOAD [LB) DIAM.
3/8 0.049 wall 5'-11" 2 5'-6" 2 1/4
] 1/2 40 80 160 6'-5" 6'-6" 12 12 6'-10" 6'-10" 10 12 3/8 l
6'-6" 14 6'-7" 14 5/8 0.083 wall 6*-10" 5 7'-5" 5 1/4 (tubc)
] 3/4 40 80 7'-7" 7'-11" 16 20 8'-4" 8'-4" 16 18 3/8 3/8 i
I 160 7'-10" 22 8'-1" 22 1 40 9'-0" 26 9'-10" 24 80 9'-2" 32 9'-10" 20 ) 160 3/8 l 38 9'-2" 9'-6" 38 ! l-1/4 40 10'-5" 42 11'-7" 38 80 10'-9" 50 46 160 11*-6" 3/8 10'-10" 58 11'-5" 56 1-1/2 40 11'-4" 57 12*-1C" 48 80 11'-9* 64 12*-30" 58 160 3/8 , a 11'-10" 60 12'-6" 76 2 40 12'-9" 82 14'-9"
~
7: 80 13'-2" 102
, 160 14'-9" 94 3/8 13'-6"s . 136 14'-4" 128 2-1/2 40 14'-6" 138 16'-9" 120 80 15'-0" 168 152 160 16'-7' 1/2 15'-1" 202 16'-2" 190 1
3 40 15'-6" 210 la'-)" 199 80 16'-2" 248 18'-1" 232 160 1/2 16'-7" 326 17'-10" 306 j 3-1/2 40 16'-7" 272 19'-9" 232 80 17'-5" 340 19'-9" 302 XXS 5/8 17'-11" 520 18 ' - 11 496 i 4 4 40 17'-7" 346 21'-2" 290 80 18*-7" 436 21'-3" 394
~
160 5/8 19'-2" 584 20'-6" 542 The actual span should not exceed the recommended value by more than 1 foot. I B-5 a c) _ _
f CARGENTO LUNDY E N G1N E E RS B-3 Sample Problem emeno APPENDIX B SL-3159 RE V. 1, 7-29-77 o _ _f /A' . D' "f'.'-f.
@~ @ .b ) !
l
]
Fig. B-1. O I Pipe Size I/" Sch. 40 2 uu 22'O' O uu
] ,
\
1 0
]o / "". _
e*e , e . o g r. e e y 20th 1 H 51b ! l Figure B-1 is an isometric of sampic probl'em one. It includes labels for all steps, marks to indicate the end-points of steps, and symbols ( ) to indicate su.pport locations. The worksheet for this system is attached a44d should be -1 tua. tea with the following discussion. 1 H Step one is a hal::-span of plain pipe nupported at end A by the header. By rule one a support is required at one end. Since the i L ' } support at end A is provided by the header no actual hanger is 1 L q needed, so the worksheet indicates no required supports. The l ]: U y step length is'one half the normal span. The span load may be B-6 'O e
CAR 2ENT O LUNDY ENGINEERS APPENDIX B
**'*^
Sample Problem SL-3159
.} B-3 (continued) REV. 1, 7-29-77 11 ted on the worx deet, but is oa1r 1 gorteat for comgerieoa ]O with concentrated weights. Rule 9 is always used implicitly:
it is not indicated on the worksheet. Step two is also a plain half-span, but it is not supported at end A. Therefore, it must be supported at end B as is indicated
) on the worksheet. Si:.ce a support at end A is unnecessary it is not recommended.
Step three contains an elbow and so must be supported on both sides (Rule 2). The step length is measured along the tangent
] lines of the elbow, 1
lo Step four is plain pipe and is supported at end A (step three end B) so no additional support is required. Step five must be supported at one end. End B is choseri e,ince support at end A would put an unnecessary support on step four at end B.
]
Step six is also plain pipe and the support 2.t end B of section five satisfies the support requirexr.u. Step seven includes an elbow so it must be supported at both ends.
] Notice that this puts a support at end B of step six so that
, step six is a half-span of plain pipe supported at both ends. The B suggert is unnecessary for steg six dut neceesery for steg seven, o]
1
CARGENT O LUNDY E N G1N E E A5 C"'C " APPENDIX D SL-3159 RE V. 1, 7-29-77 A V B-3 Sample Problem (continued) so rule 9 is not violated. I Step B through 12 are plain pipe supported according to rule one as shown on the worksheet. Step 13 contains a valve whose weight is greater than 10% but less than 40% of the normal span load. Rule four requires that it be supported at both ends. This again causes a half-span of plain pipe (step 12) to be supported at both ends.
] Steps 14 and 15 are plain pipe subject to Rule 1.
Step 16 is less than 50% of the normal span but includes a branch which may be treated as a concentrated weight. Therefore, a support at end B is required by rule 8.
]
-]
]
- ) '
]
0 1 ] n-8
9 CARGENTO LUNDY E N GIN E EDS APPENDIX B I C"'C^' SL-3159 REV.1. 7-29-77 i WEIGHT SUPPORT SYSTEM DESIGN WORKSHEET
]
Line Identification Information WEIGHT SAMPLE #1 STEP SPAN PIPING ELEMENT S U PPOR'l STEP DESIGN SO. l NORMAL SPAN l LOADDESCRIPTION A 13 LENGTH RULES . I 11' - 4" 52 lb. Plain Pipe 5' - 8" 1 2 11' - 4" 52 lb. Plain Pipe 5' - 8" 1 3 11' - 4" 52 lb. Elbow X X 5' - 8" 2 4 11' - 4" 52 lb. Plain Pipe 5' - 8" 1 5 11' - 4" 52 lb. Plain Pipe X 5' - 8" 1 6 11' - 4" 52 lb. Plain Pipe 5' - 8" 1 7 11' - 4" 52 lb. Elbow X X S' - 8" 2 8 11' - 4" 52 lb. Plain Pipe 5' - 8" 1 9 11' - 4" 52 lb. Plain Pipe X S' - 8"
- 1 10 11' - 4" 52 lb. Plain Pipe 5' - 8" 1
_ 11 11' - 4" 52 lb. Plain Pipe X 5' - 8" 1
] 12 11' - 4" 52 lb.
Plain Pipe 5' - 8" I n 13 11' - 4" 52 lb. 20 lb. Vnive '
\ \ 5' - 8" 4 g 1 14 11' - 4" 52 lb. Plain Pipe 5' - 8" I h 15 11' - 4" 52 lb. Plain Pipe X 5' - 8" I c
16 11' - 4" 52 lb. Free end Cone. wt X 5' - 8" 8 [O , I B ') b Final e. t
CARGENT Q LUNDY E N GIN E Eno APPENDIX C SL-3159 REV.1. 7-29-77 13 SEISMIC SUPPORTS SYSTEM DESIGN The nature of seismic loading is similar to that of weight loading: a distributed force acts upon each element of a piping system in proportion to its mass. However, the seismic loading is horizontal as well as vertical. Therefore, a procedure similar to that which is used for locating weight supports may be used to locate seismic support.< if provision is made for including horizontal restraints at these locations. Regarding vertical seismie loading, one set of restrainte enn serse as both weight supports and vertical scismic restraints. Choose the shorter of the weight span and , vertical seismic span for_the building in which the, system is locate.d. Once the system is adequately restrained to resist vertical seismic loading, the system must be restrained for the two horizontal scismic loadings. For vertical pipe
] runs, two orthogonallateral supports are required at each r_estraint location (choose the shor'.er of the E-W and N-S spans). For horbntal runs, one horizontal restraint is l
required at each location. The following procedure is recommended for location of : O LJ these horizontal scismic restraints. C-1 Procedure for Seismic Support System Des ,7 Starting from a convenient point (nozzle, st ntural anchor her der connection, etc.) the piping is traversed in steps, called balf-spans, of len, th equal to one half the recommended span from Tatle C-1 (normal seismic ! >an). Th" steps l 3 may be shortened to accommodate special piping componen s and must be
,J supported on one or both sides according to the rules given be civ. Only one l
step is made at a time and each ir asched a ' nig te in'.cger abel which 13
,,, marked on an isometric of the system. The isomety is included in the system design documentation along with the se's'nic support -" stem design orks'ieets (see sample problems). These worksheets lis* all steps numeric: illy and include a description of the elements in each step, the length and rceommended supports for each step, and the rules which govern the design decisions. The worksheet is used as an aid to system design and as documentation to show that the requirements of the standard have been met. Enough information should be
!= presented to show that the designer has considered all relevant system O enaiacteristics. 1 < c-1 b
CARGENTO LUNDY
, ENGINEER 9
***^*
APPENDlX C SL-3159 REV.1. 7-29--77
'Ihe steps are made in a consistent direction, and branch lines are traversed only after an end point of the main run is rehehed. Each step has two ends, A and F, where A to B is the direction of traversing. The support system is completely defined by specifying the length of each step, the ends which require support, and the support types. Note that end A of one step is end B of the preceding step, btit each support is listed only once on the worksheet. That is, if a given I step mi.st be supported on end A, it is not necessary to indicate that a support is J
required at end A of the following step. The worksheet only indicates additional supports, which are required due to the characteristics of each successive ste[. A summary of this procedure follows.
- 1. Pick a starting point.
- 2. Follow the line for a distance of one half the normal seismic support span
] (one step).
- 3. Examine the components within this step and determine which ends of the Q section require support and whether or not a shortening of the span is required by the seismic support system design rules.
- 4. Mark the end point of the step on the isometric and number the step.
(Number steps with consecutive integers.) Indicate t'.e type and location of supports on the isometric.
- 5. Enter all pertinent information on the worksheet.
~
- 6. Starting from the end point of this step, go to 2 above ano continue ti.rs l procedure until all lines and branebes h9"e been covered.
]
l l C-2 Rules for Locating Seismic Supports
] 1. A horizontal half-span must have a horizontal, lateral restraint at one end.
] 2. A ~ vertical half-span must have two orthogonal, horizontal restraints at one end.
- 3. A ha f-span which includes a bend and lies in a vertical plane must be
! g suppcrted at both ends--a horizontal, lateral support at the horizontal end
. and two orthogonal, lateral supports on the vertical end (see rule 14). i e
1 c-2 . 1
- - m ,-- ----
CARGENT O LUNDY ENGlNEER5 CMsCAGO APPENDIX C SL-3159 RE V. 1, 7 77 o 4. A straight, horizontal section of pipe which is less than 4/10 of the normal span in length requires no horizontal restraints. It is treated as a concentrated weight in its axial direction.
- 5. A horizontal section of pipe whose length exceeds 4/10 of the normal span must be restrained along its axis.
- 6. A half-span which contains a concentrated weight of less than 10% of the normal seismic-span weight should not exceed 40% of the normal-span length. It should be supported on one side with horizontal restraints.
- 7. A half-span which includes a concentrated weight of from 10% to 75% of the normal seismic-span weight must be supported on both ends with
] 8.
horizontal restraints. The length of a half-span which includes a concentrated weight of more tnan 75% but less than 250% of the normal seismic-span weight should not exceed 10% of the normal span (exclusive of the actual length of the
~ j concentrated weight). This half-span should be supported on both ends by
]O horizoatel suggerts.
)
] 9. A concentrated weight which exceeds 250% of the normal scismic-span weight should be supported directly, rather than by the piping to which it is attached. Horizontal support i.; required at the center of gravity.
] 10. In general, motor operators fo valves should be restrained in three
] orthogonal directions. For vertically mounted operators, only horizontal, .
lateral support is required. i 2
- 11. A half-span with a concentrated weight shou ~ not have a free end: hori- i 3 zontal, lateral support should be provided.
- 12. Supports not required by these rules alc Ed not be asca.
- 13. If the distance, between adjacent rigid is ngcts exceed- the normal seismic support span, vertical supports shoulc~ be added between these rigid
. hangers.
14.' 'As an alternative to rule 3, a half-span which includes an elbow may end at the elbow and be supported at a tangent point. O 1 l E I 1 ? 1
'1 w CARGENTQ LUNDY E N G 1 N E E C7 8 c .cac.o APPENDIX C SL-3159 REV.1, 7-29-77
'30 i.
TABLE C-1 REACTOR BUILDING RECOMMENDED SPANS FOR SEISMIC SUPPORTS 1 N O Al . N ORTH-SO U TH EAST-W EST \ ERTIC A L DI A M . Scil. SPAN LOAD SPAN LOAD SPAN LOAD 3/8
- 0. 9 q_ 7 1.25 7 1.25 4 1.0 1/2 160 10 16.75 9 9.50 6 15.5
- 5. og8a" s, e 3.0 e 4.25 e 4.50 3
3/4 160 11 14.25 11 22.0 7 24.0 Q 1 160 13 33.0 12 23.0 8 38.5 ' il 160 15 51.5 14 40.0 l 10 63.25 il 160 16 58.0 47.75 _15 10 79.25 ] 2 160 18 91.0 17 81.75 12 141.25 24 160 20 133.0 19 126.75 13 205.0 l 3 160 - 22 178.0 21 185.5 14 271.25 34 80XS 24 265.5 23 26i.0 15 317.75 4 120 26 441 24 299.5 16 423.25 UNITS: NOMINAL DIAMETER - IN. SPANS - FT. LOADS - LBS. I
- o .
C-4
f, CARGENTQLUNDY ENGINEERS APPENDIX C a ** ' ! SL-3159 REV.1. 7-29-77 1 b' TABLE C-2 TURBINE BL'ILDit!G RECOMMENDED SPANS FOR SEISMIC SUPPORTS r NOM. NORTH-SOUTH E AST-W EST DIAM . SCll. VERTICAL SPAN LOAD SPAN LOAD SPAN LOA { 0 9 3/8 5 0.75 6 1.75 4 1.0 1 1/2 160 7 8.25 8 15.75 5 8.0 5/8
- 0. 83 L 6 2.50 8 6.25 4 2.0 3/4 160 8 14.25 10 34.75 0 1 160 9 22.25 11 54.25 5 11.0 6 26.0 Il 160 10 33.25 13 84.75 7 41.5 11 160 11 46.75 14 114.0 8 59.0 2 160 13 77.0 15 105.0 9 98.75 21 160 14 117.75 17 214.75 10 146.5 3 160 16 187.08 19 357.0 11 243.75 34 80XS 17 195.0 20 321.5 12 244.0 4 120 18 289.0 ?2 6P" " 12 371.0 l
) i l i [ UNITS: NOMIN AL DIAMETER - IN. SPANS - FT. h LOADS - LHS. l r u e LO I . 1 i
- n. C-5 l J !
t T*' CARGENTQ LUNDY cuosuceno APPENDIX C SL-3159 REV.1. 7-29-77 h [] TABLE C-3 RHR COMPLEX RECOMMENDED SPANS FOR
, SEISMIC SUPPORTS r
NOM. N ORTH-SOUTH EAST-WEST DIAM. VERTICAL SCH. SPAN LOAD SPAN LOAD SPAN LOAD 3/8 0 49 L 5 0.75 6 1.50 6 1.00 1/2 160 7 8.25 8 18.0 7 9.50 0.083 5/8 7 2.50 8 5.25 8 3.25 3/4 160 8 14.0 9 26.5 9 16.5 1 160 10 22.0 11 46.75 10 25.75 14 160 11 34.75 12 ti8. 75 12 40.75 li 160 12 46.75 13 91.75 13 55.0 2 160 13 75.5 15 158.0 14 89.0 21 160 15 115.5 17 239.50 16 135.75 1 3 160 17 183.5 18 223.25 18 216.0 3i 80XS 18 191.5 20 394.0 19 225.0 4 - 120 19 294.5 21 582.0 , 20 333.5 i i UNITS: NOMINAL DIAMETER - IN. SPANS - FT.
] LOADS - LBS.
t o , C-6 l u e
._,. car 2 GENT O LUNDY E N GIN E E Rs APPENDIX C c .cao SL - 3159 REV.1. 7- 29 77 C-3 Sample Problem Following is an isometric of a system for which horizontal seismic restraint locations have been chosen according to the seismic support system design rules. The isometric is marked as required by the procedure and the worksheet is completed. Certain characteristics of the support system cannot be defined g without consideration of thermal expansion and anchor movements. These J include locations where snubbers rather than rigid restraints are to be used and preferred locations for axial restraints. ] The support description includes the end which is supported, the number of restraints and the restraint orientation. "B-2-liOR-LAT" means two horizontal, lateral supports are required at end B.
s Jo 3
] ] ]
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c F s ,, 160 lb. 2 ' ler.g g 3 0 f i (< P1 Y x* L_3 ,
, , FIPf SIZF: 2" M.F . 160 dP WT./FT.:
NORPAL SEl9tlL Str. 20 it. (Horizontal), g, t.0 Ft. (Verrfeal) NORMAL SPAN W ICPT: '90 l b.
- mm>
Qc==a ISOMETRIC FOR SAMPLE SEISMIC PROBLEM .mm Y -. G 2
=9 p o b 7 d
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f CARGENT' O LUNDY j ENGINEERS APPENDIX C , c mu.c." SL- 3159 REV.1. 7-29-77 p
'd SEISMIC SUPPORT SYSTEM -DESIGN WORKSHEET I
s l 5.P NORMAL SP/ N SUPPOR'l% S i l l' IHNii s N jN O. SPAN W EPdlT PlPING El,LMEN r 1)ESt:RIPflON A 18 1.ENilTil ItUI.IN t 'OM M I N IN Fixed at End A g i 20' 190 10. Vert. with 281b. valve B-2-l!OR-LAT 10' T- , 2 , Bend in Vertical Plane B-1-ilO R-L A I 3 f l 3 Plain Pipe ; i l l 4 ; Plain Pipe Il- 1 -llO R-i- A I I l l 5 Plain Pipe I l l 14 190 R-l. 41' l l j b Plain Pipe Ending at Elbow li- % \ l l 5 l j 3 ' 7 Plain hoc I LAT. Suppori at 7A Acts al Plain ISpc Endung ut Elbow ll- t -ilO R- LA I I,5 Axistly Plain Pipe Elbow in
, 9 Horizontal Plane I lbl-HOR-L AT g
10 j Plain Pipe Ends at Elbow 11- A Al 14,5 l l11 l Plain Pipe (vertical) l 2 l I /-~jl2 l f Section Ends at Tee l B-t-liOR-LA I 5' l 2 l l IJ Plain Pipe H-2-HOH-L A r 10' i ! i { g 14 Plain Pipe witti Lit >ow Il- 1 -ilOR-L A I 3 15 Plain Pipe 1 in Plain Pipe it-i-HOR-L AT I I; Pinin Pape I lia \ l les l'inin Pym l.'nel, nl 1.ltam li ? !!Oli 84 I 3. 5 u f 19 Plam ISpc l l l I h I 20 Pemt in Vertical Pirene it-I flor-l.? ! I n' 14 l l f 21 Plain Pipe 1 7' l 1 l l
- e. .iuiH. A i
' , Suppict Motor 22 l~ 160 lp. valve iH - HO R-L A T 4' ! 8,10
, Opere tor 2J '
f Plain Pipe Fixed at End 11 '- f 1
' 24 Plain Pipe Supported at End A '
l l l 10' I f
- l-llO;1-L A I ' '
25 l Plain Pipe (Ending at elbowl I- A X I 5' 5,14 l L
, %ertical Plain Pipe 26 Fased at End H
, 10' g,1 V(
h
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C-9 Final j
CARGENTQLUNDY EN GIN E E R s APPENDIX D c nc^" SL-3159 FLEXIBILITY SUPPORT SYSTEM DESIGN REV. f, 7-29-77 D-1 Procedure O Starting at a convenient point (e.g., equipment nozzle, r structural anchor, header connection) traverse the entire .1 system once for each orthogonal direction of thermal move-ment, following the steps below for each successive pair of adjacent parallel (i.e., acting in the same direction) restraints. 1 i On the thermal worksheet, identify the restraint pair 1. , and direction, l
- 2. Determine the total expanding length of pipe in the restraint direction between the pair and enter it on the worksheet. If one of the restraints is a header or equipment nozzle with thermal movement in the restraint direction, enter this movement on the work-sheet.
I
- 3. From Table D-2, obtain the required offset based on I expanding length determined in step 2 and pipe size, and enter it on the thermal worksheet.. If one of the restraints is a header or equipment nozzle, .from Table i D-1 obtain the offset required based on thermal move-ment and nipe size, and enter it on the worksheet.
-O k 4. Determine the actual existing offset - total length of D-1
]
g gg g g g M M M M M h h h M M h M U \ O O O ; TABLE D-1 MINIMUM OFFSET NEAR NOZ ES WITH EXPANSION MOVEMEPE (*
!!ominal DEFLECTION, I NCH. lZ -
Diawster i Q'O In:h _1/4 y1 3/4 1 _1,- 11 1-1/2 1-3/4 2 2-1/4 2-1/2 . 3/8 (tube) 3ft 61n 4ft llin 6ft lin 7ft Oin 7ft loin Hft 71n 9ft 31n 9ft loin 10ft 61n lift Oin 1/2 3ft 111n 5ft 6in 6ft 91n 7ft 91n 8ft 9in 9ft 6in' 10ft 3in 11ft Oin llft 8in 12f t . 4in 5/6 (tuba) 4ft 2in 5ft 10'i r; 7ft 2in Oft 31n 9ft 3in 10ft lin 10ft llin lift 53in 12ft Sin 13ft lin 0 3/4 4ft 41n 7ft 61n 6ft 2i r: 8fs 91n 9ft 9in 10ft 8in 11ft 6in 12ft 41n 13ft Oin 13ft 91n 1 4ft loin 6ft lii: Bft 5in 9ft 91n 10ft 111n 11ft 111n 12ft 111n 13ft 91n 14ft 7in 15ft Sin $ 1-1/4 Sft 6in 7ft 9ir m3 9ft 61n 30ft 11in 12ft 32n 13ft Sin 14ft 61n 15ft 6in 16ft Sin 17ft 41n 2 O y 1-1/2 Sft loin Bft no m 3i-10ft 2in Ilft 91n 13ft !in 14ft 4in 15ft 61n 16ft '* in 17ft 6in l'Jf t 61D - 2 6ft 61n 9ft 3i 11tt 4in 13ft lin 14ft */ i n 16ft 'in 17ft 41n 18ft sin 19ft 7in 20ft Bin 2-1/2 7ft 2in 10ft 2. a r-12ft 6in 34ft 41n 16ft Iin 17ft 3in 19ft Oin 20ft lin 21ft 71n 22ft 91n *Cz 3 7ft 111, 11ft 3i- O 13ft 91n 15ft loin 17ft 9fn 19ft 5in 21ft Oin 22ft iin 23ft loin 25ft lin "< 3-1/2 Hft 6in 12f t Oi 14 sin 17ft Oin 19ft Oin 20ft 91n 22ft 61n 24ft 'in 25ft 61n 26ft loin 4 9ft nin 12ft 9i .Sft 7in left Oin 20ft ;in 22ft Oin 23ft loin 25ft ein 27ft Oin 28ft 61n (a)This is the minimum lenti th ni piae which is installed perpendicular to the Sirection of no zie move nent between the nozzle and the firsi. r. considered. traint wht-5 acts in that direction. Movements in three orthw onal directions are'
- D (/) >
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O - O TABLE D-2 MINIMUM OFFSET REQUIRED TO ACCOMMODATE THERMAL EXPANSION OF PIPING, FEET EXPANDING LENGTH OF PIPE., FEET N)minal ,, Diam?ter, i; Inch f
! 10 15 20 25 30 b 35 40 45 50 I 3/8(tubs) 1*-11" 2'-9" 3*-4" 3'-1C" 4'-3" 4'-8" 5'-1" I 5'-5" 5'-9" 6'-1" 1/2 U 2'-2" 3'-0" 3'-8" 4*-3" 4'-9" 5'-3" 5'-8" 6'-1" 6*-5" 6'-9" M ;
5/8(tube) 2 ' - I 3'-3" 3'-11" 4'-6" 5'-1" 5'-7" 6'-0" > 6'-5" 6'-10" 7'-2" j ,3 'l 3/4 2'-5' 3 '-5 ' 4'-2" 4'-9" 1 2 0 m e 5'-4* 5'-10" 6'-4" 6*-9" 7*-2" '7'-7" s no Z u 1 2'-t' 3'-9" 4'-8" 5'-4" 6*-;" 6*-7" 7'-1" 7'-7" z_d 5 i 3'-C" 8'-5" g ,zg, ' 1-1/4 3'-;" 4'-3" 5'-2" 6'-O" 6'-3" 7'-4" 7'-11" On 8'-6" 9'-0" 9'-6" ah 1-1/2 3 -3* 4'-7' 5'-7" 6'-5" 7'-2" 7'-11" 8'-6" 9'-1" 9'-9"
*Z 10'-2" D =2 3'-7" 5'-1" 6*-3" 7*-2" 8'-5" 8'-10" '
9'-S" 10*-2" 10'-9" 11'-4" 2-1/2 3'-11" 5'-7" 6'-10" 7'-11" a*-10" 9'-9" 10'-5" 11'-2" 11*-10" 12'-6"
~
3 4*-4" 6'-2" 7'-7" 8'-9" 9'-9" 10*-8" 11'-7" 12'-4" 13'-1" 13'-10" 3-1/2 4'-8" 6 * - 7 8*-1" 9 '-4 " 1C'-5" 11'-5" 12'-4" 13'-2" 14*-0" 14'-9" 4 4'-11" 7'-0" 8'-7" 9'-11" 11'-1" 12'-1" 13'-1" 14'-0" 14'-10" 15'-8"
% (A > ,
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k CARGENTOLUNDY ENG1NEERS APPENDIX D c.ucaso SL-3159 1 pipe in the two directions perpendicular to the REV 1, 7-29-77 O ,I restraint direction between the restraint pair.
- 5. Check whether the actual offset exceeds the required offset. For restraint pairs with both expanding 1ength and header or equipment nozzle thermal movement, the actual offset must exceed the sum of the associated t required offsets. If the actual offset exceeds the
~I required offset, move onto the next restraint pair.
If the actual offset is less than the required offset, one of the rigid restraints must be changed to a snubber
~
and/or a variable hanger, or an expansion loop must be O erovided. cenere11 1 . cheneine the reetreine eve is preferred.
, 1 D-2 Sample Problem
~
I Replace w. snubber and S>rino l .
~
10' _ __ g JT .75 2 ' MA
, ,3. .
~
10 C_,L 15' anch >rF l /as 3. S' / D 2p EC i O~ .
. C .N change to snubber '
D-4
l. CARGENTC LUNDY APPENDIX D E N GIN E E R 5 CHICAGO SL-3159 REV. 1, 7-29-77 The above system will be checked for thermal flexibility; pertinent data will be entered on the thermal worksheet. The global X-direction will be considered first. Starting at the header, the first X-direction restraint pair is identified as A-C. The X-direction expanding length is the 10' from A to B; from Table D-2, the offset required for 10' is 5'1". The X-direction header movement of 0.25" must also be considered for restraint pair A-C - the offset required from Table D-1 is 6'6,". The amount of actual offset available (total length of pipe perpendicular to the X-direction) is the 10 f t. from B to C Since 10 f t. is less than the total 11'7" offset required, the C rigid i strut is changed to a snubber.
, i f Since the restraint at C is now a snubber, X-direction I restraint pair A-E is considered. The 25' (10' frcm A to B plus 15' from C1 to E) expanding length requires an 53'0" offset. The 0.25" header mcvement requitec 6'6". The }I total actual offset, 15 ', (i . e . , 10' from B to C plus 5' from C to C1) exceeds the total 14'6"~ required, thus accom-modating the X-direction thermal movement.
Considering thermal movement in the Y-direction, restraint pair A-B is examined first. Since there is no Y-direction i piping between A and B, no accommodation for piping expansion a l D-5
CARGENTQLUNDY E N G I N ER ERS APPENDIX D SL-3159 REV.1, 7-29 77
.O I is required. The Y-direction header movement at A, 0.75",
requires 11'4" of offset. The actual offset available is the 10' from A to B. Since 10' is less than the required 11'4", the rigid strut at B.- hich provided both weight support and seismic restraint - is replaced with a variable
' hanger at B and a Y-direction snubber in the immediate vicinity of B or C. Next, restraint pair A-D is checked.
'I The expanding 10 ' from B to C requires 5 '1" offset. The 0.75" Y-direction header movement requires 11'4". The existing
. offset, 17' (i.e., 10' from A to B plus 5' from C to Cl plus
.10 2' from Cl to D) exceeds the total offset required, 16'5", and is therefore adequate. Regarding restraint pair D-E, no l l d Y-direction anchor movement or piping e xpansion exists. Ig Regarding Z-direction movement, restraint pair A-D is l -3 i considered. The 1.5" header movement requires a 16'0" offset. The 5' run from C to Cl requires a 3'7" offset. The 22' ] actual offset exceeds the total rcquit re ef fect and is there- [ fore adequate. Regarding the D-E restraint pair, no Z-direc-tion movement or piping expansion exists. J o a k n-6
CARGENTO LUNDY NEERS APPENDIX D E N Gj,g SL-3159 RE V. 1, 7-29-77 THERMAL EXPANSION WORKSHEET Restraint Expanding Nozzle Required Actual Pair Dir. Length,ft. Movement,in. Offset, ft. Offset,ft. Recommendation A-C X 10 25 5'1" 6'6" 10 Change to snubber A-E X 25 .25 8'0" 6'6" 15 ok A-B Y 0 .75 0 11'4" 10 Replace w, snubber and spring A-D Y 10 .75 5'1" 11'4" 17 ok D-E Y 0 0 0 0 13 I A-D Z 5 1.5 3'7" 16'0" 22 ok ok D-E Z 0 0 0 0 13 ok 10 J-I
~I J
l 1 No 1
. D-7 Final E .
CARGENT O LUNDY ENGlNEE20 CHICAGO APPENDIX E SL-3159 N f (o REV.1, 7 77 SMALL PIPING DESIGN WORK SHEETS sI WEIGHT SUPPORT SYSTEM DESIGN WORKSHEET 'l I Sm NO SPAN ee-LOAD e1P1- E-DESCRIPTION e-A b eTEe LENGTH Deem. RULED i I LI ,1 i l
- 10 I
I 1 , j , me -M-- wg I o Il m\ p E-1
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m*@2mmDO QEEo >1k2ExM ur wGS - mm . wi"T M S r M f f E t m o C . M NS GE IL SU M ER - D - H PT M EG TN . SE L r r W d n B S S . K T R R O W W T O P P I G U I S S A E D a T S ! Y ! O S I T T R P I O R P C P S U E S D C P I T M ? E S M I l E 5 S L E =
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=3 SARGENTO LUNDY ENGINEERS
*"'*** APPENDIX E SL-3159 REV.1. 7-29-77 THERMAL EXPANSION WORKSHEET I Restraint Pair Dir.
Expanding Length, ft . Nozzle Movement, in. Required Offset, ft. Actual Offset , ft . Recommendation 1 1 1 1 _le
- I o
E-3 l- Final
DOCU V'i = M i 2 PAGE _ B U-- ' A\ O. smwose NO. OF PAGES 8 YnoLFS REASON-O PAGE ILLEGIBLE: PDR CF l O HARD COPY FILED AT: ) OTHER 1
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l EF- 2-FSAR
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[ DRYWELL ELEV. 662'-b" FLANGE PRESSURE VESSEL FLANGE STABILIZER TRUSS
\ ELEV. 647'-6" ll 4 t
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, PRESSURE ,
.$ VESSEL I r, i.
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S 5 PLATFORM ELEV. 607'-0" E i >r -- _.1 I '; ' I
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l ,* * * $ , ENRICO FERMI ATOMIC POWER PLANT UNIT 2 FINAL SAFETY ANALYSIS REPORT , I .. FIGURE 3.7-14 SECTION THROUGH LENTER LINE OF DRYWELL (* 1 sanoeur wuoy mont uo. so-a.2 l l .
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. . . . . . . 18 9 DRYWELL BELLOWS
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X - DIRECTION 4 93 ' REFUELING BELLOWS ONLY 25g[// CONTAINMENT 17 i s VESSEL 3 16 ' 24 s', 32
.......( ) . . . . g . . 3. , ; , "ll STABILIZER i 23,', i 31 4 g SACRIFICAL 15f22h I
- I SHIELD 2
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=.......( ) 19 28js 12 C' l
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//O///ON$/OJ/////////////$/ i ENRICO FERMI ATOMIC POWER PLANT UNIT 2
. FINAL SAFETY ANALYSIS REPORT '
FIGURE 3.7-15 REACTOR / AUXILIARY BUILDING HORIZONTAL DYNAMIC MODEL SARGENT & LUNDY REPORT NO. SL-2682 -
l EF- 2-FS AR TABLE 3.7-8 REACTOR / AUXILIARY BUILDING PROBABLE MAXIMUM DISPLACEMENTS Horizontal Displacements, " ft OBE SSE Mass X-Excit. Y-Excit. X-Excit. Y-Excit. No. X-Disp 1.,ft_ Y-Disp 1.,ft X-Disp 1.,ft Y-Disp 1.,ft 1 0.00110 0.00095 0.00157 0.00136 2 0.00257 0.00245 0.00366 0.00349 3 0.00376 0.00260 0.00535 0.00469 4 0.00430 0.00376 0.00611 0.00534 5 0.00483 0.00340 0.00686 0.00594 6 0.03502 0.03240 0.05082 0.04623 7 0.00149 0.00117 0.00209 0.00164 8 0.00330 0.00143 0.00465 0.00201 9 0.00491 0.00500 0.00692 0.00705 10 0.03500 0.02780 0.05080 0.04040 11 0.00490 0.00310 0.00689 0.00465 12 0.00070 0.00040 0.00094 0.00060 13 0.00110 0.00070 0.00157 0.00102 14 0.00250 0.00160 0.00357 0.00252 15 0.00310 0.00210 0.00436 0.00322 16 0.00380 0.00270 0.00536 0.00419 17 0.00430 0.00320 0.00610 0.00485 18 0.00480 0.00390 0.00689 0.00600 19 0.00090 0.00060 0.00126 0.00086 20 0.00150 0.00100 0.00208 0.00152
' 21 0.00220 0.00160 0.00314 0.00238 22 0.00260 0.00190 0.00371 0.00284 23 0.00310 0.00220 0.00441 0.00341 24 0.00380 0.00270 0.00536 0.00419 25 0.00420 0.00300 0.00602 0.00466 26 0.00440 0.00320 0.00625 0.00483 27 0.00490 0.00350 0.00698 0.00539 28 0.00100 0.00060 0.00140 0.00097 29 0.00140 0.00090 0.00212 0.00164 30 0.00180 0.00120 0.00263 0.00200 31 0.00290 0.00190 0.00409 0.00306 32 0.00380. 0.00270 0.00540 0.00415 Floor Vertical Displacement (a)
Elevation OBE SSE Elev. 583 ft, 6 in. 0.00013 0.00020 (1st Floor) Elev. 613 ft, 6 in. 0.00026 0.00039 (2nd Floor) Elev. 641 ft, 6 in 0.00035 0.00052 (3rd Floor) Elev. 659 ft, 6 in 0.00039 0.00057 (4th Floor) Elev. 684 ft, 6 in. 0.00044 0.00064 (5th Floor) O (a, Displacements are relative to the base of the structure. l 3.7-75 I .
s 0 EF-2-FSAR i F R EQUENCY, CPS 90 33 20 10 SA 3.3 2A 1A 05
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