ML20212M178
See also: IR 05000428/2005002
Text
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.. . a . , . - - 3 _ , MAY 1 5 1975 175 . .: / R. R. Maccary, Assistant Director for Engineering - Division of Technical Review HIGHLIGHTS OF PG&E DIABLO CANYON PLANT SEISMIC DESIGN AUDIT From April 28th to May 2nd,1975, the members of the Structural Engineering Branch and Mechanical Engineering Branch have per- formed a seismic design audit of the Diablo Canyon Plant at the PG&E office in San Francisco. Present for the applicant wem PG&E, Westinghouse and John A. Blume Associates engineering staff. In an earlier meeting held in Bethesda on April 4,1975 between the NRC staff and the applicant, general guidelines and scope for the seismic design audit were discussed in considerable detail as part of the preparatory work for the subject audit. A list of the attendees is enclosed. 6 . The primary objective of the NRC staff was to conduct a seismic design audit of the subject plant. The results of the audit would then be used as basis for judging seismic design adequacy of the plant. , liighlights of'the audit are susnerized below. 1. NRC staff opened the meetings by first stating the objective. of the audit program and defining the specific scope and depth of the week long audit plan. 2. PG&E, its NSSS vendor; Westinghouse and PG&E consultant John A. Blume Associates made presentations on the seismic design criteria, methodology and procedums used in the subject plant. The pmsentations generally followed the technical subjects included in the plant FSAR and were judged as satisfactory by the NRC staff. - 3. A sample list of Category I structures, systems and components of the Diablo Canyon plant covering safety functions similar to those included in Table X-l of Appendix X to the Rasmussen Report was reviewed for, their adequacy of seismic design qualification 8608250403 860001 PDR FOIA - ' - % HOUCHC36-391 PDR /I~# y - - . - . . . - . . _ . . . . . ..
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. . . . . . . . . . _.. eusmanes > . . . - . _ . . . . . . _ . . . . .. . . . . _ . . _ . A -3s =a'=* _...._ _ . . . . . . ._ _ pr-35 Porn ABC 318 (Rev. FSS) ABCM 0240 W u. s. oovanneesser pasavuse orreces s.74.sa see . , , - - - . . - - , . _ . _ - . . , - . . _ _ - -.- - . , _ . - - . -
- - - - - - - - . . - . . -. . . - . . c e . }) .' ) > R. R. Maccary - -2- MAY 1 9 1975 _ and documentation. The audit staff found that all the Category I structures, systems and cogonents included in the list were properly qualified (i.e.,100% successful qualification as com- pared to 27% failure to demonstrate adequacy indicated in AppendixXoftheRasmussenReport). 4. Following the above item 3 overall qualification audit, two structures and four components and systems (i.e., containment building, turbine building, steam generators, reactor coolant pump, steam generator support and pump support) were selected for detailed auditing by going through check list items. In addition, the analyses and test reports of six electrical equipment items (i.e., diesel generators, hot shutdown panel, main control console, nuclear instrunentation system, reactor trip switchgear and pro- tactive relay board) were also selected for detailed auditing. Except for the turbine building and a few missing data pertaining to the cowonents and systems, which PG&E will provide in a future transmittal to the NRC staff for confirmatory review, the results of the detail audit of these structures, systems and components MMM .. were found satisfactory and acceptable. - 5. Some of the audit staff took a field trip to inspect selected Category I systems and components. The group concluded that the selected components and systems had been qualified for service under seismic loads by acceptable testing and analyses. The group also recomended and PG&E agreed that the installation of field run Category I piping (2-1/2 inch diameter and smaller) be reviewed by the PG&E engineering staff to ensure that the accept- able field installation procedures were fully implemented. 6. The audit staff also reviewed the applicant's and its vendor's design control programs. The methods of design control and co- ordination utilized by PG&E, Westinghouse and PGSE consultant (JAB) were reviewed and discussed. It was established that adequate control procedures were followed in checking and approv- ing engineering calculations and drawings. The design control program implemented in seismic design of Diablo Canyon was judged satisfactory and acceptable. 7. The ACRS questions related to seismic design of the Diablo Canyon plant were discussed. The discussion yielded some technical viewpoints, which form part of the bases for formu- lating future response to the ACRS questions. - .. - __ - " ' ' * * * . . . . ~ . _ _ . . . . . . . _ . . ._ _ , , , , , "**I - ..... ..m. . . . , ,, , , , , , , , , , , . , , , _ , oate > . . . . . . ., . , , _ , , , _ ., Forum AEC.38 3 (Re.. p.13) ABCM 0240 W u. s. eovenmasant enentime orricas s.74.sas. nee .
. - . . . . . . . - . .- . . . . . o .- . , , , .. . , . . = ') , .. - s- R. R. Maccary -3- 8. The NRC audit staff also reviewed various computer programs used for the design of Category I structures, sys.tems and com- ponents by PG&E, JAB and Westinghouse. For programs that are not available in public domain the program verification pro- cedures adopted by PG&E and its vendor / consultant were found to follow the criteria acceptable to NRC staff. 9. A few items, for which additional information is required, have been identified during the course of the audit. The information pertaining to the items will be provided in two to four weeks by PG&E and its vendor / consultant for NRC staff confirnatory review. At the closing of the audit meeting, NRC audit staff concluded that based on the above described results of the seismic design audit, the seismic design methodology, procedures and design controls implemented for the plant were in general found satisfactory and acceptable. The audit staff also expressed their appreciation for the cooperation and support provided by the technical staff of PG&E g and its vendor / consultant. . As a final note, the week long seismic audit effort was carried out in an expeditious manner with adequate depth of auditing. It is concluded that the objectives of the audit were properly implemented.
J. Knight, Chief Mechanical Engineering Branch Division of Technical Review L. C. Shao, Chief Structural Engineering Branch Division of Technical Review Enclosures: 1. List of Attendees 2. Diablo Canyon Seismic Audit Agenda 3. Seismic Category I Audit Check List 4. Detailed Seismic Audit Check List 5. Additional Information to be Provided by PG&E and Westinghouse 6. Computer Program Verification cc (text Page) g , , _. .TR:SE . . . . ._ .;) _TRISEB __ , ~ ~ - - '"'e=* 7807 c ' - - .DJeng:m - -.JKn ih t .. _ LCSha _ . _ . . a ry .... ~~-=* 5H&l75.- . . 5hYl75 - 5/Lbl15-. - 5/ff,115- . _ =~s=+ Forum AEC.5Ie (Re,,9 55) ABCM 0240 W u. s. novsanneant enenvino opp css i.,4... s
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. . . . - , . . . - .); } - . MAY 1 9 1975 R. R. Maccary -4- cc w/ enc 1: B. Rusche E. Case F. Schroeder A. Giambusso R. DeYoung V. Moore H. Denton L. Davis 0. Parr
D. Allison D. Jeng G. Bagchi P. Y. Chen V. S. Noonan cc w/o enc 1: SEB Members 3 MEB Members . p ! , ! . .. . ~
[ orroca > , , _ , , _ . . l avama=a > . . . . - - - nave > _ - - - - - - - - - - - ' - - ' " ' Form AEC 31s (Rev,9 53) ABCM 0240 W u. s. eovsanusm? resutsue orrecs s.74.sae see
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' ' , , ENCLOSURE 1 LIST OF ATTENDEES . $.8 '#) .-( . , . t. - - e FOIA Ma *S9I .- . . . - - -. . . . . . .. ... . . . ,._- -_..._ , .. .. _ _ _ , _ . _. A-35
'.' ' , . ) J . . . , ENCLOSURE 1 LIST OF ATTENDEES NAE TITLE ORGANIZATION D. V. Kelly Ch. M & N Eng. PG & E M. J. Gormly Project Mech. Eng " R. V. Bettinger Chief Civil " V. J. Ghio Senior Civil ." E. P. Wollak Supvg Civil & Proj. Civil " , F. W. Brady Civil Eng " V. S. Noonan Mech Eng NRC/MEB P. Y. Chen Mech. Eng " J. P. Knight Chief. Mech Eng.Br. " L. D. Davis OELD NRC/ OELD D. C. Jeng Sec. Leader Structural NRC/SEB L. C. Shao Chief, Structural Eng. Br. " G., Bagchi Ftructural Eng. " ' c s W. J. Lindblad Project Eng. PG & fl _ D. Nielsen Senior Electrical & Proj. Eng. " B. Young Senior Electrical " R. Gallagher Vice Pres. - JAB Ass. ' D. Javeri Proj. Eng. " " , G. T. Downs Supvsg Structural Analysis W Electro-Mech. R. M. Laverty Senior MC ' PG & E J. W. Dorrycott Proj. Mgr y W. C. Gangloff Proj.. Mgr W , T. E. Campbell Mgr Support Structure Design g D. F. Miller Mgr System Structural Analysis y P. G. Smith Mgr, Structural Development g (Tampa Div.) .
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' ) . . , ! . ENCLOSURE 2 DIABLO CANYON SEISMIC AUDIT AGENDA d . . i F C I A Sfs - 3 9 I A -35
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) . > c - . . . , ENCLOSURE 2 DIABLO CANYON SEISMIC AUDIT AGENDA , April 28, 1975 9 - 10:30 SEB - General Briefing Seismic Design Methods & Procedures EB - Cover the items in Sections 3.7.1, 3.7.2 and 3.10 of standard format - PG & E information (not Westinghouse) - Description of material on appendix B data lists (Rasmussen List); provide list 10:30 - 12 SEB - Turbine building, intake structure and containment analyses 10:30 - 12 MEB - Specifications, analyses, etc. on selected equipment 1:00 - 5:00 SEB - General Briefing on PG & E design control methods & ! procedures 1:00 - 3:30 MEB - Specifications, analyses, etc. on selected equipment 3:30 MEB -- Leave for San Luis Obispo . t - .,
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) . . , , AGENDA April 29,1975 9 - 12 SEB - Further discussion of information on Appendix B data lists (Rasmussen lists) following overnight . review I-5 SEB - Discussion of seismic related computer program verification - Visit PG & E computer facilities 8:30 MEB - Tour site and look at selected equipment April 30,1975 9 - 12 SEB - General briefing on component seismic design adequacy - Cover items in Sections 3.7.3, 3.7.4 and 3.10 of standard format - W stinghouse design control methods and procedures e - Steam generators & supports ( - Reactor coolant pumps & supports - 1-5 SEB - Material on appendix C, D & E data lists (Detailed MEB information on certain selected components) . O e e --- , -- -- ,- .,
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May 1, 1975
9 - 10 SEB NRC caucus - MEB l 10 - SEB Containment liners bulge, Salt Water Cooling - All day Pipes, ACRS questions, etc. 10 - MEB Qualification of equipment of base slab and - All day ground May 2, 1975 AM Completion of any outstanding items. - . O . O = % % S " -.--m._ m-mm_ _ _ . - _ _ _ _ - - -_._-m __ - --___ ..._m--.___________
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. . . - , , AGENDA - May 1, 1975
9 - 10 SEB - NRC caucus MEB 10 - SEB - Containment liners bulge, Salt Water Cooling All day Pipes, ACRS questions, etc. 10 - MEB - Qualification of equipment of base slab and All day ground May 2, 1975 AM - Completion of any outstanding items. . . . . l . f . ;. .
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. ' .. ' QUALIFICATION I DATE I4ETH00 0F SEISMIC QUALIFICATIC:1 AVAILABLEt / ,- l AE OR - QUALIFIC[dTED DATA \\ TION ~ ' '-~ C0i4:',l TEST
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- VENDOR
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- AfIALYSIS
REPORT BASIS , h'HER! r I:3. OESCRIPTIO:t , , . , , . .. ..L l I
-* 6.3.7 Electric Power Distribution Systems [ . , , , . + 1 '. . . . ' _' X ! Yes PG&E f - . . i 6.3.7.2 containment Penetrations Ceneral Electric Hay 1970 ,
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_ . - . - . . . . . - - . . . . . " . - - . *\\ . ..! ... .- . . . . . . . . . .* ENCLOSURE 's . I SEISMIC CATEGORY I AUDIT CHECK LIST /y . l
QUALIFICATI0?! I DATE i METHOD OF SEISMIC QUALIFICATI0:1 , . , AVAILABLEt.~/, OATA lAEOR - QUALIFICATI0il ~' ' " ' TEST
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WHERE' . Appendix X ST,5*JCTURES OP. C0i:PONENTS IVENDOR COIPLETED ! (PASTd4 FUTURE) ANALYSIS REPORT BASIS , , I:0.
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.,. + i l ' , " ' _ i .f , j 6.3.1 Containment Structure Yes PGE [ I r X l Blume 1970 , Soil-Structure Interaction . Yes PC&E 6.3.1.1 X Blume 1970 l , 6.3.1.2 containment Internal Ser Yes PGLE
I 1 X J , 1970 i
.. 6.3.1.4 Containment Polar Crane H. Jordan /Yuba ! I
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t' l ! 7 I - 6.3.2.0 Reactor Coolant System
Yes ici?. i . , l ,, Westinghouse 1975 l X
' . 6.3.2.1 RCS Loop . ' Yes PCSE ' " 1975 .' X ! ,, .i ,6.3.2.2 ' Steam Generator & Pump Supports ' Yes PCEE l
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" 1975 , 6.3.2.3 Reactor Coolant Pump Nozzles f , . Not Related to Seismic Design NE ,% . 6.3.2.4 Pipe Whip Restraints X
Yes PC*E , 1975 ! Yes
Westinghouse ~ X ! 6.3.2.5 Snubbers Paul-Munroe 1972 i
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i l '$sl , 6. 3. 'l Low Head Safety Injection System . . i ! Yes PCLE g . X ~ *i Blume 1972 . ' Vestinghous ! 6.3.3.1 Piping f Yes X 6.3.3.2 Pumps & Drives .We stinghouse 1972 l Yes Westinghous; i X . Westinghouse 1969-1975 , t Yes Westinghou. l 6.3.3.3 valves X Westinghouse 1969-1975 , " j ' 6.3.3.4 Hotor operators l Yes X X . 1972 , Blume ^6.3.3.5 Snubbers & Hangers . Field Test on ' Westinghouse "' "
6.3.3.6 Instrumentation gpg
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- VENDOR
COMPLETED TEST
- 0T9ER
T , (PAST OR. FUTURE) ANALYSIS REPORT BASIS , WHERE' !.0. E30RIPT:03 . i , .s 1 . ' - I. I I j 6.3.4 High ' Head Safety Injection System l l i ' e ' Yes We stinghouse 1 6.3.4.1 Accumulator Tank Nozzle ! Westinghouse 1975 X . . 6.3.4.2 Accumulator Piping Conn. Westinghouse 19f/3 X j Yes PC&E - ' I
, I f . to RSC i Westinghouscf Yes W 1972 i X j ,estinghouse
6.3.4.3 Charging Pumps & Drives l i
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6.3.5 Containment Spray System
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6.3.5.1 Spray Pump outside Containment' Westinghouse 1972 l
. Not applicable to Diablo Canykin i I J
6. 5.2 , n de ne ment i i I. ' . , ' t e , , ! .6.3.6 On-S'.te Electric Power System ' .ml i ! Yes PCLE f 6.3.6.1 Disel Generator Housing 'Blume 1970 X , ' I ! i l (Turbine Building) 1 . i . 6. 3.~ 6. 2 Diesel Cenerators Vendor + PG&E 1975 X X } ! Yes PC&E . ,
j f Yes PC&E ' Vendor + PCEE 19I5 X i { 6.3.6.3 Day Tanks , .
f , , Yes PG&E . ~ 6.3.6.4 Air Tanks PC&E 19f5 X i I 6.3.6.5 Battery Charges EXIDE PSD 8-11-72 6 X Yes PC6E ' ' ' 4-27-71 Unit #1 Pattery Rack' Batteries Yes PC&E Battery Rack & Batteries C&D, Inc. e 8-29-72 Unit #2 . I
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. .. . . ., ... .. .. . ) . ' ' - .: . i ENCLOSURE 4 DETAILED SEISttIC AUDIT CHECKLIST C . 9 e I I - g y y.yj - - - - - _ _ _ _ _ ._ wsci
. - . . . _ . . . . . . . - . . . ENCLOSURE 4 ._. ._ . . _ . , ,, ,, _ .
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Detailed Scismic At it Checi: list - Structtires_ ,,. 1 k s,'. -
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O Plant flame: . DIAB 1,0 CANYON POWER' PI. ANT IyPC:
~ ? DNR ' \\ Utility: P.cande Company
PWR x , NSSS: Westinghouse llTGR A-E: PGandE Company , J. A. Blume & Associates,, . . ' . Structure - flame: Containment . ' . . Description (Include sl: etches): Exterior Shell: 140'ID x 142'High x 3-{0 thick Cylindrical Wall,140'ID x 2'-10 thick hemispherical dome roof. Interior Structure: 106'0D x 49'high x 3' thick cylindical crane wall, anchored into base slab, 34'0D x 8' thick x 11'high recctor wall. 4' thick fuel transfer canal walls & floor. 3'-7' concrete main operating deck I tforms between ext. shell and cran wall. Foundation: 15' reinforced -Structural steel annulus 8 designer: Responsibl concrete base mat. Stanley Hanusiak - Roger Villatuya (JAB) . f Responsible Checker and/or Reviewer: 8 David C. Landes (Reviewer), R. Y. Chandivata (JAB) f Pertinent Reference Drawings: 443231 thru 443237, 443239; 443240,'443241, 443243, 443251 thru 443254, 443272, 44327,3, 443276, 443277, 443283 thru g 443285, 443286 thru 443287 ., -. ( i . v , ) Seismic Input - acceleration: 0.20g (DE) 0.40g (DDE) ~ . . . g 6 l Ground Response spectra location: Surface / foundation 3 . . I 8 Time !!istory:Hypthetical time history, developed to produce an envelope spectrum, 1,hich combines input from time histories of March 22,'57 San Francisco and July 21,'52 Taft [ Calif) carthquakes. In addition, to these two time histories, arbitrary modifications were ' Introduced following meetings with AEC Staff, for the purpose of making the criteria more
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., l',ethod of Analysis -
, ! - f' Model type (ccch direction): Axisymmetric finite eletnent model. The lfrundation rock r.nss and the containment structure are modeled as one structure system, to l:ensidar rock-structure interaction (FSAR Figure 3.7-5) Co.puth godo: " Dynamic Stress Analysis of Axisymetric Structures under brbitrary Loading ukmar Chosh and Edward Wilson UC Report No. EERC 69-10 - Soil Structure Interaction: Soil is included in the model. Soil damping: Structura fdaraping: 2% (DE), 57. (DDE) Combination - 3 Ccm,70nents: Largest Horizontal component added i I to vertical - . Torsional cen':idera tion: -Axisymetric Struc,ture <:
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! ~~ ( Modai Shapes & frequencies: ' Fig. 3.7-6 See FSAR - . . - . . . Total Base Shear: 35,05 (DE) Overall Response (shear & moment): 59,990k (DDE) - , 6 Total 3.48x10 k ft (DE) - 6 5.62x10 k ft -(DDE) Floor Response Spectra (sketches)Overturnimg Moment:
Attached , ' Foundations: . STRESSES Critical ' Load - . LOCATIO1 Combination Bearing Seismic Total Allowable
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Base Hat Dead 1.oad + DDE 8.KSF 88KSF 96KSF. 800KSF Min (150 ks f)** (158 ksf)**
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ing passive resis
, E r ek. Factor of Safety - Sliding-Not critical, ~ seismic force resisted by ;*fs010e . j- r,esistance of rock on vertical f ace of base slab. 6 Overturning 1.2 (114)** ., , J - .. ,, , , - . . ., . Critical Structural Elements: ' STRESSES . Governing - . - Identification location Load Co.T.bination Seismic Total Alle>able - Hoop reinforcing 12'above base C=1.0D+0.05D+1.5P+1.0T" O 55.8 ksi 57ksi Diag. reinforcing C=1. 0DM. 05D+1. 0P+1. 0T+1. 0DDE 3 0.1 59.4 57ksi " . ... . ., . .
. Iia'x Deficction: ~ Amount Location 0.666" (DE) c*. , Top of Containment
',. 1.063" (DDE) - . , p .- . - l 1
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, ,, , . p,/ J .,- . ,\\ - Date: , , 'l . r' t. e . , , - .: . . .. ! . .,. .. . , 'l 9 Detailed Seismic Audit Chec': list - Co:nponents - ~l < t ' q, i e I * ' '
.. . , . . ' Plant - Name: Diablo Canyon Units 1. and 2 . Type: / ' ' . c ' Utility: Pacific. Cas and Electric BWR - '
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A-E: Pacific Cas and Electric HTGR
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.i, Vendor: L,. . , - , , '
Component' - Name: steam Generator supports - <- - ~ ( ,}. ,y Z Description: See attached - 5 I ' ' Location (In-plant): containment 31dg. .
..' Functional Description: support the steam gcnerator under 'all loading conditions $, ~ . - . ' - Pertinent Reference Drawings: 438276, 438277 ,- -
, . - . . ' Pertinent Reference Design Specifications:
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,. , . . * . , . ' 10 ),e,ff.'ig) The lower supports for the steam generator consist of: Four vertical pinned columns with bushings bolted to the bottom of the steam generator support pad. , . A lateral support frame which is shimmed to transfer the load from the steam generator to the concrete. The upper lateral steam generator support consists of a ring band around the steam generator shell. The ring is attached to concrete by four hydraulic shock suppressors and by four steel bumpers. Loads are transferred from the . equipnient to the ring band by means of shims between the band and generator , shell. ' . . !?. ~ - . S e 6 - t . % 4 e 9 m O e , I
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Seismic Qualification - Method (analysis,): Analysis ( ctc. * ) .
3 - Directions: All three directions included -
Accelerations: N.A. (Response Spectra Peak DE 8.8g, DDE 14.2g Modei Frequencies: N.A. (S.G. Freq. 8.7, '8 8, 10. , 15. ) - _ _ _ Critical Structural Elements: . Governing Stresses Identification Location Load Combs. Seismic Total A11cuable - . S.G. Upper Support. LOCA & DDE ,, 65% 36.2 42.0 S.G. Lower Support LOCA,& DDE 41% 41.5 50 . . _
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n ,-. Hax. Deflection: f - . . Location: - - - . a Effect Upon Function: - . . , . , If Qualification-by Analysis, then Complete. Hethod of Analysis - Response Spectrum Method - Model type (each direction): Three dimension model of the Reactor Coolant System . Computer Codes: westdyne . , Structural Darping: 1% Support Considerations: Upper and lower supports considered in the analysis Combination - 3 Components: SRSS combination of worst horizontal plus vertical Torsional Considerations: Incorporated in the model . .. . . %
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. . . ' . " . The supports are analyzed and included in the Reactor Coolant System analysis. For this analysis, the Design Earthquake and Double Design Earthquake Responso Spectra curves obtained from - Pacific Cas and Electric analysis of the Reactor Containment Building are utilized. The DE and DDE Floor Response Spectrum _ Curves corresponding to 17. critical damping at the highest elevation at whic G supported com h ent is attached to the containment, were conservatively used in the analysis for the . Upset and Faulted Condition. . ll . . . .
. . 9 4 1 , . . . . . e . ' . . .
__ . . . ..- . .. .. . - . . - - ._ - . y ..;. ) b Date: pjb:ks ~ ,, ~ . . . . , . .- - . , , . - , Detailed Seismic Audit Checklist - Components, , .. . Plant - Name: Diablo Canyon units 1 and 2 Type: - Utility: Pacific Ca s and Elcetric BWR NSSS: Westinghouse Electric Corporation PWR x - A-E: Pacific Cas and Electric HTGR Vendor: . , . Component - Name: Reactor Coolant Pump Supports ' Description: See attached Location (In-plant): Containment Bldg. , . Functional Description: Support the reactor coolcnt pump under all loading conditions Pertinent Reference Drawings: 438278, 438279 - , . Pertinent Reference Design Specifications:
. J . . .
Seismic Input - , Floor Response Spectra: Fa e Y See s . . 4 . . e . . D - . _ - .- - . . _ . _
. 3h / ~
~ . .- o ., , . .. ' = = . ..
. . . The supports are analyzed and included in the Reactor Coolant . For this analysis, the Design Earthquake and System analysis. Double Design Earthquake Response Spectra curves obtained from - Pacific Gas and Electric analysis of the Reactor Containment Building are utilized. The DE and DDE Floor . Response Spectrum Curves corresponding to 17. critical damping at the highest elevation at whic N supported com h ent is attached to the containment, were conservatively used in the analysis for the . Upset and Faulted Condition. . . .;' C - - . . . e . . 0 . 1 . . l . . 4 . - e l - . 8 ! - . I ~ ' .
.- _ _ ,. . . . . . . . ., y . . . . ,, ,l- !
.. . . Oe':C2 ; ' The reactor coolant pump support consists of a structural frame. The frame is attached to the pump vertically by bolts. The frame is equipped with steel bumpers that are shinuned against the pump casing to transfer the lateral - loads. , _ _ _ _ e e . I ! . S 6 + ! ! , . t l - . . - . - - , _ . - _ . . . . . _ . _ . . . ,, - , , , , , _ _ _ , _ _ _ . _ _. ,_ . , _-_ .. _____._ _ , _ , _ . _ , _._ _
9 .{'{ " (d. b ' ^; - 1 - ,
- .-
, , ..%. - . . , w . . , , - - s - .. - - + . , . , ' ( Test, ) ~ - Seismic Qualification - Method (analysis,): Analysis ( etc. - ) ~
' 3 - Directions: All three directions included Accelerations: N.A. (Response Spectrum Pedk DE 3.lg, DDE 4.9g Model Frequencies: N.A. (RC Pump 6.7, 7.2, 10.7, 11.9, ) . , . Critical Structural Elements: Governing Stresses Identification Location Load Combs. Seismic Total Allowable - . RC Pump Supports LOCA & DDE.
- S 30%
98 115 - 2 65% 30 36 . .]t - . .. ., , . .- . n v. Max. Deflection: . 1 . - . . Location: - - . . Eff,ect Upon Function: . - _ . If' Qualification by Analysis, then Complete - , Method of Analysis - Response Spectrum Nethod Model type (each direction): Three dimension model of the Reactor Coolant Systera . . Computer Codes: Westdyne . , - Structural Danping: 1% - Support Considerations: RCP supports considered in the model Combination - 3 Comp'onents: SRSS combination of worst horizontal plus vertical Torsional Considerations: Incorporated in the model ' - . , . , ,
- ma
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-:- . } , . ' e . The supports are analyzed and included in the Reactor Coolant System analysis. For this analysis, the Design Earthquake and . Double Design Earthquake Response Spectra curves obtained from Pacific Gas and Electric analysis of the Reactor Containment Building are utilized. The DE and DDE Floor Response Spectrum Curves corresponding to 1% critical damping at the highest elevation at which the supported component is attached to the containment, were conservatively used in the analysis for the Upset and Eaulted Condition.
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i
. . - . . - . .. - . . . . . . . ,- y . Detailed Seismic Audit Checklist .com9enents , .. Plant - llame: Diablo Canyon Units #1 and 2 Type: _. BUR Utility: Pacific Gas & Electric, NSSS: Westinghouse Electric Corporation PWR y - ' A-E: Pacific Gas & Electric llTGR Vendor: Westinghouse.-Tampa Division ,
. Componcat - Hama: Steam Generator , Description: Vertically oriented U-Tube Heat Exchanger ' Location (In-plant): Reactor Containment Bldg. Functional . Dascription: Feedwater, heated'by~ reactor coolant passing thrcuch U-Tubes, changes to a water-steam mixture and flows upward through the tube bundle .. c ,' exiting, the unit as, essentially, dry steam. ' . Pertinent Caforence Drauings: Cutline D.vg. 717J350,/ Genera 1 Assembly Dwg.1097J74 - , Portintat Reference Casign Spacifications: .Hdsting' house Equipment-Spec 677310 - - - . . . ' . . SetsmicInpyi- , Flcer f.c:pcase Spactra: . Design Earthquake and Double Design Earthquake Floor Response Sr,cctra obtained from Pacific Gas L Electric analysis of the reactor contain:r.ent building. Elevation corresponding to upper support elevation was used with 1% equipmant damping. . ' . . . . . . e
e 4 6 . . . .
t
~' " - .. . , . . . - , .. .- ) . . , -
. - . . . . . . . . - .- Te'st. .. Seitr.iic Qualification - l'ethod cnclysis, : Analysis etc.* ,
. 3 - Directions: All three directions evaluated. - Acccierations: Peaks on ficor response spectra design carthquake - ~ '8.8g; double design earthquake 14.2g. Podel Frcquencies: 8.7, 8.8, 10.0, 15.0,....... - , ' Critien1 Strneturcl Ele:onts: . _ Coverning Stresses - Identification Location Load Cc:das. Soisaic Total Allo.- able _ Tubes U-Bend Design Press- 50% 3.4.9 ksi- 35.0 ksi I Region ure + DE ' Shell Upper Design Press- 15% 37.0 ksi 40.0 ksi Support ure + DE - ' ' Tubes U-Bend DDE + LOCA 30% 68.6 ksi. 73.4 ksi ' ~~
, Region
ShcIl Upper DDE + LOCA 30% 80.3 ksi 84.1 ksi? .. Support
IkX. D3ficctica: 1.96 inches for DDE. / ~ n s, . , ' .' Locntion: Tubes in U-bend region.
' Effcct Upo;t Fuaction: tione ' . . . . If Qualific:tica by Inelysis. than Complete ' I '. I'.cthod Of /GalySiS - Response Spectru:a tiethod .
lbdel typa (etc.h directicn): 3-diment.icnal lemped mass becm clerent j model with approximtcly 300 degrecs of freedca. Corputer Oc:hs: StlAKE, RESfdl (T apa Division Ccdes)
, , ' i Stru:ttirci Cc.)ing: 13 i, Support Consid: rations: Upper and lcuer support stiffnesses included ! Co:nbination - 3 Ccmponents: SRSS ccr.:binatien of worst horizontal en.i vertic; ' Torsional Cont.iderations: tiedel incorporates torsional r.: odes of vib.0!. ice.. .
- , 1 -
= l . . . . ,, -- - - - - . - , - - - - - .-. , - . . - . . . - - .-- ra - - .
,, Date:
- .
. . s .
't - g... ) - - . .- . . - . . . . . ., Detailed Seismic Audit Checi: list - Comionents .
- r Plant - Hame: Diablo Canyon Units #1 and #2 Type:' Utility: Pacific Gas & Electric DNR NSSS: Westinghouse Electric Corporation PUR y . . _ t.-E: Pacific Gas & Electric HTGR Vendor: Westinghouse Electromechanical Division . Co ponent - llana: Reactor coolant pumps . ' Description: See Attachment !!o.1 ' Location (In.-plant): Reactor containment building ~ Functional Description: See Attachment Ho'. 1 '
r. -p Portinent Reference Drawings: Outline D::ge 618J860; /Ar,sembly Dwg. 618J861 - , Pertinent R::Tercace 02 sign Specifications: E-6f6574 -
, . . - . . Seismic Innut - . - -- 6 . . . Floor Responsa Spectra: - Design Earthqual:e and Double Design Earthquake Floor Response Spectra obtained from Pacific Gas & Electric analysis of the reactor containcent building. Equipmant damping of 27, of critical damping.used in the seismic analysis. - . . . . - , - . 9 . . % L _
.
.- s . . - -.. . . ,s ,. ,) - 3 - - . . . . . ,. . ( Test ' ' - Seismic Qualification - I'.e'thod (analysis, : Analysis ( etc.' - N . 3 - Directicas: yes 1.ccelcrations: Feak accelerations: 3.1 for DE and 4.9 for DDE ,
Podel Frequencies: See Attachment t!o. 2 . .C.r.itical Stri!ctural Elcirents: _ - . ,_ Governing Stresses Idcatification Location Load Ccabs. Seismic Total Allowable . . . See Attachment flo. 3 . - .. . - . ..
O 3 p V, I.?OX.Dbilection: Lateral - 0.80" Vertical I .020."
- . ' LOUBtiO3: Top of motor Whoie Pump' '
. , ' Effect U;oa Function: flone None - . . . If Qualification by Analysis, than Complete , ' !!sthed of fr. clysis - Response spectruni method b ibdal tyio (ccch direction): A 3-dir.:ensional c:odel incorporating iteped ass, beam, pipe, spring, du.:per, and fluid coupling cler.'ents. 00g utar Cod 2G: AflSYS - , Structural E t.piim: 27. ' Sur;;crt Considcrations: Sup Co::' sin *; tic:s - 3 CG::)CnntttS*:ipkort stif fness c: atrix Fig. 5 of E n ng stiffness matrix Fig. 4 of E-67574 .SRSS,c c.-binatica of thn Ucrst horizontal plus the vertital c lorLi ra t t.o.M c Nati?.is: . N0d fi i ei<-ried..<. 14, c i ,...>1 .. 01(.3 o f vil,rt.ti Gn . . I - . . . . . . . . - - - . . . - - . - . - . . . . . . . . . .. .. .s . . . . . . , . . . - . . . .. , ., . . . ..
. - _ - - _ _ _ . -_ . . . .. . - . .
. .
- ,-
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. AlTACh?iEf1T f0.1
. . . The Controlled L.eakage. Seal P.eactor Coolant Pump is a vertical, single-stage, ' centrifugal pump designed to move large volumes of reactor coolant at elevated temperatures and pressures. The pump consists of three general areas: the hydraulics, the seals, and the motor. . The hydraulic parts primarily consist of an impeller, turning vanc-diffuser, diffuser adapter, and casing. The casing is permanently welded into the reactor cooling system. Attached to the bottom of the shaft is the impeller which is the prime mover of_the ccolant. The coolant flows into the eye of the impeller and a velocity head is imparted to the fluid. The coolant is then directed to the turning vane-diffuser assembly where the velocity head is converted to pressure head. Directly above the impeller is the themal barrier / heat exchanger. During normal operation, the thermal barrier limits the heat transfer from the hot coolant to the radial bearing, seal area, and other pump components. Ilowever, if a loss of injection watcr should occur, the component uould then also function as a heat exchanger to cool the hot reactor coolant which would leak into the bearing and seal area. . liigh-pressure injection water is introduced through a connection on the thermal barrier flange and flows into the cavity between the main flange and the themal barrier. The injection water flows downward to the radial bearing 1:here it then divides into two flow paths. The upward flow travels past the radial bearing and into the seal area while the remainder flows down throtgh the ~. thermal barrier labyrinth and past the cooling coils where it acts as a buffer to prevent reactor coolant from entering the radial bearing and seal section of the pump. Both the radial bearing and the seals are lubricated by the injection water. The pump seals are water-lubricated and control the upward flow of the high- pressure injection water. The leakage of the Number 1 seal is channeled to the plane chemical and volume control system. The leakage of the !! umber 2 seal ar.d the !! umber 3 seal is directed to the reactor coolant drain tank. The Reactor Coolant Pump is driven by a vertical, solid-shaf t, air-cooled, squirrel-cage induction-type motor. The motor is couipped with an oil- lubricated double Kingsbury-type thrust bearing, two oil-lubricated radial bearings, and a flywheel Ubich is equipped with a ratchet-type anti-reverse rotation device which prevents the rotor frca being turned in the reverse direc tion. The rotor and stator are of standard construction. Six resistance temperature detectors are located throughout the stator to sense the winding temperature. The upper and lower bearing temperatures are also manitored uith resistance tei.perature detectors. t!ater-type heat exchangars are used to cool the lubricated oil. Further detailed description of the motor is given in the motor 1.::.nufacturer's operating instructions for the Recctor Coolant Pump Motor. An additional feature of the Model !!-11004-Al pur.!p is the use of a spool pixe heturan the sums and retor c::r. lines. This s:001 nicce can be removed with^ut di .e. tu rM m tne r.c tr.r '.n: rt:.y c i l e.fi c : rcr."c2l, tr~r;::!cr., 2n: rc;IR . - -- - _, .t. . . .2 . .. . ..,...:. e... - . . ,. ._
, ; ,3 , . . . -
. _ _ . _ _ _ . . . _ . . . . _. . . _ . . . . . . . . . . . . . . _ . . . . .. . .. '
a , - '~ ~). '-
- ATTAcitMENT i:0. 2 , . . . . Frequencies and Model Diablo Canyon RCP . . ' Rotor / Frame Max. Rotor ' !! ode No. Freq (Hz) . Mode Shape Max ip Disp. Loc - 1 6.7 Frame Z l.0 Flywheel 2 7.2 Frame X 1.0 Flywheel 3 10.7 Rotor Z 87. Impeller 4 11.9 Rotor X 64. Impeller 5 20.1 Rotor / Frame Y , 2.8 , 6 25.1 Rotor /Frcme Z 3.4 Flywheel 7 26.3 Rotor X 8.2 Flywheel 8 28.6 Rotor Z 6.3 Seal Area ' 9 31.6 Rotor X 23. Seal Area . 10 35.9 Rotor / Frame X 1.7 ~ Seal Area , 11 35.9 Rotor /Frcme X 1.7 Seal Arca . e ' . , . . . 3 e e . . . e - - - - , - - - . 4-- . , _. - . _, . . _ . , , . _,___,__,8 , _ _ _ _ . , _ , _ _ e
__..___ ____. ._ .___ _ , ! . . .,
_ ~ * . . Attachment No. 3 , - . . TABLE I .
- -
4 St"..C'.ARY OF RESULTS FOR PRESSURE BOUNDARY COMPONENTS '
4 , . . - OPERATING CONDITION STRESS INTENSITY . I Co ;er. cat ,tr:ss DESIGN NORMAL UPSET FAULTED 1 .. Ana,17z ed Category' Chiculated Allowable Calculated Allowable Calculated Allova le Calculated Allovalbe . i Suetica c6tane 14067 15300 . Nozzle '"ar & Bend 16S07 22950 18215 37440 -
- Tn ta
34893 48672 17787 46800 21795 46800 Discherge k::.'2 rane 15050 15300 v Nor:1c
- <e & Bend
20119 22950 21927 37440 46584 48672 , ': c :c 15746 46800 22693 ' 46800 ' , C.r: f n g f.sct1 Men 10702 22950
,
At
- *: il Mem +
27911 45900 25234 48672 . Dt: charge .?: ndary . I Fo-ele 'n: - 26350 46800 30799 46800 Su pert ':.:t + Bend 21045 22950 ' ' i Fc.:t 50329 56100 in ;.2 4590 46800 23194 46800 ' - , c .ing ' pit Mea 14803 22950 .-
1.t
il Ih= + 19295 45900 19612 48672 Sc:q ore . . . .ud.ny ' - , re:t .' m .c . . 15070 46800 20443 46800 . _ . , Cic -ure ' , - ene Ecit- i -' Eced ' 39553 67480 40259 67480 41183* 80976 . 94154 101220 97241 101220 101369* ,1214.64 ' Sc-1 rane 16200 19300
- %'.r f nr,
. + T:rd 20514 20700 17822 480C0
22594 62400 ne - 49440 60000 54393 60000 C ' ' '. rr." 2
- ?
- 35165 65000 33632 66000 3S682 79200 i r.': 4- Send : ' - : 47970 990C0 52767 99000 52767 118300 i . ' '
- M
.* , . )
. . , - . . . .. , , . ' .. ' Detailed seismic Audit Checklist - Cemoonents Component - flame: Steam Generator Supports .- . . These sheets are currently being prepared and will be sent to PG&E during the week of April 28, 1975. 9 9 e a '. ' . ' s 4 4 %h . , , . $ e 9 g e . c.
, e , e 4 e
. -. .# . , . , , . - : .) > ' ' . .
. Jgtailed Seisraic A ndit Checklist - Components i Component - Name: Reactor Coolant Pump Supports . . These sheets are currently being prepared and will be sent to PG&E during the week of April 23, 1975. . . . t I
. , t . '. . e 5 e e . . .
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. . O e O G A . A A A
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- . . ;
) - > , . ENCLOSURE 5 ADDITI0tlAL IrlFORMATION TO BE PROVIDED BY PGSE AND WESTINGHOUSE . 0 4 % M
.. _ _ _a : - - - . - . . . - . = . . n -. _. u = .- , -.
- ..;
') i - , ENCLOSURE 5 ADDITIONAL' INFORMATION TO BE PROVIDED BY PG&E AND WESTINGHOUSE At the close of the audit meeting, PG&E and Westinghouse comitted , to provide the following information for NRC staff reviews: ' PG&E PORTION 1) Report on design adequacy of Category I buried salt water pipe and buried piping connecting the diesel generator and diesel oil tank. 2) Report on method of combination of horizontal and vertical excitations of Category I piping due to earthquake loading (A clarification of the specific seismic load combination procedure adopted by the PG&E piping analysis computer code). 3) Report on seismic adequacy of turbine building due to the latest seismic load. , Stati,stical data for material strengths of steel and concrete for evaluation of as built structural capacity of the turbine building. (This information will not be needed if as built material strengths are not to be utilized in the structural capacity evaluation). . Detailed seismic audit check list for turbine building. 4) Report on inspection results and follow-up action, if any, of providing) proper supports to field run Category I piping (21/2" p or less by responsible engineer. 5) Description of assumptions used in the "DECON" program utilized l by JAB for calculation of bedrock motion time history. - PG&E agreed to provide the above information within one month approx- imately. ~ WESTINGHOUSE PORTION 1) Four sets of detailed seismic audit check lists indicating use of the absolute sum method to combine horizontal and vertical earthquake loads and incorporating additional data as well as copies of applicable floor response spectra as agreed to in the audit meetings. Audit check lists apply to steam generator, reactor coolant pump, and their support systems. 2) Revisions to design control method (Seismic Error Mitigation Program) as applicable to the Diablo Canyon Plant of the following Westinghouse divisions: Pressurized Water Reactor Systems Division, Westinghouse Electro-Mechanical Division, Westinghousse Tampa Division. . . -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . - _ _ _ . -
r .. . _..._. . - . . _ , . _ . . . . _ . -_._____-_.; -_ . .__. _ .. . .- , _ ) ~
> - . . , . -2- Westinghouse agreed to provide the required information within two weeks. ' . . 9 6 e e
. . . - - -- . . . - - - . - - - . . . . - . . . .. . . - . . . . ... .- . ,' )
. , . EllCLOSURE 6 C0!!PUTER PROGRAF 4 VERIFICATION I , ' . . , f I l FoIA %"Al . - A-35
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o o , j. . - - . l im- % JollN A. BLUME & ASSOCIATEG, ENGitJEERG IN:f. "I:l
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(:asuinea 's t 1(1:, ' . t 1 s ?.s :Y'! T.I'T* 9 ENCLOSURE *6 - ! f COMPUTER PROGRAM VERIFICATION February 1, 1974 , , Mr. Frank Brady Pacific Gas G Electric Co. 77 Beale Street , Room 2613 San Francisco, CA 9410S Subject: Diablo Canyon Final Safety Analysis Report Verification of Computer Programs Dear Mr. Brady: In accordance with your recent request, we have prepared des- criptions and verifi. cation documentation for each of the following
computer programs: AXIDYl'; DECON; MNTRAN; SMIS; PIPDYN; and PIPESD. e These were used in our scismic analysis work on the class 1 structures and piping of the Diablo Canyou plant. , A copy of this program documentation is attached herewith. . If we can be of any further assistance, please call. Very truly yours, J0llN A. BLUME G ASSOCIATES, ENGINEERS -).7,.s wl / L0
, . Ronald P. Gallagher Project Engineer RPG/oc Enci . , .. bec: CWO JPN/ Central 2090217* - DilR* /. - - RPG*- - - .R/F -
- W/cnci
. . . .
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.. , ' . . . . > . . . . . c - . , , DESCitlPTl0llS Ai!D VEP.lFICATI0llS OF COMPUTER PROGRAMS USED 111 SEISillC AllAL,YSES . . OF DIABLO CANY0ll SEISillC CLASS 1 STRUCTURES . The purpose of this report is to transmit information regarding computer . programs which werc utilized in the seismic analyses of Diablo Canyon facilities. All the programs discussed herein ore maintained by URS/ John A. Blume & Associates, Engineers, and are operative on the CDC/ ' 6600 SCOPE 3 2 Operating System at the Control Data Corporation Cybernet Data Center in Palo Alto, California. A bricf description of the analytic techniques employed by each program and a summary of the development his- ' tory and verification procedures used to' insure accuracy and validity of the results are presented herein for the AXfDYN, SMIS, MATRAN, PIPESD, PIPDYN, and DECON programs. AXlDYN was used in the Containment Building analyses, MATRAN and SMis were used for the Auxiliary Building analyses, PlPESD and PlPDYN were used for the dead load and seismic response analyses, . c .
respectively, of the piping systems, and DEC0lf was used to develop the base / motion of the soll mass for the Containment Building. . .i . . 1. AXiDYN . The AXIDYN program is a finite element method for the dynamic analysis of complex axisymmetric structures subjected to any arbitrary static or dynamic loading or base acceleration. The three-dimensional axisymmetric continuum . Is represented by axisymmetric thin shells, by a solid of revolution, or as a combination of both. The axisymmetric shells are represented by conical frustrum-shaped elements and the axisymmetric solids are represented by an assemblage of toroids of triangular or quadrilateral cross section connected , at their nodal circle points. Acceptable loadings are axisymmetric or are such that they can be developed into Fourier series form along the nodal circles (i.e., as functions of rotational angle, (). ~ . . AXIDYN was formulated and developed by Professor E. L. Wilson and S. Chosh of the University of California, Derkeley, Earthquake Engineering Research Center. AXfDYN is a recogni cd program in the public domain, is available .c to the general public through National Information Service - Earthquake ' 1- . - JOHN A. GLUMC & AOUCCIATCC. CNO'NGUf'A
, . . - . .~ -. . . .. . . . . . . . . , . c. . . - . - . . .a. . . . . . . l , , l' s Engineering (NISEE) of the University of California,-and has had sufficient history of use to justify its applicability and validity. Further verifica- tion in the form of comparative solutions to a series of test problems with known solution is described in detail in Reference [1]. " 2. SMIS . The.SMIS (SymboIIc Matrix Interpretive System) program is a general purpose command language designed to perform a scrics of matrix operations under the direct control of the user. The program consists of a main " supervisor" routine and several user callable subroutines to execute specific matrix operations such as addition, multiplication, inversion, cigenvalue extrac- tion, plotting, etc. Several special features are availabic which allow the program to be easily used for the static and dynamic analysis of compicx structural systems. , SMIS was developed by Professor E. L. Wilson of the University of California, Berkeley, in 1963 The program is a recognized program in the public domain, p is available to the public through National information Service - Earthqucho - Engineering (NISEE) of the University of California, and has had sufficient history of use to justify its cpplicability and validity without further
ddmonstration. Versions of SMIS have been continually updated and maintained , by URS/ John A. Blume & Associates, Engineers, since 1966. SMIS solutions to a series of test problems with accepted solutions are summarized in the SMIS user. documentation, Reference [2] . , 3 MATRAN The MATRAN program is a general purpose command language for performing i matrix operations, time series analyses, and static and dynamic analyses of linearly elastic structures. MATRAN was developed by URS/ John A. Blume & Associates, Engineers, from the SMl$ program with the purposes of (1) remov- ing some of the limitations of the SMIS program, (2) adding additional opera- ' tive subroutines to the supervisor library, (3) modifying SMIS Input / output routines to better meet specific user requirements, and (4) streamlining specific analysis operations to minimize the computer time required for exc- . -2- . -'
, JOHN A. OL. UMP. de AUGOCIATC'I CNOIN*r r".V 9 ,. L
. , _ .-.. . ... . . . . - . , .. . . . - . . , . .- .. . . , i * o,' d '
. O cution. . Thus HATRAll can accurately be describcd as a version of SMIS with pre-processor and post processor additions. - . Because MATRAll was developed from the SMIS program and essentially provides identical matrix operative routines, arguments cited as verification of SMIS can be applied to MATI:AN. Throughout the development of MATRAH test problem , results were compared to SMIS results for the same problems in order to insure validity of the MATRAN program. HATRAN has had additional verifica- tion in the form of extensive use by URS/ John A. Blumo & Associates, Engineers, since 1969
4. PIPESD The PIPESD (PIPE S_tatic and D_ynamic Analysis) program is designed to perform lincar clastic analysis of three-dimensional piping systems subjected to sets of user prescribed static, thermal, and dynamic (carthquake) loadings. PIPESD cmploys a finite elcment analysis technique using the direct stiff- ness method for static analysis, Householder's QR method of eigenvalue ex- . traction, and the response spectrum nodal superposition method for calculat- Ing scismic response. Stress calculations are also performed for Class I and Class 2 piping components according to the requirements of Section lit, , "Nuc1cor Power Plant Components," ASME Boller and Pressure Vessel Code, 1971. The program was formulated by Professor G. H. Powell at the University of California at Berkeley and has been extensively modified and expanded by . URS/ John A. Bluma & Associates, Engineers. The program is a recognl:cd com- puter program in the public domain available to the engineering community through the Control Data Corporation CYDERNET network. Appendix F of the PIPESD User's information Manual (3) cites several vertfication problems of PIPESD results versus the ADLPIPE (4), ANSYS (5), and SAP (6] programs (all recognized programs in the public domain). ,
. 5. PIPDYN -
, The PIPDYN (PlPc DYllamic Analysis) program is designed to perform scismic analysis of three-dimensional piping systems by the response spectrum modal superposition approach. PIPDYN is a furcrunner to the PlPESD progre.m and . f -3- _ _ JOHN A. MLUM C a AtWOCI ATf*Go 1* Nr.it.. ..___. _ _ _ _ _ _ _ _ _ ,
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< I seismic analysis techniques employed by PIPDYil' arc identical to those used by PlPESD. Thus PlPDYli is in reality a streamlined version of PIPCSD de- signed solely for dynamic response analysis of carthquake loadings in the horizontal and vertical directions and was used because (1) it is more cost ef fective than PIPESD and (2) PlPDYli output formats were modified to meet ~ special criteria for the Diablo Canyon project. , The program was originally developed by Professor G.11. Powell of the University of California, Berkc1cy, and has been maintained and r'odified by URS/ John A. Blume & Associates, Engineers, since 1968. Because PIPDYli re- sults agree exactly with PIPESD results (for dyr.amic response analysis), arguments cited as verification of the validity of PIPESD also apply to - PlPDYll. A verification problem comparing PIPDYil results to PIPESD and SAP-IV results is described in Appendix F of Reference [3]. 6. DEC0il The DEC0tl (Deconvolution P'rocedure) program is used to calculate motion at g the base of a given soll mass for a given free field surface ground motion. The soll mass is asse.med to be elastic and may be modeled by various layers of soll with different. material propertics. DEC0!! uses a fast fourier transform technique to determine the time-history of the base of the soll ..ff column. g . The DEC0ll program was deveicped by URS/ John A. Blume & Associates, Engineers,
and is based on a Cooley-Tukul (7) fast fourier transform technique. To Insure validity of DEC0tl results for the Diablo Canyon project, a scif- verification procedure was employed in which: 1. A finite element model of the soll mass is formed (without build- ings) for the AXIDYtl program. A unit impulse base motion is sup- plied as input to AXlDYli and the resultant surface (impulse) motion is derived. . - . . 2. The surface impulse response derived in step 1 and the desired free field ground motion arc input into DEC0f4 and the desired base <- I' motion is obtained. ,
. . I, . . JOHN A. OLUMf? cs ASSOCI AT.*G. F.N t.'.IN ;.. .
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, The DEC0ll derived base motion is input into AXIDYN (using tho' ^ 3 ~ ' c original soll model) and'the surface ground motion is derived. s " calculated" surface ground' motion is then compared to the Thi~ free fic1d ground motion input'into DEC0ll, ' _. AmorecompleteexplanationofthhsprocedureisdetailedinReference(8).
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, . , i REFEREl!CEs } . , - -
. 1. Wilson, E. L., and S. Ghosh, " Dynamic Stress Analysis of Axisynynctric .- Structures Under Arbitrary Loading." Earthquake Engineering Rce,carch ' _ Center Report No. EERC 69-10, University of Califoi nia, Berkcicy,- . ' September 1969 ,; '- ! 2. Wilson, E. L., "SHIS - The Symbolic Matric Interpretation System." National Information Service - Earthquake Engineering Report 03 r,73,, - .l University of California, Berkeley, California. - . t 9 3 "PIPESD: Static, Thermal, Dynamic and Stress Analysis of Piping Sys- - 1 tems," John A. Blume & Associates,. Engineers, San Francisco, California, ' , I
June 1973. Is . "ADLPIPE Static-Thermal-Dynamic Pipe Stress Analysis," Arthur D. Little, Inc., Cambridge, Massachusetts, January 1971.
5 Swanson, J. A. , "ANSYS: Engineering Analysis System User's Manual,"
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Swanson Analysis Systems, Inc., Elizabeth, Pennsylvanic, 1972. 6. Ba the, K. J. , E. L. Wilson, and F. E. Peterson, " SAP IV -- A S tructural ' Analysis Program for Static and Dynamic Response of Linear Systems," Earthquake Engineering Research Center Report No. EERC 73-11, University of California, Berkeley, California, 1973. 7 Robinson, E. A., Multichannel Time Series Analysis, Holden-Day, pp. 62-64, 1967 8. "Diablo Canyon Nuclear Power Plant Unit No. 1, Containment Structurc - Finite Element Model, Dynamic Scismic Analyr.is," Report No. JABE-PGE-DC-1, by John A. Blume s Associates, Engineers, pp. 5-7, July 1970. ' . . . I - . Fca'e ur39 - soss 4. m_ume a associarn.,. en.we ;AQ . }}