ML20141M049
| ML20141M049 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/03/1986 |
| From: | Abua E, Fraser D, Holtz A WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20141M032 | List: |
| References | |
| FP-7, IEB-79-14, NUDOCS 9203310250 | |
| Download: ML20141M049 (178) | |
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"l PAGE.003 NOV 2091 ~7i49'
-PAGE 1 0F_39
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Y00n,E FINAL 22770!! PROGIIAM TP-7
-l AS-BUIL7 EUCI!!TDtII.J l'lJ.MC11N GUIEELI!!E Phase t & 2
' 1 FF7.P1 ReiAsion 1
- October 3.1986 Essenvel Abut
.Alex Holtz Wade'Faires'Jr.
Approved
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D.R. Ptaser, littager-
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Vogtle Final Desi6n Verification i:
Referoces: CPC Frc' it File %7BD60 a
a r-9203310250:920326
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PDR ADOCK 05000424 P
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PAGE.004 NOV 20 '91' 7:50 PAGE 2 0F 39 YOOTLE TP-7 A.4 BUM Ei!OIREGIHO 1%KDOWN CUIDELINE VfTN Procecure FF7.P1 P
Record of Revisions i
E.tLif.10n C.
2311
,D;rM3e O
7/31/65 Initia.1 Issue V-Ellbic-06925, A. Nit:
1 10/3/86 Cenatal Revision to incorporate current progran require =ent.s.
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PAGE.005 t40V 20 ' 91
? 00 PAGE 3 0F 39 V00TLE TP-7 AS-5UILT UALT.ICHU CtTIDU.IM i
TP7.71 TABLE OF CONTYNT5 i
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,i 1.0 Pur pose t.0 Scope t
3.0
!!ssponsibilitten 4.0 Project Interf teas F0 Dravir.g sed Document Dotirations 6.0 rivM Walkdovn Prc oss 6.1 Se:cary or Vbek flov 6.2 Description cf Wikdown Activaties ti.3 thase 1 (755) ValkMwn i
6.3 1 Phase 1 Pikin6 t'alkdoVD D&ta 6.3.2-Phase 1 Support Walkocvn Inta i
6.3.3 r.=beded f antes 6.3.4 Structural IWisce Steel h
6.3.5 taae Plateo 6.3.6 Walkdown Documentatica 6.4 Phase 2 (100%) W ikdown 6.4.1 Additional Phase 211alscown Oata 6.4.2 Re71 sed Iray1 Ass for Phase 2 Valkdtwcf 7 'D Fo st.)'alkcorn Packaging 7.1 Ettess Tolders 7.U Support F01ere 73' File Tniders Y.4 Post.h c%tging
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- 'ctusta Ter I.uformatien (RTI's) 9.0 Suole Tetrus f
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l P40E.006 NOU 20 '91 7:50 PAGE 4 0F 3$
V0071E TP.7 AS-EUIL7 VA1X*.CV!! 0711nI! T 1.C FDXf085 This dnou::ett ; ovides pidelines for perfeccing the V5MD field walkdowns in aupport of t.he Vcgtle Fira11xrition Program 7 - Pipirs, and Support P. econ 0111ation for IU 79-14 cloeo out. These walkdovr.s are done on applic4ble piping.Systeus to provide an independent engineering rev t.ev of the at-built drawings that are provided by the piping conunctor, and to provice supplanental field data for the recon:1112tien engineera.
The VSA!U reconciliation rect; ram utilizes the as-built data provided by the piping contasetor to tbs fullest extent possible.
2te ValkfoWn Trogram that supports th18 reconciliation dea 4 nJt Andependently verify the as. built dicansions trovided by the Fiping contenotoa uader their quality centrol progra=, and the vaikdown engineers are not certified QC inspecters, althcugh they meet the cenatal experience and educatio.nl requirteents of ANSI IA5 2.6.
The Vestingboute valkdown engineers c,ay, tharatore. Freride the previously mentioned supplemental fie.\\d data fcr use tu reconciliation under tbs VSUU / Westingboase Quality Asstrance
- regr an.
The TT-7 reconcilittion tror, ram is ;*rforced in two pbasen. Phase 1 la the in!tial review vben approximately 75% of the supports ard all cf the pipics is installed on a \\ine. In isolated cases, V-Scu cay accept packages ffcc f?P with portions of the pipe omitted. The Phase 2 rettev occura when 1005 of the supports are installed and
'as-built' by the piping contracter. The velkdown trogram is structured to support these two titaats of reconciliation.
2.0 T4:0?r The FP-7 valkdown prorf an opplies to al) pipiy coalyticu packayes (annacks) within the scope of the If 7914 bulletin. ' bene incluco j
all A!!W lines and additiccal ron-Ah!Z lines that are defineJ to be sufficiently critical to plac?. operation that they are reconciled under the safety related procederse. T-50% provid1d the initial scoping list to GPC under a gre/ious engineerig activity.
Due to design chan5ee an# Dofified scoping requiremente, this list cay change from time to tape. The punch 11sts issued to GPC af ter Phase 1 reconciliation, as described in the FP-7 Program annus1, l
trovide a uettc.itive litt, of anpecks in the IE 7914 pro 6 ram.
t Engineerir.g field walkdovns will be performed on all FP-7 a:: packs.
f occasionally, sbo piping contractor as-built ;eckages will bive 1001 of the hangers installed for the initial Thase 1 review.
In thia l
case, the thate 1 valkdcun 6uidelinas will apply.
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'AGC+007 t400 ZD '91 7: 51 PAGE 5 0F 39 4
h Phase 1 utaittal is based on a target of 75$ installation for supports. The cesniaant ent.inears cay elect to accept a Phase 1 suboittal frets the piping contracter (Pu11 tan Tcvsr Products, ce FFP) with fewer than 75% of the barger's as-built. Thin aatton does not jeopardize the Phase 1 reconelliation troonsa, and does not
- e require any other engineering approval beyond the tvCuttant e nginee r s.
The it 79131 bulletin also requirea copidoration of Ituited clearance conditions on the piping syste';s. These cooditions, or
' Aattle Points', are considered in a serarate suddeline under the TP,7 prograu, and a.re out aica the scopw of tbia dscunent.
30 AE8Foll3I11n,ITITA Pu11 tan is rentcosible for providing Ptsse I and Phase 2 as-built isotretries and support dravir.*,a for each TP.( arm 3ytical package ter the scoping sheet or puncalist. p'0Vided by 750%.
Ctc hantructice is responsible for coordie.rtin6 the inte:' race t;etween VSMU and tu11can toe the as-built smokeses. In this catecity, the CFC coordir.ater receives the packuses issued by Iu11 tan, logs and tracks the pach,gos, and transaita them to the VEC nikdown cocrdinator.
7SAlU is responsible for engineerin6 valkdowns cs all TP-7 analytical packages. The walkdown puckaces Will be provided to the responetble engineering organization (Dechtel or Westinghouse) for s
formal reconciliaticu.
The walkdown troup in TSAlfJ is d<taignate,; as the Pipityg Syster.s is-luilt, oa psi, group.
P3A will also p rform the ent;ines.aing lis1kdowne for rat 11e points, 3
4.0 PROJt0T IliTMF&tXS Tt
- FP-7 ergineering walkdowna util tra ' &e-Blilt, Uithin Toleranca' t-awirge free the tiping installation contractor, Pu11 nan.
- Thee, Pn11 tan as> butit drawings provide the design ba sta inpat for the IE 79-14 reconcuiliatien.
The FP-7 reconciliation vulkdovna ce not utiliza any othe walkdown
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data from othme finali.ention prograus.
Ibvarer, stie TP-7 prol; ram dann interface with the FP-14 $41er.ic 5eparatica program. This 1
interface to desta-ibed in tbe FP-7 tattle Point Guidelino.
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PAGE.000 NOV 20 '91 7tbt PAGE 6 0F 39 l
5.0 IleWINO iWD 10cm3t!T IFJJUITIDR3 l
The followirat drsvicca and detunects are considtred in perforcing valkdowns and completing Mckages for rec 3nciliation 1)
Raikdevn 2soustrie frautrgs. We N11can 'an. built witLJn tolare nc4 ' piping iso:setries. neae include the pink field e,opies and the wnite red 11Is copies. The pink oopies are used deir4 the walkdown to notate field data. This data la transt *1 bed to the Whit t copy 1.n red ink (hence the redlico acconciature) and the tedline becomes the copy of record s'e*
valkcown it. formation.
7)
Valkde.vn Support trawing - The N11 men 'as built within toivance' support drawir4a. These also includt pick field copies and wh'. '.e redlita, copies.
3) di&!.15tructural Dravir4 - ree.htel drawings used for locatir4
- L'Mds, huse clates, and fer ganaral reference.
4)
Otructural ?!tel hwinfa - f4chtel dravtr4s that are used for identification of beso number.s and loonting connection pcants for a oferotice.
3)
Orthorraphic Drawini; - Requir6d when necessary for colu::n J c oatioca tu containment and Setoral rnftsence.
6)
Penetration frdta Sheet - Rotuired to prcnride the pipe stress 20mlyst uitb cicaranoss for pipe Mattrations.
7)
Embedeent Plate For'n e This form is used to docunent the
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aurport t.ittachcent configuraticn to the embeccent plate along with 3.rta violations.
b)
Wikdown Isomett<io and Support Checklist. These forcs are to be used dwing the walkdown to assure that all itans are verified.
9)
Deviation Report Haquest Form - This form is to te unod to id4ntify ;,0tthtiki nonconforcances. The form Will be sent to GPC/PPP for the purpose of init.inting a formal deviation rerort.
- 10) Valv4 Idetr lfication Torn - nis fore is to be vaod to identify venkr, tag number, and pressure class intornation for each valve on a given isometrit,. Bis interraation tay be added to the itoustria in lieu of updating the value !.D. form.
- 11) Response Spectra Seluction form Tain form identifies the hit;5 ant attachrer;t point of the supports ta the buildings and the attachment to a building other than that specified by the isometrir support dravir4
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pear. nso Nov Pn 'mi vier DAGE 7 0F 39
- 17) Talve Ori.tetation Form - Ria fora is to be used to satv the c.'1Litatto.1 of valve o;cators it not provided t:y N11can.
- 13) Rattle Point identification fore this form is to L4 ured to ideatify rattle pp10ts fcr it.ter consideration.
Deleted Sappert Tors - This fern is vsed to identify the 14) supports ehcun on the noopir.t s!.est ce punohitat that have teen deleted.
Yoct;rint Lead Request form - This ferm to used to request 15) loads free rtter discipline's hangits that attach to the TP-7 oubed and vie. late 3-minimum criteria.
Ecbed Flate tlse 11, quest ' Form - The form is used to intorn 16)
Bechtel that a been plate is installed at a cartain location.
6.0 FIELD VALCOVN PROCF.33 6.1 Smu.RI 0F VORE tW Listed belw is a sur. mary of the arquentid flow of work in the walkdown sad packagics process.
1.
Pullma as-built submittal to OPC 2.
GPC trar.wittal of to built anpack to fSA 3
F3A pro.-valkdown rey Aew and pre-paekncin6 4.
Tield walkJown 5.
Transfer of valk6own data to redline drawings 6.
Packagir.g for offsite tranrettts.1, 7.
Offsita requesta for ictorsustion (RTI's) 04 pr.mmaram s ut a sev e n ws 4 44 6w Based on the oricirW4 analytical scopics provided b7 VSAIAls Pu11xun These absenbles me-bu,ilt data packages for nach pipirJ; analytioni.
consint of the e trrent 'a> built within toleranus' loometrica and suppert strav&ngs, or tbs latest revis$on of non-asbuilt supperta, with all open charge noticts or field problass. Pullman fo*mally tranacitA th1D PAChagt to the CPC ConttructiCB afe built codrdiA3 tor.
CPC Iccs tht' receipt of the package, perforc4 a reviW for coupletonnas, and forwards the packago to Lbe V341$ coordir.at.or in tbe PS A valkdown grcup.
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HOV 20 '91 7tM PAGt 8 0F 39 The PSA walkdown acordinator logs the package sad perfore.n 4 comp 14mrson review to ensure that 111 requirco isometrie and hanger ambutit cravir4s vece trenicitted as identifie d en the 80001:a sheet (Fitsee 6.21), and that they are nr.rkow as 7H or 1005 as but'.) r*v isions, If tt e tranaatttat is not complete, it is rejected t4ck to Minsn via the GTC coorcitater for correction.
g A
- p e.vad.asins' task is perferned to ri epre tee anpack for assignaont to the finid walkdevn teams. Pro.pckaging obtaics the pihk volkdown uravingo trou drawing control, r etrieves any grevious renline r.arksd-up drawings frr.c previous walkdevns, (wnen ptrferntec Phist 11 walkdosen) and revaws the anpok for coupling to other M cka ge s.
L Anpacks are easigned to the walkdown tear.3 based on current systeo triorities try the PS A coorditator. The scope and cantent of the valudowns vary for Phase i vs. Phase 2 packa6es. Details of the walkdowne are $roviied in the ic110 wing sect 10ts.
The field walkdown data is marked on the pink walkdown drawings or one of the standard forna. After the valkcovo, the field e
Jnferestion la transcribad onto the fornal redline white copies of the drawings. The red 11 ass kre stamped 'V3111179-14 heoonciliation' and signed / dated by the walkdown tsan nebberti. The walkdown er4At.esrs chack each otbor's ewk to e*iare ti.e accuracy of the redline s.
Any noncontcrains itens seen during the usikdown at a documented on a devie. tion repet request (DR!t) to CPC. Exa:ples could inaude an iccorre'.t assenbly type, or a deleted hanger that has not been r ebov ed.
The valkdown engineers are not perforcing QC inspretice, however, and are caly ne, ting a;Mrent nonconformanoes obritaved darin4 the norcal cotras of their job.
After valkdown and cr.rkiLC up th's redline copies, the pacPage is given to the 'NckS61ng' sub.6roup in }3A where wdditional data is assembled fo" both th9 pipe stress and unpport portions of the aralytics1. and sufficient copien are nada for the offsite enginetrant offices.
'lhe pekacing activity is decuribed in detail la Section 6.5,,
Tha lead accines.* then fornally trans=tts tha cocpleted package to the desit.nate,t office for raconcilitition. A manple tranaaittal lette:* is shown in S$ction 9.
This letter also etma as a check 1 Ast for the transmitt.al.
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PAGE.Cil WU TO ' 91 7:53 PAGF 9 0F 39 63 PRASE 1 (755) VuxtcVN The Phase 1 engtueering walkdown is perferned to review the piping configuration against that shown en the at-built isometrics (to ensure against scons discrepencies), and to d efiew hanger configuration to that abewn en the as. built e'apport drivings.
In addition, certain inf 6tuation not included on the Pullrat abbuilt cravings in u. nod ty the reconciliation engineers to eliminate emasively e neervat ve astucptiens that could result in unnecashary rework. The valkdown en61ceers are reepcasible for obtaining this supplausLtal.fata, end docucenting its accuracy.
This supplocental field data is listed and deteribed below.
In addition to this 11stier., checklists are used by the walkdown tence to help ename couptetecess (.f the field 4ati. The 755 valkdovu checklist is shown in figure 0 31 6.3.1 Phase 1 Piping Walkdcun obtains the folloVirJL datal s)
Valve obrate crientation tcturmation h)
Vent and drain in;* creation if not a> built 0)
Vain veador, prosaure class and tag ruaber.
d)
Fenetration locations and anaular cleritances at toth ends or thi, penetratien. If there are cultiple pipen in the c.ame penetration, pecvide a sketch of their configuration and indicate the pipe to pipe clearances.
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Du11 ding joints (eetsrio joints) if not indicated on the an-built drawing fron PPF/CPC, Idettify the building to which supperts attaen, py.'.ng particular attaction to attuations vbere the pipe is in one building (i.e. nuriliary) but the support attaches to anoner (i.e. centainoent natarior).
Sapporta vill coessionally attacb to two r.emrate buildings (1.9. a valvo hous.e and adjacent stora6e tank) when suitip!e
'wacirc is need. This data e.hould all be dooumer.ted en tr.e red 11m s, f)
Omitted dinoa41ons for pipe sognento, compoonnts, evppe.ats, or
- fittin6s.
L' hen a> built dicensions are not indicat44 by Pullr.Ar, de walkdown te4m may taka the coawesents and notate them on the rediir.es, cr the coordirator Lay reject the sankage took to Pullt.an tared on his judgenact of the difficulty to ob t.a in th e Last anary ca ta,
g)
Vender pipinc informatica will be requested from Pullman where e
a ppl icabic. Vendor gdpir.g 1.t not no. built, and vill be supp)1wd directly to PSA. Mi an alterrate, the volkdown teans cay take the tpproprduto (14d anasurements on vendor pipinc, at the mikdeva coortituter's atscretion.
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PAW 10 0F 39 b) 1.1.%ited claarances within a 1/2' annular space arcund the pipe will be identified on the iponettica for consit' oration in the subsequent rattle point gescan.
1)
The highest point of attachner.t is to be wted for it.e response spectra selection,abeets.
j)
If the anteck is tubi'24, identify the locatica and crientatica of tube track on the 100netric.
6.3.2 Phase 1 Soppx't !!alkdown obtains the folicwtof, datas a)
Jocument arg attaching Aupports and these tag nunters not shown on the design cesvins,s.
b)
Cheer so ensure tbst restraint type and direction catch tbo de sign drawing. If noe, doce';ent the insta11od condition.
c)
Document restraint clearances for s'Jpports within 10 pipe dianswers of rotating equipment in Mth the restrained and ucrestrained df.rections.
d)
Document th Un pintes tot shown on design drawinga. Also tete stacked ahim plate 0,onfiguratiens and mininun shin width.
e)
Excess weld on clip an&1em beyond normal weld returcs. this trovides intcenatten to the antlysts on end connection boundtry eenciticas.
f)
If the pipe rests on a rack, or the tact is used as part of a support, obtain chain cimensions for the Inontions where the pige as in contact with the rack. Also note any lugs attached to the pipe ir close pros.tetty to the enok that are ut part of an exist tu pipe support.
g) 1r the supperts are #31.1 overitp and atter inzoops, ho Wall:Cown 11 required. Tug futican as-built daawings will forn aufficieret documentation for the in soope reoone.tliation.
h)
If supports are class 1, reasre and doounent cantslevee an;;
pin to pin dimensions. This is needed for realistic st&ffness calculations in the bcce effice.
1)
Donunwnt building attachants such as onbed plates, base plates, end building 4ti.el per the following anctions.
j) hennt Supports - Verify that the parent support identified on a baby upp rt drawing is correct..
If the baby support being walked is attached to as out of scope unit 2 hanger, the unit 2 parent nvat be identified 'as-built' on the support drawing.
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The node scint> identiflot on the isonstrico should be terified to answe consistency vith tne nupport and stress drawings.
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PAGE.013 NOV 20 '91 7tS4 NCE 110F 39 6.3 3 fabedad F1ntes a)
Aoquire the ap;ro;riate edad aketch 'crewirca (. located in the V-Suu controlled craving n'.icks) latelled *SrX8C'.
The civil structtral dravig numbers are crosa referer.ced just above the title ticck.
b)
Locate the utill:ed embed ar4 document ita, cunter, type, and aise on the appropriate buildig attachroat form.
c)
- he embed control books any be used to derive supplemental aubed inforcation. fasad cn the civiUstructural number destgaated en the support drawing, locate the t. ant.or tag number, and the ecbed number Will be identified next to it.
The type of plate thould also be specified on the drawing. The control books are subdivided by civiUstructural drawing nunbers.
d)
Enbod utilization she ito are only required for tase plates not
- hen such a tame plate is found, abwn on the embsd drav124.-
the walkdown coorditatcc issues a letter to BPC request 14,that it to incorperated into the civil drawing.
e) 5-min violations (per F.5) need to be documented for other attachments to on an embed only vith respect to the specific walkdown r.upport being reviewed.
6.3.4 Structural Tn.flace Steel a)
Document the location of the pipe suppcet attactnant on in-place builcinC ateel to the nearest end point on the hanger Cr av ing. 16t6 tbs team type also.
b)
Obtain the ep;rcpriate beam euctvr from t.be structural eteel drawings freu th's beam icg book.
c)
Using the reference dimensions given on the support drawing (key plan icoation ) that were acquired frec, the walkdown, the i
aptroxtcete location can be dsrived utilising the structurni steel, civiUntructural and crtLographic desWini;s for laan/colusa identification. This 1.s required because the disenator acquir$4 during the walkdown may not be the arrow end (lsf t and on the beam drawin6). Thim ;rocasa also identifies the besp/ column tumber.
d) kten the beam / column is identified, document its bumber en the rad 13ce drawin6. Attachment locations on colun.nn will be given by t!.e attachtwnt elevation, and attachment locations for terms will 64 siVen froo the left and (arrow end) ut'en possible.
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PAGE.014 NOV 20 '91 7:55 PAGE 12 QF 39 6 3 5 Iase Plates a)
Document support attachesnt locations'to beso plates. Socie support drawiras speci*y tolerances on base plate cetails from bolt location to the plata center 11re, while others specify tolerances to the conter11ce cf the attachtent and/cr veld.
Thenfere, docuse:at the actent location of the attachment and veld contarlite to the plate edces, as well as the bolt centerlinsa to the plate edges.
b)
Document any eye distance violations (per F 5) sach so proxicity to other tese platas or est>eds. Wis la done on the baats of center 11r,e of t.he bolta to the edge of the enbed.
6.3.6 Halkcovn Documentation Af ter the walkdown, all informatun docesanted on the pink Walkdown drawir.gs in transferred to the white redline copies cf the asumatric and support drawings. We redline drawir4s then beocco the design input for the piping and support reoonciliation engineers.
The copies of the redline isometrio and support drawings are stamped and siisned by the auther and checker.
'V Camu 79-14 Reconciliation e
The ocupleted package is then forvardsd to the cognt: ant enginear in the packacin5 Croup.
6.4 PTd52 2 (100$) VA1.UOWN The Phase 2 walkdown is initiated after Pu11ran co=picteo installation ared rework er the Trevioualy uninstrailed p pw nuppor ts i
within euch sr.alytical package and revaeen taese drawings to reflect the An-! Milt within tolerance conditions.
7be analysta packages defined by VSi)U and Bechtel in the 7M Ptana vill be the baats for the 1005 packages. Scoping infwnation Will be obtained froc the 755 VSilfJ Punch 11st for Phase 2 packasca. This scoping internation includes the in-soone isosietrics and supportt.,
and those cyn' 'aps i equired to developo boundary cov%tions for the a nalysis. 7tv Phase 2 walkcown checklist in abovn a Figure 6.4-1.
6 A.1 Addltional Stase 0 Walkuown thta The 755 valkdcvn stepe given in sootien 6.3 are used to ot'tain field inforcation fer the supports that were not 'in-lhilt' during the Phase I walkdown.
In addition, the following steps aboitid be followed to complete the 1001 walkcown pacPageI a)
Drawincs that We-e revised rance the 1bs,se 1 waikdown to incorporate Abysical ch7tsi.s cust be walked down (cf Thase 2.
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NOV 20 '91 7:55 PAGE.015 PA K 13 0F 39 b)
Any wikdown inforr.ation Lt.at was maased deficg the Ph&M 1 wikdown (e.g. valve tag nus,bers) because of previously inaccessible areas aaould te obtained duric6 the Phase 2 walkdown if posattle, Results of Pu11:an's 14 (Tan-4) QC valkdown ray be used to supplenect the inforcation collected by the velkdown tosu.
c)-
When additict.a1 valve inforcation is obtained during the Phase 21 valkdown, the valve tag nucter, annofacturer and pressure i
clast abould be taken from the valve taga in the field and docunented on the isometric tavings as indicated belows Additional Valve lutornation
_- m
- v.- v - -
p Valve ID Pressure Class 4
e III 223 YYT MM 1
79-14 W
If the information on the taga la missing or different than j
kbat la marked ot, the valve bodies, is a manufacturers plate, r
the valve mark nucesta and valve specifloation number shoujd a100 he obtainnf..
d) ill supports abould be reviewed in the field f9r general i
conf 14uration to identify any new common support attachtents.
7f new common attachnents are found, these should be identified on the redlinsa. In addition, the response apostra selection sheets should be reviewed for possible changes. -
e)
If additional penetration details are requested durir4 Phase 2 walkdowns, the detail may be $bwn on the redline isometrio drawings.
6.4.2 Perised I atwings for Phase 2 L'alkdown It drawing revielons change between Phase 1 and Phase 2 walkdown.
the isometrica or hanger dawaings shwld be reviewed for data that could aft'act the initial walkcown. This could include added braces, new ooseson supports, ato.. -Corrections or additions should be made to the latest revision redline, and the old revision data should be lined out or noted as superceded en the new revision. Stamp the
- 14. test revision of drawing and add the following notet *$upplemental 1
information for wpport/isonstr$o Rev.,,,,,,,, Red 13me Rev. j Tf the.criginsi redline.ia est availabls at time of Phase 2 walkdevn, one may be recreated with the following note: "This drawing replaces original redline drawing ganarated during Phase I-79-14 wlkdown. " It la also acceptable-to provide the offalte valkdcwn drawing, assuming they-nre legible.
engineers with signed and Checked copies of the criginal pink 1
Standard I.otes are cut on the redline to balp ensure proper use of i
valkdown cata. These are shown in Figure 6.4 2, as approrriste.
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NOV 20 '91
?i95 PAGE.016 4
PACE 14 0F.in 7.0 10ST.W1 LED 0Vil FictiODO following completion of the field walkdown and crt.atior. or updatir; of the redline walkdown isonstrion and support drawings, the package is ledtned out of the wclkdown sub-group and transfered to the
(
Nokaging coordirator.,
The Achaging coordiratcr (frat auB1Cne the anpack to the
'tireakdcun' clerks, who separate and copy the wandown pckage contento into foldera fcr o*.ross, suppports, and for site filinf,.
?.1 Strela folderI i strees foldte is created for eacu isonstric in the analytical pa cka ge.
The folder contains the redline itonotric for inecopo isocatrica. and copina of the redline isonetric fce cuerlap 1potetrica. If available, a D!C apareture card of the redline is included. If not available, an aperature card of t.he redline abould t$ cade after eccletten er the 1005 reconcilietion.
The stress folder containa either tne scopieg identitleation forti (phase i pekage) or a copy of the 7't punch *.ist (phase 2 ;4ckage) s for inacope / overlap definition of laccetrica enc hangttra.
ant deviation report requests (IER's) that may nave bien generated are included, along with lug, stanebion, anchor, tearien pad, and trunion cravirte.
In general. all of the applicable data c%41ned in the piping walkdown is included in the otrnso folder.
72 Support Folder The suppcrt folder contains the redline r.upport denwings for each support en the associattd tact eteir. In addition, it centains all npplemental forma and field data obtained ducir8 the support vaikdown, such as oct>ed attachuent ferns and support celete abeets.
131.1 parent support drawinsa, or other out of scope parente for in econ or overlap supports, are ion'.uded in the support package.
73 file folder:
ne filo folder contains copies of llc isometrio anct all supporta Jontained on the twastric. In addition, all field walkdown pink ooples of the drawiry;s are stored in the file folder, 9
.n
... ~.-
- -. =
NN 20 '91 7:5G PAGE 15 0F 39 4
7.4 Post fac14cing The across and support folders are transfered t.o the cognizant stress acc support Nckaging engineers, respectively. It* Mekagieg engineser are respont.ible for ensuring the cacpletonssa of each foldar, anf for checking that all 1.1soop and overlap taometries und hanc, ore are Nchgod Locother for the off site acalysts. An important function of the support mehger is also to obtain all wigitul harcer calculationa trec DDC, or other snaigned party, for offaite reconciliation. Specif.0 goldelins3 that per tain to t t.e packaging effort include the fellovity,i a)
The origir.a1 redlines cay to sent offatte for inseope taomatries. These redlinea vill tre rettrood af ter reconciliation, at which time FSA util obtain nicrofilm copleo
!?cm DDC fcr the file if none exist.
Pith duplicates of the redlines will ta sent offsite for overlsp or partial frenope Lascet.rien.
b)
The crit.ical stress calculatico 11 obtained frus DDC for each -
isoustric for off site tranmittal.
The cale should be chucked for cierofiche copica of the computer runs. If three copies of the fiche are etall in the cale, one ahoJid t,e renoted and returned to DDC for separate btokup tillag.
c)
The packaging en61ceer abould review page 4 of the etress caiu for open itema, and prenride any data pessible.
d) 7be h6nger drawings are requirsd ter Support Susnary Tables (SST) preparation off site prior to pipir4 analysis. It is imprtant, therefore, to transmit the bandt? redlines at tha aame time as the etresa pachce to avgid reconciliation delays. The crigiral har4er calet.laticab should bs transnitted a s soon af ter. or concurrent vita, the a:.rees Mckage as
- possible, c)
The V3 AMU SCAR program should te used to check each dravira; for any open change notices, cr to locata calculations, f)
Checklists ter the stress and support pekat,134; are anovo in l
figwen 7.51 and 7.5 2, respectively.
4 n
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NOV 20 '91 7:57 PAGE.010 KII 10 0F.39 8.0 Requests for Intweatios (RTI's)
When the otraite recenciliation groups encounter difficulty in either " performing their analyses, er in locating the itiornation needed to perform the ar.alysia, they cay requent acditional assiste new reto psi in,the fb-a cf an Br!.
If an RFI is fcr additional fielf dat*, such as mur.suring specific chait ditenato".s to minimite toleracce uncertainty, the volkdown engineers say oetsin and transuf.t this supplenantal a.t. built dat.a on an $TI, or Suppleeental Tield Inforcation form, er squivaleat. Any
(
dsta obtainted by field engineers c.sy t,e considnend as design inpus proviGed it is 41stled and dated by traiced and tiualified field v igir.e ers.
in RFI coordinator vill be responsible tc.a interfacing with the offsite org.inserir.s effices, and for distritnti:n the RFI'h that. are receiv ed.
RTI coordinators will genera.11y t>s desitwatad in each fucational proa; valkdcyn, pachging, ;$pe strers, and support 5
DCIPa.
90 Senpte Fors.s the folltwier, fors o tre provided for vse by f he valkdova and paokasine, etv,ineies.
Picuae e Fere ID 9-1 Eae4 Plate Inf ormation Form 9-2 Common :Japport Attachment Fore 9-3 Deviation Benert Request 9-4 T&id Mato Internation Toru 9-5 Exs sting steel Informatio.1 Forn 9-6 Fe r4;rint Load Request 9-7 Creenline File Request 9-8 hput for Respose Spectra Selection 9-9 Supplemental Field Information Fern 9-10 Valys Identification Sheet.
9-11 Ysive Orientatien 9 12 Valkdown Penetratin rata Form 9-13.0 thru S.anple Transmittal Letter to off site 9-13 4
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HOV 20 91
'i57 PAGE.D.?
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.020 NOV 20 '91 7 50 PASE 18 0F 39 FIGURE 6.3.1' VALDOWN ISO)MIC CBCEL!st MR 755 RED #CILIATION 4
201stRIC 1 27.
ANALTt! CAL NUMBER t
t TB FULLOW30 2725 MALL BE toCU1ENTED:
M8 E/A
- 1. PIFK RUE DDEF3 IDES AND LOCATIDN OF CDNF0EENT3 i
- 2. TALTE OFmATOR CCIENTAT10N IF NOT DDICATD
- 3. TENT AND DIAIN ttrAILS 27 Not INDICATO
- 4. YALTE YSDDR, 77E55U12 C3.488, AfD '!A0 EMBLIA
- 5. FrwEtn ATION toCATIONs AXD CLEARANCE 3 AT BOTH ENDS
- 6. INTRPERENCES WITND 4' ANNULAR
- 7. BU23. DING. MINTS IF NOT DDICATED WALucWN TEAM LDTNGt DATE CHECEIR DATM
- TRIS 130pk1RIC VA8 Btf7WED TO DE CDMILETE AFD ACCUBAft.
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NOV 20 '31 7150 PAGE*E28 PAGE 19 0F 09 FIGURE d.4.1 WALKICW!! IS0)'3TRIC Chic)1:.sf PEA $E II 150!Z1RIC INMS5t REY ANflYTICAL l'012Dt TEE IVLLOWTNG c1ALL IE %0CUtztTTED ON THE CHANGED AhEAS OF 17tt ISofETilIC, AND Ih* FORMAT'.ON NOT IOCUl2bTID IfJRIT;0 Pl!ASE I VnLKDOWN YES fuA
- 1) VALTE OPD ATOR ORIENTATION IF i;CT INDICATED --~~-~~
- 2) IINT AND IR AIN tttAILO IP NOT INDICfiED ----~~~~~-
- 3) Ve1VE T ENDOR, PRES 5URE CL AP.$, AND 7AO l#hBER -----------
- 4) PENITR ATION LOCAT.10N AITD CLEAR ANCES AT BOTH D.WI ~~---
- 5) SEISMIC J0:rT3 U i 07 I!tDICA*rD ------.
- 6) PIFE ZECIENT AND CD10VNENTS/ FITTINGS OMITTED DII't.KSIO!!3 -
- 7) 7tATC R P 1 PI N G - --.-------- ----.-----------~~ ~
VALKt0WN TEAH:
AVTRO.1 DATE:
CEECIER DATC _ _
THIS ISOFETRIC VAS RETIrdED TO BE COMPLETED APTD ACCURATE R EYIIVE,,. -
_, DA73 i
l i
NOV 20 '91 7890 PAGE.022 4
PACE 20 Of 39 i
Figues 6.4 2 Standard Redilns Drawing Notes l
l 1.
NO MEA $UREMENT 07 DOCUMENTED P!PE LEGMENT LENGTH, IN.W10E WELUS.
COMP 3NENTS, ETC. REFERENCE CONSTRUCTION SPECIFICAT!DN. X4AZ01.P3/P4 TOLERANCIS.
2.
NO AXIAL NEAbOREMENT ANU DOCUMENTATION OF SUPPORT LOCATIONS. REFERENCE l
CONSTP.UCTION SPECIFICAT!ON XAAZ01.P3 TOLERANCES.
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FOR SUPPORT LOCATIONS. $fE KEY PLAW SHLET.
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NO P! PING INSULATION INSTALLED AT TIME OF RALKDOWN.
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PAGE.023 NOV 20 '91 7159 PAEE 21 CF 39 FIGURE 7.5.1 1
WESTINGHOUSE PLANT ENGINiiERING DIVISION 4
,- n.
m, 1
or 1
1001 AS4utit Packsofre Checklist (Stress) M
~~"**
PMQstot asynde DAIL gE& p PATE CHK'p 54
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y/A ly.$atw N/A 1
AtTaessa upt. _
Its WAta We teos up s.41mme ter di Is.aeeve.te.eetrina 1,
.- -4
.. -..- (wigami tad h1w 12mm) ---
2.
775 Ut Beetsmo ter ta, amepe teametetes Erf used fee teos rewardena (artsten1)~
~*
3,,1908 us Deelena far e'.1.orarlap lanettrise (ntes Stae)
)
[
4.
195 U A access bles for all 6 "-
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imametries (erlatama)
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1.* 1oos us veneer ytyise does (art vedam>~~~
i frturitse Cept)'
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perased vaave seestirimetten*ateet (if ast~
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fAeuuitted on 1005 roelas, wprL i
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Aerland gespannt Apeente De4997,&as sheet I
( espp ) -
= ---
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4.
swised teostra'.aes ants Pers (eept) 9.
Dortas4/&est4as41 Doristlas separt Woqreest-~
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(espy)
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it. opes Items in iniFeisei stan'146 fe~eitT
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11, acr m. 7t118 a, su's as per **48 (espy)._..
it. Mreserstsen amm1 larwanties
- 13. Ftt's eM stre Aapse4146 Latest vwrieten ol'. -..
. + -.
P439's (eeWF)
- 14. gaarettane for comptter room stattaL'ia in este-
" * ' * ' " ' " - ~ -
peeknes is. m.m e.o 6e traema:tiala tre, Tse mesipta
$does4taat en pass 17.1 er este poetess r
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punireas It est eve &ambie, Adeskatt tw s
.. a.. W anopes teniptient Phu
. -. - 4 (montaes h.
8 asens supeeses done ter.-
91selsemesete
- 18. Flas.1 amatet vertrimassas emomb11st (most)
- - - ~
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- 19. Insersal in,ee swersetsmo (ess arr=riat e,srettas a
temy) obteland treet AvettelapFH (sepF, if eve 11akte)
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- 20. htye apose/Jreertogs it ALfrurest rendes saan tend am 755 us aanlysta (tairk sheet and --
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opom/eparise)
- 21. wat wereriesm/setasse w it -'- -
estrecent resates that imrd im 798 us,,~
hemlyhts (eark eneet set spee/e urias) i 12.14 test terlatese of tesestries, esadas.l _
munnemas. P&tr a, e64. (esek sheet espF
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NOV 20 '51 7: 59 PAGE.024 PAGE 22 0F 39 FIGURE 7.5.2 a
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PAGE.023 t40V 20 '91 G:00 PAGE 23 0F 39 FIGURE 9'1 WESTINQHOUSE PLANT ENQlNEERING Olv.510N
~
r et6 sa se MSE PLAff INFORMATICN FORN en sao.scr nav la
- ,474 cn o. s v of f s r,an c. e, -
- ugg v0G3,E
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s a $s. no e is, 4, 6aowe - --
qHJ V.$utu Support No.
Rev.
Isometric No, Civil /Struct. Dwg. No. _
IPlan)
Cfvt1/Struct. Cwg. No.
(Elev.)
- Provido orientation of base plattr (plan, elev.)
- 5how cer.terline.01 attachm ht and weli to til bolts on the plate
- Locats base plate with respect to colkm lines and elevations ac-
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PAGE.026 NOU 20 '31 Bt00 F. AGE 24 0F 39 WI$flNGHOUSE PLANT EN0lNEEPLING DIVISION FIGURE 9.2
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5,upport No.
Line No,
,,, O l 3 Ci!.l i M Support No.
Line No.
OisciMine Support No,
Line No.
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PAGC 027 NOV 20 '91 0 00 PAGE 25 0F 39 wt5TINGHCUSE PLANT ENGINEERING DIVISION' FIGURE 9.3 f.i6 a fin s tr/IAT:cti FIPCM in%2:n
~~
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m Trm itan(s) idanufind helcw is/are rce.carf'onws in Wtnce with a:r.stnr;tien socificAtlon(s) X4A201-P3,P4 and/or r$.
NatATIO? PAOW210.
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cafe sec.
,9478 Wet $71eroseOuta scasd $3646 Matt 6
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d PAGt.02G NOV EO '91 0 01 Pali!. 26 Of J9
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l FIGt!F. 14 WIKTINGHOU$t Pt.N,7 gNQlNEIRING DIVillOM new r.
...r wi a _
lwiis
(.M$t0 PLAtt INFCAMATIO_N F0llM
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un
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,eig s wa, 4 a w, GJHJ V.$AHu support No. _
Rev.
!sometric No.
Civil /5truct. hvg. No.
. (Plan) tabed No.
Civil /$truct. Owg. No.
( Elev. ) Type __.
~
LIST OF_M0f !NSTALLED $UPPORTS f
IN$fAl.l.!D
{
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S'JPPORT3 e
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pgp gg, 4tf f W94 84f5.A E'b O Y NI$
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PAGE.029 140V 20
- s1 3:01 PAGE 27 0F 39 F10JRE 9.5 1
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l Wl57tNOMCU35 Pl. ANT ENGINEERING DIVl510N ExtsTING sita INFonMAt!M PCRM m.,
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Isometric No.,,,,, _
Structural $te Owg..No.
l 5eas No.
- Draw enough views to adquately locate the support to the nearest cone.ection point and provide orientation (plan, elev.)
401mension the distance to the contarline of the been or the edge of the f14tige.
- !f the attachsent point is on the web, dimention to the nearest i
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NOV 20 '?!
0 01 f
PAGE.030 PAGC 2B 0F 39 WESTINGHOUSE PLANT ENGINEEFilNG DIVISION FOOTPRINT LOAD RECL'EST
'Act P RCw& C T A4,t dd A
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DAY 4 Can0.$t O&YI Cisk'E. g t V0GTLE gAji 4 @.
CAbg. ano.
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9464 too.
Q MCV:*
a, REWIRED TOR SUPPORT NO.
AND ARALYTICAL NO. -
COMPLET!OM HVAC support as located L* low.Please provide reactions at Thate reactions era required to resolve 5-MIN HVAC/ELEC.$L7 PORT NO.
BUILDING C.S. PLAN Onts._,___
__ LEVEL:. _ _
_ C.S. SECT. DWQ.
AREA:
ROON 5ECT./ELEY.
_ g DIB CONTROL NO.:
(if applicable)
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PAGE.031 NOV 20 '91 St02 PAGE 29 0F 39 FIWRE 9.7 4
e cm2Nt.mc ruz, M
The followire pterdirw flie(s) is/am revisini for asetilt reconci3.iatfort:
G. L.
DEDFF.
- ww h WR TII2 SetAtA7ICM.
CDM23'It24 Cr SUPPORTPC.
10.
PfC. NO.
M841.YTTCAL_ PNG.10.
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l pdEh'0F39 NOV 20 '91 0102 FIGURE 9.8 wisTINGHOUSE PLANT ENQlNEERING DIYlll0N TIf 48
'444 input FOR etsPMst $PicTU ttttCTIM es r saev
.wi-tm eau can....
sari c a...,
av.
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=
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Isomet,ric Drawingt m highest attachment point of the supports to the building (Desigt.ated by the dravtag number) is at elevation a t hipport u...
The following supports attach to buildings other thin the building designated by the drawing number.
Support Highest Attachment tievation/ Building G
e r
g S'-
_ t#
1 SATE CME. B. t v
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GATI Caet t $1 OI'
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NOV EO *91 8:02 PAGE 31 0F 39 l
WESTINGHOU$f PLANT ENG1tillRING DIVISION FIGMf 9,9 i
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The Y.SWJ Open items log and the design assumptiens of the stredt cale's have been reviewd ano all open items have been resolved or suf fletent inforuation is included for resolution by the offsitt grouri.
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PAGE.039 N W 20 '91 8:01 PAGE 37 UF M
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Thir (*.; ment ruperwden in its entirety the initial ReviJiou 0 issue rtf orer.ned t.6.sve.
A r+ quired by previour audit comitaants this document vill be 1:. sued
'a. Jar acetrelled cistrCw.len with ta s renainder of Volu:u 1 Piping In the intera, this is approved for use ir Guidelines by U.* '13/86..
V-$A!.'U for FP-7 reconci'istica valkdowns.
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m Georgia Power i!
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l July 27, 1987 United Strtes fluclear Pegulatory Commission i
Document Contre 1 Dest Ffla:
X7BC24 Washington, D.C.
20555 Log:
GN-1352
Reference:
Vogtle Electric Generating Plant - Unit 1; 50-4?h j
IE Bulletin 7914; Letter CN-1273 dated 12/31/86 In the referenced correspondence, Georgia Power Conpany (GPC) notified the USNRC that it had completed its Final Design Verific:: tion Program for Safety Related Piping Systems for Unit 1 of the Vogtle Electric Generating Pinnt (VEGP).
This program was destgr.ed to address tne requirements of USNRC IE Bulletin 79-14 and was completed during the construction phase, for plants undnr construction. IE Balletin 79-14 and its supplements require construction gemit holders te inspect all s,'ety-related piping 2 1/2 inches in dia:neter and greater and seismic Category I piping regardless of size which was dynsmically analyzed by.omputer.
The JPC Final Otsign Yeri'! cation Program consisted of enoineering/constru;ticn usikdowns of all safety-relsted oiping systems regardlees of size w analytical method.
The following is a summary, by item, of the methods utiliAed by GPC to address the 1
requirements of IE Bulletin 7914.
l 4
f^
item 1:
This item is nat applicaole to VF.GP since the requi rement s of the 3ulletin were addressed dt' ring the construction phase.
Item 2:
For portions of systems whWh are nomally ace:essible, inspect one sys te'n in er:h set of redundant systems and ill non-redundant systems for conforniarte to the seismic analysis input infoma tion set forth in design documents.
Include in the ins;;ection:
pipe run rjeometry; support and restraint i
design, locations, function and clearsnce (ine.luding floor and wall peretration); embedments (excluding those covered in IE Bulletin 79-02); pipe attachments; ano valve a,d valve operator lo u tions and weignts (excluding those covered in IE Guiletin 19-04).
item 3:
In accordance with
! tem
/,
inspect all other normally accessible safety-ralated systems and all norualb inaccessible safety related systems.
0bf.[
f
~~
ilP1 2024 U. S. Nuclear Reguletory Comission Aly 27.1987 File:
X76C24 tog: GS-1362 Page Two
Response
Althouph not required by IE Bulletin 79-14, the Vogtle Final Design Verification Program for Safety-Related Piping was a
p e rf o n.ed in two phases.
Phase I was cenerally conducted when approximately 7% of the supports and all the piping was installed on a line.
Pnese 2 was generally conducted when 100I of th supports were installed.
The walkdowns were structured to support the to phases of the final design verification ef fort, The Pha*.e I walkdowns gathered data concerning the following e!cments; valvas and valve operator identification, location, anc orientation (this infomation was used to verify valve weights); butiding seismic joints; piping geometry and clearar,:es; support design, lochtion, restraint type, and clearances; Lse of shim plates; building attachments such as embt>d plates and - base plates; t u t,1,1 g interfaces; and penatration location and clearances.
The Phase 2 walkdowns, which wde performed using the information gathered in the Phase 1 walkdowns, collected the following' information:
field data for supports or other attacrments installed or reworked subsequent to the Phase 1 walkdowns; A review of drawings revised since the Phase 1 walkdown to eraure the valitiity of previously gathered 17f ormatien; any infomation not available during the Pht.se 1 walkdown or any auditional dab requested by reconciliation engineers.
Walkdowns were conducted using procedores developed spJcifically for the Final Dtsign Verification Program to address the requirements of !E Bulletin 79-14.
Copies of controlleJ as-t,uilt drawings provided by the piping contractor, Pullman Power Products, cere used in the walkcowns.
Data gathered during the walkdowns was documentec on the drawings and provided to stress reconciliation engineers to be used in veri fying the qualification of the as-built configura tions of the seiety related piping systems.
Mhen changes were required to piping rystem components and/or-design documents as a result of the stress re:onciliation l
enginee s' evaluation. design change documents such as Drawing 1
Change Notices, were issued in accordare: with established project r,rocedures.
When the c'esign change; were implemented, revised as-built drawings werr prepa red if required and submitted to engineering for evaluation and incorporation J
into stres; calculations.
Stross Reconciliation Notices (SRN's) were issued to identify piping systems for which the verificction/rteoncilict.'en process was completed.
)
t i? 2 :t a a n, l
I U. 5. Nuclear Regulatory Commission July 27, 193?
File:
X7BC24 t.og: GN-1362 Page lhree item t.:
This item is not applicable tu VEGP since the requirements of the Bulletin were addressed during the construction phase.
l In conclusion, the GPC Final Design Verification Progrw. has effectively l
ensured compliance with IE Bulletin 79-14 for Unit 1 of the Vegtle l
Electric Generating Plant.
A similar program as that used f or linit i l
has been initi:ted for Unit 2 and is expected to be completed prior to fuel load.
This correspondence contains no proprietary information and may be j
placed in the NRC Public Document Room.
5
>Pws-
- p. D. nice Vice President.and Project Ofrector, Vogtle Project i
CWH/PD4/je i
xc: USNRC - Ref on !!
l Suite 2900 l
101 Marietta Street, NW Atlanta. GA 30322 H. G. Bater D. R. Altmn T. Gucwa J. P. O'Reilly J. A. Bailey C. W. Hayes R. E. Conway G. Bockhold R. W. McManus r
R. H. Pinson C. E. Eelflower Sr. Resident (NRC) j E. D. Groover J. F. D'Amico C. C. Garr<ttt (000)
R. N. Bellamy O. Feig (GANE)
J. E. Joiner (TSt.A)
NOPMS r
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31*4 Pe</US V SAMU 10660 4
FROM
- V.SAMU VIN
- (404) 554 3526 DATE
- January 2ti, 1989
SUBJECT:
TINAL17.AT10N FROCpAM 7 Ct.0SEQUT P
1SSUED TO CORK!CT VTDV.3SC 6614 deced 12/14/$5 1
4 TO
- S. Owens, C?C C. Markam H cc
- T. I.oceff, R&D 701 D. Sevoll, BPC M. V.
Barlow, */.SAMU Sea Distribution 2
1his letter is to notify yeu tbst all engineering tasks have Seen Se FP 7 Final Design Verification Pror,taen for Safety corepleted foi Rotated Pipinr, 3ystems on t! nit 2, as identified in the TP.7 Pror. ram Description, reviaton 4 The FP 7 prograto is designed to address the requirements of the NRC IF.
l reconciliation The cortpletion of piping and nupport g
Bullet!n 79 14 is documented by means of Stress Reconciliation flotification (SRN's) i to Jeorgia Power and Bechtet. A complete list of SRN's issued to the 1.
This listing providen you with a project la provided in attachnenttha piping and supports in the TP+7 4
refere ce for verification that program have been reconciled to a6-butit conditiens by the responsible In addition, the FP 7 and TP.14 activities engineering organization.related to identification evaluation, and disposit".on of limited A.and inatine elearance conditions on safety related pipin6 syster:
mounted components (Rattle Points) have been cottpleted by bechtel and This activity is docus. anted in'opecial calculation V.SAMU.
The engineering requirements of the IE Bulletin 7914 X'.C P S.0151.
have, therefore, been satisfactorily addressed.
for the FP 7 This letter serves as the final close out report If thare.are questions concerning eny arpacts of the Prog wa.
program, or additional infota;ation is required, please cont:act me.
W M. E. Maryak, Maruger Vogtle Final Design Verificatien Finali:ation Progeait FP 7 Attachment MEM/ gab o'
l l
0 T1#
,=
,o_e,33cg,,4, cn no.,
WAemscvW FWirwytvatha 17Foi biocnone (T17) 3234991 Pullman Power Products Corporation ZOO wa.--n May 29, 1987 Georgia Power Company
[
Nuclear Construction Departent J
- Pact Office Box 282 Waynesboro.-Georgia 30830 Attention: Mr, C. W. Rau -
Mechanical Discipline Mancoer
Subject:
Vogtle Elet.tric Generating Plant - Units 1 1 2 Contracts PAV - 0020/PAV2 - 0010 4SME Section III, Class 1 Forged Pipe Tees L
Gentlemen:
With reference to your letter dated May 12, 1981, we are respondicg L
with our explanation of your concern to the " Root Cause" for the reported Forged Tee problem.
The apperent reason appears -to be the failure by-PPPC 'dngineering to incorporate the requirement of AX40R001-Table 2 "Brench Connections" (Noi,e 4-see Attachment (1) into PPPC purchasing requiremnts for "81cck -
J Forged" fittings.
Althougn we now understand the intent of Note 4, apparently a niis-interpretation existed at the time cf initial ordering.
Sotre history review is in order:
1.
The ASME Section III Code of Record for the Vogtle Prc.)cct is the
~ 1974 Edition.1975 Summer Addendum.
For butt welding fittings, 816.9-1971 is referenced.
2.
A review of. B16.9-1971 (Attachment #2) indicates that it <nvers OVERALL dimensions...for wrought... alloy steel welding fittings. The term "w. ought" includes fittings made frum pipe, tubing, plate or-foraings.
3.
The~ second-paragraph of B16.9-1971 states " Fittings may be made to special dimensions...other than _ those covered by this standard by a g reemen t... The fittings furnished do comply with the dimensional and -material requirements of 816.9-1971.
There ure no dimensiona!
requirements beyond "overall dimension" and welding ends.
The re -i s no nea-confonnance in this respect.
9
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' Pullman Power ?roducts Corporstli
.lV May 29, 1987
^
Georgia Power Company Page two.
u 4.
It has been interpr eted by PPPC Engineering that the term "special" in Note 4 of Table 2 implied dimensions other than the "overall dimen-sions" in Paragraph 6 of B16.91971, and as provided for in the second m
paragraph of the Scope noted therein.
5.
In any case, the intent of the note was not clear, and appears to have contributed to the problem.
'It should 'also be pointed out that references have been made _to Standards ANSI Bl6.9-1978 and MSS-SP-87-1978 in site meetings lately to judge the ecceptability of the fittings in question, and while we feel
-the useiof both standaros are appropriate for making a good engineering judgement, we tust indicate we were never contractually obligated to fur-nish material to these requirements.
B.16.9-1978 Para. 7.2 states that fittings made from, bloc,k,, forgings may be supplied subject to agreement between the manufacturer and pur-chaser. - MSS-3P-87-19 7 sets requirements for minimum radius at machined intersections and limitations on maximum wall thicknesses. -
, )
As previously pointed out - the Code of Record for Vogtle is the 19741dition.1975 Sumer Addendum. This references B16.9-1971 which does not contain Paragraph 7.2 as in the 1978 Edition. MSS-SP-87 is not ref-creaced et all.
The Project Piping Material Class Sheet FGO specifies fittings to Specification ASME SA-403- (Attachment. #3)
. In Table 1, forging material to A182 is " permissable rai( materials."
In conclusion, the root cause appears to be a lack of clarity in Noto 4 (Table ~ 2), and PPPC's misunderstanding of its intent. We under-stand the Supplier of the 2" & smaller fittings nay have made a similar mis-interpretation.
P We have made a thorough review of all other purchase orders and Fabrication. Sheets as requested in.your letter of May -12.
Attachment
- 4(Unit #1)-and Attachment #5(Unit #2) tabulate the spools involved where " forged row materials" were utilized in Class 1 piping systems.'
The Material Supplier, including the fitting, description and appli-cable Heat Nuder,, is included on these tabulations.
+
i
, -. -.... -.. -..,. ~. - - -. - -
-. -. ~ - ~ ~ ~.. - -..... - ~
i.-
Puuman Pmw Products Corporctiot -
May 29.-1987 t
- Georgia Power Company' Page three.
l
?
As' you have verbally requested, we have contacted the various suppliers
-of-the forged toes for their tranufacturing methods of the applicable Heat Nurrbers involved. While only Class 1 fittings.are now basically the. matter of concern,- the Pullman. Inquiry letters and supplier replies have also in-cluded fittings applicable to Class 2 and 3 piping systems as you have ini-
- tially requested.-
The Pullman Inquiry letters and Supplier replies are enclosed (in book-let funn) for the following Manufacturers:
' l Custom Alloy ReplyLetter5/18/87)*
Ladish Company Reply letter 5/19/87)
Taylor forge (Reply Letter S/15/87 & 5/28/87)
Flowline (FlowlineLetter5/20/87)
Babcock & Wilcox
.(Class 3 Fitting - See below)
- Custom Alloy's Reply for Fitting Heat No. E3402 has not been in-I cluded. This Fitting is a duplicate of the Fitting Under Heat:No.
- E3400-and ~a supplemental letter will be forthcoming.
For the-Babcock 4 Wilcox. Class 3 Fitting noted above, we have not re-l ceivcd a response to date as we were informed their manufacturing facility has been closed for more than five years. We hope to. receive a response soon.
In' closing, Pullman Power Products is willing to cooperate in the resolution ^ of-the reported problein. We trust, with the Supplier's Res-ponses - tnat an acceptable solution will be realized for the safe opera-tion of the Vogtle Nuclear Units Should you:have any coments or questions, please do not-hositate t.o' contact us.
Sincerely,.
ny }M)
A%'
l ohn M. Coleman Plant Manager s
j s
~ B. Edwards
- PPPC Vogtle (w/ Attachments) cc:
J. Weaver - PPPC Wmspt. (w/ Attachments)
- 'JMC:j s
)
~ Encl.
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-~
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7e 651 Smessee Stoet (t [-
OLtsburgr Penneyhenes 15222 Teespone (412) Sea 7300 Pullman Power Products Corporation 1990 May;24, _
Sechtel Power.Corporatton 15740 Shady Grove Road-
$ /eJd. Md./d < W4.-
/
GnIther*.40urg, Wary 1and 20077
(/Mu : (3 C/) 68" 3 T2 )
Attentlon:
'Mr. S.R. Kalarvtr
-Location Code: ELL 18
Subject:
Vogtle Electric Generating Plant - Units 1 and 2 Contract-PAV-002/PAV-2-0020 ASME Section ill, Class 1 Forged Pipe Tees Centlement in response to your Inoutry regarding tile f.iroacer af f ects of the block forged tees at the Georgia Power Comoany's (GPC) Vogtle Project, we provide the following explanatlori.
Through discussions with noir retired emoloyees and review of Dast corresocndence between GPC and ourselves relative to this issue, it was decided that the rect cause of the problem was from a !)ck, of u
clarity within the specification and a misinterpretation of its intent.
As a result of this conclaston, it was determined that Vogtle wts an Isolated case and further review with regard to other nuclear plants was not no?cessary.
If you require addit!onal Information, please adviso.
S i nce r a l'/,
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stfesses one strosns resubing, from the elevated ttm.
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Dirnensions in inches. Weights avad s.
Retivr.inD fittings ton be furnished by boring stvoight-line blonks.
Avuiloble in a wride re.nge of cas.on stainless
-Diometer of fitt!ng ho<e is eqwon to the i D. of Double Entro steels. alloy segels, and non-ferrows rnetals.
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AUTHOA D A f 8 CEE O S V Daft CMCD 9' O * 's 40 DATE t'
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ThE DRAWINGS-FOUND HERE WILL BE XEPT ON THE SHELF IN THE CENTRAL fit.E.
THEY ARE AS LISTED SF. LOW:
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't.o fallowing infers 4tien to required to complete tu stylar incorporation of is-69 tit retvirementi ser 114.
A) tabed Plate Infersation
- 8) taistint less Nueer C) Locating dimension baby to partst attachment pelat Class 1 Connection Point Ofeenstent (Seta11 Selow) 9)
() $nebber / Strut Reconciliation itsper+, Jacomplete F) ideld list / Luetion
- 4) Orientation of Drawing flot Shown i
p)- Olsension Not Providef (Attsch Drawing If necessary)
ACTUAL Ltn83 O!MtASION PE00 FRED
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Wald length informatio's for RFI on ANFil was not uo64 in calculation. No further sction except to notify C. W. Gay, or lIO on ANPAK Od O L.6oq S.
- deld length intormstion for RFI (Isometrica 2A 4. mi o14.r43 was used in calculation.
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$UBJECTi ANALYTICAL PACKAGES FOR 1001 AS-90!LT RECONCILIAT10M PHA5F. I Please be advised that Analytical Package EE-M-G04 is-_ being submitted for the 100% As-Built Reconciliation Program.
This packagt, scope has been verified to the scoping sheet
-l transmitted par letter VF0V MI dated l~l4*B7 The applicable as-built drwing revisions and exceptions are identified on the ati. ached.. marked up scoping sheet.
As-Built revisions - identified on the scoping sheet that are different than the revisions identified on the Deadicad Verification Record do not affect deadicad gaps.
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C40up45) ...... StAIUS/CDest(NJ$ ...s...' BOON, 4 ...e......................................e.+...........................................s.............................u......... OR-PP*s72tS-98 . Vu2 TAG:4201-021-02 D E:2N4 8201-028-02/2 ENG 03/20/s; 06/13/es 04/29/a7 8802 WALVE 2-120s-04-136 OPEaaica Otste4 TAT:C+# CO** GM1 C PPIP P/L: f/O' 24AC DeplO BE SOu!H. ACiuat IM FIELD IS 82 OP*2 Caf-t seL5 s #4: 4. 0 ' OES$ 10wA*eD NGRtH I ROtt E ASI *wE51 Ct. (90 GC Psi!. EE5: RES O!E: DEG1 NG'tf H OF 2* PI PE CL. ON trE S* SI DE ) O f s. ......-..............>.-.s WLv COULDN BE INSTALLED AS-DE51CMD RESP JP: Lasf C PAV-IT: CO: +
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OR-fil tS427 88 wu2 TAG:2-1202-Oa-534 Dic. : 2M4 - 1201 -023 -02, ENG 10/10/e6 02/t7/87. 84sC2 WALVE s2-1201-G4-134 L IM AR INDICAY50NS CON CssEC PPIP' P/L: f/O > t/tS* DISC TEST' Di;S q . gp g.gy.y,OWf 9f D Otaelm P(M TUNT 24 3, OC 1 (AT-t set $1N ; 33 P21: RES: RES Off, -Orn J Et $P GRP: Gst C pay ,7; Co QA-PP-tin 982 5SO2 s'd2 icG uc,2x4 820s-024-02 Em is/25/mae 02/17/$7-r S'50 2 L INEife. INDICATION DISCOVERED IN VALVE CON CMtC PPIP P/L; f/O 23 bOOV APPROAlmATELY - levCtt AN LENG% DP5 Caf-t sent N nO 00 Oc PRI. RES: RES Ofi-OTH ki SP 6W. GMEC PAV. 17 CO: ..~...a....-...... .......... -. ~.............., De PP-3474-E3 vu2 3 AG 2 - 1;tte s 128 DwG.2h4-12G5-025-08 I E f e-3 P 10/10/86 02fM/87 8802 3 / th - LINE-R SPOICAt !ON Dl5COVEDED IN CDN 6aet ; ? PIP P/L-T/O 24 VALV( 82-1209-04-125. OPL r 'l UC CAE-t seL$ f N. DO OTH PRI: Ri$: Rt$ DTE-Rt *;,P GEP - GMEC Pak. Ii 00: Oft -PP - 16447-88 vis2 IAG' 04,G:2M4-1201-027-01 (E FPIP 10/13/8( 03/02/67 S402 IsutiIPLE LlaeEAR 1aDICA!!ON$ IOUND IN CON (JeLC PP2P P/L;'t/O f 24 vetvE IPOf. 095 GC CAT.s seL5f M - a-C DIP Rg $P CP " GM( C 1" A V : II' CO: ( PRI: aES: RES OTE: L ....................... -....... - - - - ~.... -... - -.. - - -. - - -. -.... - - - -. - -. - - - - - - - ---' ---- ------- - --- -- -- -.---.----- 03 89 37000-sen vu2 TAG: DW6.2W4-1236-017-06 fM 01/27/87 O2/23/97. 8802 3 LehtAR INDICAT!*]NS IN VALVE FOuND 'CDN Gk.EC LPl# .i/L: 1/0 E OPS 24 OuRING. T OC LIH I CAD: amLSTN 00 Pe!. RES: als Of*: ut*.9 GRP SMLC PAV. I1: C._. t/13/96 C3/2ts/s7 De PP.ter656-88 vu2 IAG.2-1204-U4-t19 C*sG 2d4 - 1201 028 -0 6 1NG P/L, 1/0 DR-PP 11i666-88 8803 DuetNG d!SA5MseDie' Of VAiWE M R CWQ M-CON GastC PPIP i Rio eCJeaO2318 OPS Cwe-2870904-84 24 3:37.inkfa05 DAatAGED, F QC CAT a sELSTN O'A OTH PRl RLS RtS DEE Pi$P GRP-LaaE C Pay 2s.xntA -f CO: s I .I l l, i w r ua s-a ' s i
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' KA5flR.IRw o!NG SYSTET$ _*.. pA{[; 07/22/gy , agg.' g3 [ WOGTLE E L E C T R I C GE Nii s# A T I NG PL ANT ggut; 23 2e ggpy u q, ALL Cm(C DE-54. -... l .a........ I f f et NueIBE R 'UN87 F ORf (. 3 57 ORIGINAlf EEG O CPI' COMPtEsE Atax. l if M e 508575' PE5PCNSIBatIlf DATE DA.E DAiE Aux. t if te 2 StDG'
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GROuPi5) STAiuS/CC.e6LNIS *....*. ROOtt 't ...................................*..........*+.+...+.......+..................>......4.**...................................... L CC PP-16922 88 VU2 I AG. 2-1204 -tJ4 E*9 DwG 254-12Cl*021-Ot ENG 8802 YM4f AD5 DN 8MMI Of VALVE DamAGio DuZ COs GM(C PPIP T/C 24 TO EACE551vE PEseETRATION ON TACM wfLDS. 095 CAY-1 seLST N: 00-gc 'PRI: Rf5: Rf5 Oft; ogg RLSP GRP: OsE C pAv CO.- 04 FP-17034-88 Vu2 TAG: Dvs.2*4-120s-02s-os fuG onjo./s7 DR-PP-e6454-88 8802 IHRE A05 DAasAGEO ON 80eetti VALVE 2-120b CON GastC p ~ ' 23 U4-069 DURestNG REseOVAL DUE TO EACESSIVE GPS REO sGauu23'3 CAI-1 80L,i t N : 00 PENE;2ATION ON VACr: wfLDS. F PA1: RE5: RES DIE: egH s GE 9 GRS; Gae(C pav:2.OO2C5 if-CD-h [ 02-P6 t?307-Se vu2 TAG-2-$201-u4-069 04G:2K4-1201-028-01/2 ENG v3/ 26/e-2 C4/o2/a7 i 88W THRE AD5 OAseAGED ON EONNE T OF VLV 2-1201-CO*8 GMt C PMP p/t-Tjo 24 . -u4 - Oe9 OUR I NG RE seOV A L DOL 10 fACESSIVE OPS CAT-1 enLSIN 6 0 Pf Ni T R A T IGH ON T ACK ir(LDS. TH15 DR SuP-OC { PRI: RE5-Rt$ OsE: tRCEDES DR-17038. OtH WESP GRP GastC PAW. 11 CD I OR-Pi*-t73Ga 88 vu2 14G.2-1201-04-5t9 DwG.254-1201-02t Ot/2 ENG 03/.6/87 04/02/87 'l 8802 DuRING D15A55Ete6LV Of VALVE Pf st Cee as-wm Gast C PPIP p/t: ;fo 24AA 3:37 THREADS DAMAGED DOE 10 EACE55 OPS i l CAi-t asL S I N, 45. 0 PipeEIRATION 08e TACM trt LDS. INRE ADS DAas4 - OC PRI: REi: RES SIE-GEO 06: 800eeET GNLV. THIS DD SUPERCtCES DIH - i 09-86656. RESP GRP GMEC PAv: li: CO: ( ..........................~....-....-...--...---- --- --.-- -*----------- -- -----.----- - ---*---- -- - - - - -----~~---- De - PP - ! 7 h 3-88 Vu2 IAG:2*t2Ol*u4-123 DwG:2d4*i201-028-Ol/2 ENG 04/02/s7 09/:40/37 04/29/87 f 8802 VALVES 2-120s-ud-t7-) & 127 ARE ROtLE83 CON GMCC PPIP F/L: I/O' 24A8 Out OF DE51GN 87 22 DEGS. 095 i OC -[ CAT.4 alL STN : 5. C. GM [ Pfl: AE5: RES OTE: RESP GRP: GesEC
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gg.pp.g7440-56 vu2 TAG:028 w-tOs DwG:2x4-620s-028-ut/2 (NG O*a/13/ 8 7 80/30/87 ggc2-3) 2-5/103 PIPING 15 5CRIBED ni s(6597s. CON GPIP FPiP OS/O t/8 N P/L' R/T 24 HEAT NuseBER 15 ACCEPTAl?LE 102 CtA55 2 OPS H! NO CN PIM CAi-t' setSIN 5 0 00 IN Att CASES, & FOR cia 55 t IF RfC*D OC sel' RES-RES 0?g A5 I)Ese a4 ON PAV 5010 P1 PING 15 GTH -l MCO CtBE 5CRsSED w!TH I T(g gy RESP GRP. GasE C HAVE5 PAV. I1. CO: [ -- ---~~--- T--^-
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gg y iAG. nt4G.2M4-$20sy29 0t I f=G ? ?/ ts/888 J/2 6 i _,.............. ~....... 8802 $PGOL 029 S 10 WAS Sut* Pal [G WITH s e. 5/ CW GMIC PP!P l 24 160 ( UR. A 1 ?/4" 6000 e SO(.WOt f i wl !H OPS .l CAI-1 pat SIN 00 f 17/32-SHL%nD Bf E-5/e60 HDR s t-OC i Pal af5 Pf5 DIE 6000, wito raO DRitt a GCP. GM C eav. il CD-l l l l t L
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.s. p V-SAMU ME /ld b l_ / i kra y.SAMU Piping Analysis m (404) 554-7711 Ext.1553 um s t.lg. gS %.a Transmittal of 79-14 As,8y11t Reconciliation Package u a.r s u-nts e. ) -4,A Bishop PC#7/P: C r,Ti,,4't_ la cc: D.A. Barttd. PCf2* 3.V. W W 4 V-SAMu* p 5. Ag g y,v.549 i A.J. Ayoob, V-SAMU* M.G. Ball. V-SAMU* R.B. Patei. V-S J.A. Torterice. SVC* B.H.SPAW V-SA P.G. Smith, STC., E+2 '. ; M.W. Barlow, V-SAMU* H. Golshir, V-SAMU* R.E. Kelly, PC,/2* gggy.g Attached is analytical package _, E$- C'L ~1\\D Tnescheduledpipinganalysisreconciliationdateis The scheduled support reconcihation date is p.AI, P S. Sandhu V-SAMU Piping Analysis
- Cover' sheet on'iy PSS/res A
Westinghou:,e h ' Author Date Checked by } MN lt-it4f Hp (A L ii. i t'. e g Note: The scoping f s not to be changed without approval of the V-SAMU 95AB grou,' " ~ 1. In-Scope Isem tric Rev i of $p Calc no. DCN's &/or FCR *: K a ts-NR \\ \\c A _n__ _o t - O't V-ob \\O 1tr 8 8 DC4*l -4 ( - o M ol io IO sx.u u l g 'c, 4- - M - o l. _ 11 15 _E - t S_ - _ m. g@g NOV201985 II ..- a b"" TOTAL. SUPPORTS, Al PifbiG DE5fC4 i. 2)I'~i'. 4 C,a.e s cu c t.. wr A cu.c u te n.
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P '0 ' W Computer rnodel is not availt::e ,_,, ~J m A us.y.,W 5. In-Scope stress calculations and associated croficht are attached l unless no',.ed: S'Trce:CC cAc4 s. stoT M2/ C-es D. (R4T_ A t/A WA-B tb 64 St-{c ), I' 5. The V-SAhu Open Items log and the design ass stions of the stress cale's have been reviewed -and all open items'have bon resolved or sufficiept information is included for resolution by the ]ffsite group. / Yes 7, Re feree".e s : -A. Piping Design S;:ecification X4P\\1oi R e v. ~.L__. B. C. 'l u g o. AV A u-A e> L E @ Pc u y Qs.;gg, 8, 'et Impingement t.caos b Yes No L ads At. tac".ed Yes agv egy '"O* Javt 0 as o av c r. t s q% D, %0
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'fes ' Yes YES a.) Controlled Copy Of The Walkdown Isometric / / / b.) Suoport Swmary Table Mo Mt _%
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4 7 ' WESTINGHOUSE Pl. ANT ENGINEERING DIVISION ' VITLE- ' PA04 YhlVE-ILYNTIFICATICN SHEET ICR ISO NJMBER lk4-iM o&on i o, t P ROJtM AufNOR Daft Ca n*0, a v M 6sn'D.wf oAfg [ r m,,d.,w7 3 s 1 -- N. [j e,,,,.Fa vel IN q s 5 - e 3 p. CALC.he. PILS NO. QAC49 4,/ ( A plQ .e = l 1 i VEVE IICEIFIER VEVE IDE!EITIIR A_ C D - -- l27'. - I VALVE VDECR. VAI.Vt; VENDOR F,-r w am w :cW f w O : * & ^) s y VEVE TM IUBER VEVE TM !OBER l.
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v 0 l S A 2,330 Generation Technology Systems Division fer Structural Analysis I 236-6302 Octaher G l986 i t.m 1004 FINAA DESIGN VERITICATIO!! RECONCILIATION CLASS I SST TRANSMITTAL t to R. B. Patel - R&D - 701
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__ ~. MPI H%7 E Ceorgiahr u. ~,,,,-. m. IN8TRUCT!0M8 f06 COMPL6' TING 78!8 FORMi comelate all,1hkQtly (,QJack ink. Nga.atch u-a gggggly in the upper : sht ILand corner. DAff Ninet/Mt>[ AM NUMBER OF FACES AT7AciiD - I h Mbi/ TRLECOPY TO: k.k h00$$$f U4$/ (Naine) (Companyl (City 620$Je) 1ALICCPY TROMi WM Dr $ rtt( 73C0 (Name) (Dept /Coiiany) {txT) SPECIAL INSTRUCTICt;Ee O /U (L) MLd[/N'dt# 'J Do YOU WI5H TO RITAIN THIS COPYf [ (CSepleted telecopy will be i yes ptsced in tray for pick up) (Completed telecopy will be deatmyed after transritting) no ~ Tor Telecopy operator vae M iy: ~ l TEI.ECOPY TR.ANSMITTED: DATE /0 4 % 7IMt_,# dP&f,,, OFr.t.A N R N h k V _.m, TAON: CR0ACIA P0hth COMPANY - Vogtle tiectric Canerating Plant Telecopy Equ1 aents F Dex 4100 (t.04) 554-2936 Omitax G96 (404) 554-7680 Verify Numberst (404) 724-1257 Ext 7471 or 7405 l -l404) $34-7711 Ext 74'.1 e 7475 Tie Linet 8-317
- 7471 or 7405 Supervisor:
R. L. Roberts l l l l~
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^ E(CillC 4 CU48 :) SWPORT RfCWCILA1'10N TMelN!TTIL $Upport Tag Einber,y1),2,_.p,,j,,,,!*h M00 d. 8vilding @'f !senetr(c Drawing,)ka-12SI. Hu) 0L Ares / level lib / lwd 6 mene4 m Mode Musber 270 Requested $y E ClPAlhall (SL Signature NMJ $hown below for piping approval are the as castr]ned support stiffnessen. If the dtstgn loads c.herege t' rom those indicated beln.please complett the table at the bettes of the pegs, .C,,ggpOHENT Q},T, N Of5IGN$71FFNE$5Ej,, DESJfM0ADt Kx - lb/in rx e,_ Ktps Gro2 4 :3'lbdWF Kici Ky a 2/71x.lO lb/in Fy *_ ggg 3, gy, K2
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- 31pt Plette supply the pipe deflections in the tab?e below.
l =' 53(08f) S AMI!.H ; CH l C}7$_ O(30 'JilGWT DI D Al. 'Of $55 l i j \\ l Cy( K!')l l r ico); z o b.A =, _= O I =~ O2 4 CCMHENT$ - = -.- - - - ^ ' 5244__ 3, h, g l ,. ~
G150.YF0r. $if t/ f 8e V.Sasu Piping Systees As.Bullt (404)1.C'3554 7711 Ext. 7255 .w Leen TRANSMITTAL OF FINAL DE$1GH VERIFICATION AS.80lLT RECONCILIATION PACKAGE (,,,,__75% f_1001) N.5 sys. J7 C) f. @. ff1 7 f l., $ $ D 70I T rM r-A r' ass r R AC-701/ A rW r-Ma ntr$f (C-Te .s, s t.t. 1.. V. Suu cc : M. Pandya. V.343u* 8.Baughman, Y.Samu4 D. Weathers. V.$aW
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l Attached is analytical package 8 -~~T75 5His antion for IInal Design Reconc114 Tic /NNL 21C, and associated infor. i. H-i/.-+-( hebbchifationShi$k kS[kM(Cias$k ...........................................Cis h/h ) Westinghouse / Bechtel Author: Date Checked by: Date: Ls sa v TT Se ~~~ ............................9..,..g.,g, .............7../......4 ej,c. Note: The scoping is not to be changed without approval of the Y.Saso PSAs Group. 1. in. Scope isometric
- Rev, f of Sp.
Calc No. DCN's A/or FCR's \\ Yu. v ! GL@ n__., ? g . ? 2,$. 0 ) 1l l )) rtI r *] ~ v \\fjO._L 11 1; TOTAL. SUPPORT 3 JI V. 2. Overlap Isometric Rev. DCA's &/or FCR's !, A4y3,,; i I tvJ a sg>'r { ~ (Con'tPage2) /d)'Th E.Abuah
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~.- - - - -.-..-.. - - - -.. _ t'CSTINGH00$E PLANT ENGINEERING DIYltl0N s - +.. A/$ PACKAGC N **O2 EIO 2 3 .. o,. c, mus-mr mv., wrt o. c.tr VDSTLE 7 <f/s fs4 /,.'/.f 5 so a n c %c,, Mt so pove - ~ ~ ~ X 4C - V-5ANJ
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Rev. DCN's 8/or FCR's l 3 3. Pal 0's Rev. FCR & DCN L ~ 1X408 IIf-14 _ ' P C d # 3 2--- 3 ^ 1X4DB lI.*> 16 . 7" /j :: p. /c. r n,' / / 77 7 lX4DB 8 4. ME105/ME101 Computer model transmitted to username p ij/t-- P C0mputer model is not available v 5. In-Scope stress calculations and associated microfiche are attached unless notad: --r -( r r O.-.r , :,, r m \\s
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,/ ' ',~ 7') z t -. n.. 6. The V SAMO Oper, items log and the design assumptions of the stress cale's have been reviewed and all open items have been esolved or sufficient informatten is included for resolution by the offsite group, t/ Ye t, . < e,) ; s c 7. Piping Design'5pec X4P--/WI Rev. 3 X4P-Rey. 8. Notes t i t N a t [ 't P i ,g, ,gy A v i se O R Oatt Cnt s av 04 tt C M L 0 41 '*'tj NO 04tt i nt nti%c,movst somu 661130 I J -,.,,,,,,--,_,,5y..n.,,,,,.., ,.,--m,,-,. . - -, -.. ~ .g..._. -,e- .....,-m.., .me~~.,y ...,.-.-,,,-....--m-.m..~..-.-m..- -. - ~..
WESTINGHOUSE PLANT ENGINEERING DIVISION M-be 210 gfg p gggt ..o m .vi-ou e.n c. o.. 3.w o...v- ,- 3 3 vosTLt Tr,.thL 4 ?4F m so c.sc ~o 45 so o.ov. xac - ___1-sam 9. Penetration Seal Information: Type / k'all/ Sin Isometric / Penet.No,/ Arch. Pen. Seal St re Floor Thick. Detail No. Line No. Drawing No./Rev. No. ,, ht,[ -/ / .-. - J / __/ / / / ./ / ,__7.,_- / / / / / __ / -l _/ ~ /._ - / / / _._ SNJ2 (a) of piping. disp. 9 the penetrdtion attached. 10, 9 SAMU walkdown package containing the following: 'i Yes Yofies Yes Yes; a.) Controlled Copy of the Walkdown Isometric / W b.) Aperturt Cards of Redline c t c.)SupportSummaryTable -a d,) Supp' ort Summary"Xey Plans ~ ~ s e.) Welded Attachment Drawings (copy if applicable) Jr =; f.) Input for response spectra selection No 4 ~ g.) Vane Identification Sheets rh .. a h.) 100% Orawing Rev. Work Sheet u v 1.)75%Punchlist V v v
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CLASS OE. SIGH t%!iUAL I DC-109.)_ DC-1007 4 ' - ~ DC-1017 r-PIPIll0 DESIGli SPECS X4f '",*1 3 X4 P- ~"" PUT ISOMETR.ICS ~~~ seu->:. . ~., e m w ~. +, r. r. f ~~ _~ s ' '.. e 7,,,_ ff I S S 4 ) 6 f
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t Forrn $46a28 Section Descrioriens insex Added Section 3.2.3 1.1 In footnots (.1) adced 45uE 1930 Code Reference Giving s!Fs. 1.1.3.1 In footnett (1) removed reference to " Thermal Sleeves" (Same a::'ies for entire document) I'.l.5.1.7 Deleted E Responsibility for jet impingement leads cafinition an: ther structural evaluation. 1.1. 5.1. 7 Tabic 1.1.5.1.7-1; acced piping systems indentified to W 5:::e including their non-class 1 entensions. Table 1.1.5.1.7-2: changed responsiblity for jet load determo ui:n t: jet target identification from f tu Daner as indicated. A::e: footnote (5) 2.1 Added references Sections 2.1.16 thru 2.1.20 incl. P 2.1.1.2 Revision updated 2.1,1,0 Revisions updated 2.1.12 Revision and drawing number updated 2.2 Addad Reference Sections 2.2.8 thru 2.2.13 3.2.3 Sections added by break-down of existing text, added referen:e : :. - System 3.3.3.1 Added 3.3,4.2 Text change to as shown 3.3.4.5 text added 3.4.1.3 Deleted 3.5.2.1 Table 3.5.2.1-1, t. cad combination table revised and updated is: N: ; Table of notes wherein Note 4 was deleted and notas 9-14 incl. -ere I added. "Ger. oral Nots' was added. lible 3.5.2.1.1-1 and asscelated Notes /0efinitions eng.anded as: a::s:e:. Tabie 3.5.2.1.1-2 and arsociated notes definitions ahd 3.5.3.2 Test added as shown 3.5.3.2.6 Added text to definiticns of o g 3.5.3.3 Changed text te as shown 4, . m._ v u 955211 Page 3 of 52 Pages Date 9/25/88 Revision No. 4 c -- Stee#te Sims '$ obt90s
m v gW1 CATION DETAILS 1 "8'
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DETAIL DESCRIPT!ON OF CliANG!S IN_ REVISION 3 Note: Not identified in change descriptions art, correctiwns of ty;os or minor editorial changes / clarifications. -2.1.22 This Section added 3.1.2 Data solaced by reference to Radiation Analyils manual. Ref. Section 2.1.23, 3.1.3 Data Rectaced by Reference to Water Chemistry Specificatien, Ref. Sec tion 2.1.21. Table 3.5.3.6.1-1 Footnote (3); rewritten to clarify structural evaluation criteria for valves associated with favited loop of RCS. 3 Front Page Added to Equipment Des:ription:...c.nd Apr opriate Non Class 1 -Ixtensions. 3 DETAIL DESCRIP't!ON OF CHANGES IN REVISION 4 o Delete redundant 3rd paragraph of Section 1.1. o Add (PSAP.V) to 3rd paragraph in Section 1.1.2.1.2. o Revise Westinghouse mailing address in Section 2.0. o Add Section 3.4.1.3. o Add note (1) to Tables 5.1.1-1 and 5.2.1-1 and delet Revision nue.ters. o Delete " ascertained" from note in Table 5.5.1-1 and ado "cetermined". s e Revise Tabis 5.5.1 1 to add correct S.G. General arrangeeent and ACP Outline drawings, o Front Page - Added PSAR to system description. o-Added letter # GP-12305 dated 6/12/86 to Sectico 2.1.24. o Corrected /added valve 10's and or valve location for exuss l uccan, reactor vessel vent system, and AVLIS lines in Tables 3.5.3.6.1-1, anc 5.5.2-1. o Aeded last sentence in Section 5.3.1. o Revised first sentence of Section 5.5.2. o mu,, 955211 Page 5 of 62 Pages Date 9/25/88 Revision No. 4,, _ - -_ n -- - - - .a.-.__. ein. s r_-- ______________1_______________._________._
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i5 ON gtFICATION DETtJLt '( !NDEX. - 1.C G M RAL 1.1 Stopi 1.1.1 Project Applicability 1,1.2 Equiement Governed by this Specificatien and the Functicns cf the Equipment 1.1.3 Functions Governed by this Specification 1.1.4 Functions not Governed by this Specification 1.1.5 Responsibilitier, 1.2 Occu entation Recuirements i 2.0 - APPLICA!LE OOCUMENTS i. l 2.1 Referenced Westinghouse Docunents l-2.2 Additional Referenced Documents 3.0 Dis!GN REWIRDGNTS AND SARAWFTERS 3.1 Design Information 3.1.1 Design Life 3.1.2 Radioactivity 3.1,3 Water Chemistry 3 1.4 Weenanical Design L 3.1.5 Pipa Bencing L 3.1.6 Environmental Effects 3.2 Design Pressure. Design lemperature, and Desige Mechan se.a! Lea:s l 3.2.1 Design Pressure and Terocrature 3.2.2 Design Mechanical Leads 3.2.3 Other Machtnical I.oads j L 3.3 Operating Conditions 3.3.1 Nore41 Conditions 3 ).2 Upset Conditions 3.3.3 Faulted Conditiens -3.4 System Boundaries l 3.4.1 General 3.4,2 Interfeca Inforsation 3.4.3 Equipment Characteristics 3.5 Design 8 anis 3.5.1 General 3.5.2 -Loading Combinations and Stress Limits E 3.5.3 Analysis Axuirements L 3.5.4 Mditional Requirements L rwrenewau 95S211-Page 7 of 62 Pages Date 9/25/88 Revision No. 4, _v. ~ _ _ _ e* 31erp is UMe te-ettet s
-y .gg omo Lr 1.0 G,15 R Al. - l E This specifigion is applicable only for functions within Westinghouse ' score as identified in Se: tion 1.1.3. The general design, analysis, and interface requirements providec b lc this specification are based on this pre:aise and, theref ore. l this specification shall not be used for other than its sntenced purcose. Any conflict between this soecification and the referenced cocuments herein ca;'ed for shall be brought to the attention n' W for clarification price to any action by the designer or analyst. This specification and the docuunts referenced herein fulfill the requirements of the 0$ sign Specification as required by Section hCA-3250 of the Code for the equipment identified in Section ).1.2 and for the functions specified in $ection 1.1.3. 1.1-Sc.op,a This specification establishes the design by analysis recuirements for MS Safety Class 1 (Class 1) extensions pipin; sys t etts. This equipment snall be designed ag) analyzed in This ecais-accordancs with the rooairements of the Code ment will becou an intsgral part of the nuclear steam supply tjstem of an electric generating station. The integrity and relistility of the equipment are, therefore, of prime imperta :e. The Westinghouse piping des #gner and analyst shall be responsible for compliance with all of the cetalled requirere* s presented in this 10ecification. There shall be no deviatie' frem inis spec 4fication or 'its referenced documents without prior written approval from W. III For purposes of this specification %'estinghouse' or,0l[) refers to Westinghouse Electric Corporation. unless noted otherwise. (2) The term ' Code" as used in this specification refers to Section III of the ASME loller and Pressure Vessel Code. L 'N' $tasping Certification of the components within the Westinghouse scope of responsibility is to be conducted to the requirements of ASuE L Sectfon D!,.1977 Edition including Moends through Winter 1977 Piping ani.btis, Jor. systems within the Westinghouse scope of responsibility, is to 'Je conducted to the 1977 Edition including l Acd6nda through Winter 1977, in addition, the Sumner 1979 Adcenda is pernitted for use it. the Class 1 piping stress analysis. For Non-Cien 1 sitensions, stress intencity f actors (51F) per the 1980 'l Edition of the code may be usad. Ref. Section 2.2.10. rm ererwrue 955211 Page 9 of 62 Pagat Date 9/25/88 Revision No. 4 W - l h%$ h
CG SiG4 CGECIFICATiON Of" AILS.
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pq Form 54428 1.1.2.1.2 The RCS pressure is controlled with the aid of a pressurizer in which liquid and vapor are maintained in equilibrium of electrical h&sters afd fluid spray. The ClasJ l piping cor.necting the pressurizer to the reactor coolant locos contists of a pressurizer surge 1994 whica joins the not leg with the pressuri2ar and two pressurizer sprey lines which run from two different cold legs to the pressurizer (see Appenois B). The two spray lines are joined hofore retchirg the possurizer. To reduce the pressure in the RCS, fluid casses thrcugn ve spray lines and crndenses the steAn in the pressurize *. ine R:5 presaure is increased oy using the ele:trical heaters 1: nea the fluic in the pressurizar. for protection against over pressurization in the RCS. theew spring loaded saf at,y valves and two power operated relief valves, connected to the top of the p*esstrizer, discharge :: the press;.rizar relief tank where the steam is condenseo anG l c nled by mixing with water. The piping connecting tne pressurizer to the cressurize* relief tank consists of the l orassurizar safety and relief valve (PSARV) lines. The Class 1 L portions of these lines and the non-Class 1 extensions are sncan in the flow diagrams of Appendix B. t l The safety grade cold shutdown system is designed to enable the l Vogtle nuclear steam supply system to be taksn from not 4 tan:oy to cold shutdown conditions using only safety grade systems. This condition may be obtained with or without the availaoility j of off-site pcwer and a single failure may be postulated. The basic function.of the Reactor Vessel Head Vent Systr i (RVMVS) is to remove non-condantable cases er steam fr a the l reactor vessel and head which may impair emergency ccrr sco'ing and natural circulation cooling. Also, this system is osec :: provide a safety grade letdown path for the cold shutdown syste2. Operation of this system is conducted via remete reanual .operstion from the control room. The Reactor Vessel Level Instroentation System (RVLIS) is designed to provide a relatively siinole means to monitor tha water level in the reactor vessel. This system provides additional information to the operator during accident conditions; however, it dcJs not replace any asisting system. L 1.1.2,1.3 The resistaneo temperatura detector (RTO) manifcid bypass loc) is used to monitor the temperature of the fluid in each of the het and cold legs of the RCL. For each het leg manifold the fluid enters via three scoops in the hot leg flows through the manifold where the temperature is detereined, and esturns to the loop at the crossover leg. The fluid for each cold leg manifelo comes from one connection in each cold leg. The fluid flows from the sanifold to the same return uced for the hot leg 955211 Page 11 of 52 Pages Date 9/25/83 Revision No. a w gicm ic 91Db,16-elNeH j
- DE51GN $0ECiFICATION DE~.'tJts
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Form 54642B 1.1.3.1 De.sj gn II) RCL pipi g RCL fittings , pressuriger spray line temocratsre elemnnt, pressuri er surge line t n: fittings ( thermowells, and P.TD bypass manifold (including associatec fittings). 1.1.3.2 Wamuf acture, inspection, testing, documentation, packaging, anc sniement of oiping subassemblies ano fittings _, RCLpiping,RCLfittings,pressurizarsurgelinepioingand fittings, pressurizar spray line If themonells, and R <D typess manifold (including associated fittings). L.1. 3. 3 Analysis Class 1 piping and fittings in W scope of analysis as cefine: in Section 1.1.0 af this specification. 1.1.4 Functions riot Governed by This ".,oseification, The following functions are s scifically not gevornec ey this specification for the equipment designated: 1.1.4.1 Design Class 1 piping and fittings not forming a part of the como: e-ts casignated in Section 1.1.3.1. -1.1.4.2 Nanufacture, inspection, testing, documentation, packaging, a : shioment of piping subassemblies and fittings Class 1 piping and fittings not forming a part of the comoore-ts designate:1 in Section 1.1.3.2. 1.1.4,3 Installation, inspectium testing, and documentation of piping subassemblies 2nd fittigs at the P' Ant Sits All Class 1 piping anct fittings 1.1.4.4 Analysi s Class 1 piping and fittings not in W scope of analysis definec in Section 1.1.3.3 of this specification, i ') inn feDittings' associated with the RCL fer purposes of this specification represents the albtss, the 45' lateral nonle fittings [ end tho RCL branch connections including nozzles. RTO scoco, samole L connection with ruep, spray accop, elbow tas.s. WJ temperature slew <t (TE) bosses and therenwells. l-(2) l The term " Fittings' assectated with the pressurizer surge line for l purposes of this specification represents the elbows, pipe bonds, and TE boss and thoracwell. 955211 Page 13 of 52 Paget Date 9/25/88 Revision No. 4, _. ~. _ u_ L o... ., w..
1pg g.,c a n,co m i -- .1.1.5.1,8 Verif ying the adequacy of the' primary equipment (RPV, SG RCP. pressuelzer) for rawulting loacs n" this equipment from the piping analysis governed by this specif4 cation. 1.1.5.1.0 Verifying-the structural adecuacy of the primary ec ineemt sucports and RCt. piping restraints designed by W for resui 4; ' loads on these supports / restraints from the piping analysis governed by this specification. 1.1.5.1.10 Caveloping and providing to the Owner all inferreat'en, as :aac Nt 10 be provided by W in this specificatier, for use in tre Danet c: ope of responsibilities. 1.1.5.1.11 Preparing stress reports and obtaining certification. as required by NCA 3550 of the Code, documenting the analysis results of 1.1.5.1.6 and 1.1.5.1.7 for the defined Class 1 piping and subjecting these stress reports to revie= as ren~ec by Appendix 0 of 10CrR50. 1.1.5.1.12 Acting as the Owner's agent to enview an:A to certify this re.de-of the stress reports called out in 1.1.5.1.11. as recuirec :f NCA-3250 of the Code, to determine that they have satisfiac tre requirements of this design specification. 111.5.2 The 0+ner is responsinle for: 1.1.5.2,1 Providing or causing to be provided to W for use or esfereue n in this specification tne information defined in Se:tions 1.1.5.2.1.1 through 1.1.5.2.1.12. 1.i.5.2.1.1 Ocerability/ structural integrity valva nozzle and icad anc acceleration limits for all Ownar suppliec salves interf actr; with the p> ping sjstama in y scope of analysis. 1.1.5.2.1.2 Drawin0 numbers for all O*ner supp?ied valves interf acing =i:a tne ciping systems in W scope of analysis. 1.1.5,2.1.3 Earthquete respense spectra for the various floor elevatten c' the containment sti uctures for both OBE and SSE. 1.1.5.2.1.4 Maximum displacements for the varioud flour elevations of the containment structures fer botn OBE and SSE. 1.1.5.2.2 Providing a copy of this specification, which has been cartifiec by a registered Professional Engineer, to the onforcement authority having jurisdiction at the location of installation. 1.1.5.2.3 Providing er causing to be provided specifications governing the functions listed and the equipment designated in Section '.i../. y a e n., n, ~, 955211 Page 15 of 52 Pages Date 9/25/88 RevisionNo.i i om.,+ mu L I
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- 0ESIGN SEECIFICATION DETAILS e~
Farrn 546a23 m. TABLE 1.1.5.1.7-}, l W CLASS-1 PIP!NG SCOPE OF ANALYSIS S,vstem Leto Reactor Coolant System: 2 RCL Het, Cr ssove~, gnd Cold Legs 1, 2, 3, 4 Presssrizee Surge Line 4 Pressurizer Soray Lines 1, 4 RCL Drain Lines 1, 2. 3. 4 Pressurizer Relief Lines Pressar'ree Pressurizer Safety Lines Press rize-RVHYS, anc RVLIS Lines RCS RID Sypass Manifold and Associated Piping 1, 2, 3, 4 -1 Cnemical and Volume Centrol Systerr.: Ausiliary Pressurizer Spray (via pressurizar Pressori:e-sprsy line) E.xcess Letdo-n Line i Normal / Alternate Charging 1.ines 1, 4 Normal-Letdown Line-3 RCP Seal Water injection Lines 1, 2, 3, 4 ResiNal Hett Removal Systvm: RHR Suction
- Lines 1, 4 o
Sofety Injection System: Accumulator Lines 1, 2, 3. 4 3 Low head $15/R.w.R Return Lines to Cold Leg 1, 2, 3, e Bif Lines 1, 2. 3, a Migh Head SIS Lines to Cold Leg (via lon head 1, 2, 3, 4 SIS lines to cold teg) Low Mead 515 Long Term Arecirr.ulation/RMR Return 1, 4 3 Lines to Hct !.eg High Head $15 Long. Tere Recirculation Lines 2, 3 - (G lutas) to hot leg (4 lines via low head SIS losg ter.s recirculation hnes to hot leg and 2 lirts via the 1 hiph head SIS long term l recirculation line to het leg). 'FOOTNOTESi 1. The ausiliary lines listed in the Table include any other small Class : connections (nom. 00 < l'} attached to the Class 1 portion of the line '(e.g., test,. vent, drain TE bosses, TE thermowlls, etc.). The availia y lines identified also include the non-Class 1 extensions and piping attached to the Class 1 pipit.g.. 2. The fittings associated with this piping are the saue as those definec in i Section 1.1.3.1. i 3. These linas are also used as part of the residual heat runoval system. r.,.,~ me 955211 Page 1.1 of 62 Pases Date 9/25/88 Revision No. d. = l$Mk )h
gt4Gg,C#CAtloN D% TAILS 1 1 FLOTNOT[$ FOR TABLE 1.1.5.1J,-2 'l) V scope targets: RCL piping, primary acuipment (RPV, SG, RCP, 5ressurizer), primary ocuipment supports. RCL-piping ristreints, aec ClaLs 1 auxiliary piping within W scope of analysis as destgnatec in Table 1.1.5.1.7 1 of the plant design specification. 7) - To analyze for maximum ' jet loads on the-Re.L. a double-ended circumferet.tial break shall be assumed at the RCL branch nozzie/ auxiliary line weld joint.- -TAe broken end of-the auxiliary line sreil be assumed te displace laterally or.e outside diameter of _the auxiliary - 4 line. 3) inis' entry applies if the break-configuration is differvnt from tre once assumed in (1) and (2). a)- To analyze for maximum-jet forces on top and on side of the SG, double anded circumferential brJaks.shall be assumed to o: cur indepencent'ly at the main stesm line noz31e and feedwetar line net:'e weld joints. The broken end of the main steam line or feedwater ;i e stall be assumed to disp' ace lateraily one outside diameter of tne respective line. 51 Tasks identified for. corpletion by Owr.or may also be-performed by tne Onner's casignee. t
- vmv ww 955211-Page 19_of-62 Pages Date 9/25/88 Aavision No. 4 a,,
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g-a w .12 u u..- c~ - - - -.. - -..~ .u-, l gts4cgglFICATION OliTAILS g. wu w e....es w a-o,- 2.1.1.2 W Equipment SpecUication G-67B866,
- Reactor Coolant Seamless Forged Pipe' to Ask! !!! Class 1. Safety Class 1," hv. 2 aitn interim Revisions 1 and 2.
r 2.1.1.3 W Equipment Scecification G-678855,
- Reactor Coolant cast-Tittings, ASME !!!, Class 1. " Revision 2 including W Eauiceent Specification 679162
- Reactor Coolant Cast Fittings? ALME 111, Class.1 Safety Class 1 for Caerg's Power Company, Alvin W.
Vogtle Nuclear Station," Revision 2. 2.1.1.4 W Equipment Specification 3-678854 Revision 2 " Auxiliary Piping Mattrials - ASWE Section !!!," 2.1.2 W Control and E10ctries) Systems Standard, Section 2.33 ' General Use Thermcwell Stancard," Rey, O. 2.1.3 W Eauipment Specificatien G-67B833,
- RID Bypass Manifold,*
Rev. 3. 2.1.4 W System Standard.1.3.F. " Nuclear Steam Supply System Reacter Coolant System Design Transients for Standard Plants witn He:e1 F Steam Generators,' Revision 0, including Systems Stancarc 1.3.X, ' Nuclear W Steam Supply System Auxiliary Equipment Design Transients for all 5tandare Plants," Revisien 0, 2.1.5 W Topical Report WCAP-8172-4, " Pipe Breaks for the LOCA Inslysis of the Westinghouse Prirrery Coolant Loop," January 1975. 2.1.5 W 3yttom Standard Casign Criteria 1.19, " Criteria for Frotection Against Dynamic Effects Resulting from Pipe Rupte s, Rev. 1. August 1930. [ 2.' 7 W System Standard Design Criteria 1.2.1, " Criteria and Guidelines for the Design of Safety and Relief Valve Installations,* Revision 1. August 1977. 2.1.8 Crocby Dng. 70-00005, "Reccamended Nasimum Externally Appliec Forces and Moments Valve Closed (Forged Body Design)," Rev.1. .2.l.9 W Equipment Specification 953174, " Auxiliary Piping Materials - ISME Section Ill," Revision 1, 2.1.10 W Design Specification 955537.
- Pipe Fittings and Flanges ASNE IPVC Sectier,111," Revision 1,;89.1-84 (RVMV Piping) Code Class 1 Safety Class 1.
2.1.11 Westinghouse Drawing he. 167?E46, Revi:, ion 2. "Alvin W. Vogtle-Reactor Vessel Heat Vent Lina Piping Arrangement. 2.1.12 Wastinghouse Drawing No. 1686E64, Revision 4. " Reactor Vessel Level Ir.strumentation System Head Connection and Piping.' e ..,..w% 955211 Page 21 of 62 Pages Date 9/25/58 R.evision No. 4 e, eue-anu -
- 'Otsich $8td.FIC/cT'ON t.GTA1LS aw : c. H t.a : 't = * *: ec c Forrn 546428 -
2.2 Addi tierJ1 Referen:ed Documents 2.2.1 "N Stampi99 Cetification' is to be conducted by W for the reactor ecolant loop oiping _ including the = elds to tra crime y components (reactor vessel, steam geNrators, anc reacter coolant pum s) and tha branen H3e nozzles but not toe asics : the branch line mezzles of the ausiliary piping. Specific Y stancing responsibil'tiet are delirs.ated by the dre iag described in Section 2.2.4 The M stamping certificat :n is : be ccnheted to the ASME Code 19M Ecitien including N:eaca througn Wintt? 1977 For A suplied vahes, the a:rlicao'e Code Edition is 1971 inclu3ing Addenda ti.rcugh Sums 1972. addition, the Summer 1979 Addenda may ba usse for Class ; ::ic"; analysis. 2.2.2 NRC - 10CFR$0 Appencia B. "Qeality Assurance Criter's 4r Nuclear Power Plants and fuel Coprocessing Plants." 2.2.3 MSl/aNS-58.2.1980 "Prettetion ei Nuclear Poaer e ;ms Ags' st ripe Rupture." 2.2.4 Secntel drwing for A. W. Vogtle Nuclear Plant, " AS'/E I!! C::a Res;cnsibility Matrix," AX40n005 Revision 3. 2.2.5 Bechtel Saeeification No X4A201, " Plant Design anc :sstalisti:n Construction Specifiestion for the Secrgia Power Com:any, Aldn W. Vogtle Nuclear Plant, Burke County, Georgie - Units 1, 2. r: Commen." o Division P1, "G6taral Requirernents," Revision 11. o Division P3, "ASME Section !!! Pipi g field Fabricati:n a : Installation,' Acv W en 12. Division P9, "Pernis5 ble Consumable Materisis fer Use 4 o Ouring Construction," Revision 8, 2.2.6 Bechtel Specification No. X4A206, "Nucine Steam Su :I y s,* s t r-Installation Construction Specification fer the Georgia Poae-1 Company, Alvin W. Vegtle Nuclsar Plant, Burke County, GecTa - Units 1. 2, and Comon. " o Division N1, " General Requirementt,' Revision 2. 2,2.7 All drawings, letters, and attachments to letters, -nich tha Owner has respnsibility of providing. The lutest a: lica:le revisions of ths 'aferenced documntations are to be utilize.. 2.2.8 NRC-Letter by T. W. Nevak to 0. D. Foster Georgia Power C::. " Piping Design Criteria for Vogtle, Units 1 & 2, 3-18-86. 00:se:
- 50-424/426. Authorizes use of N-411 Dampino.
2.2.0 NRC-Letter by Elinor G. f ddene'un to D. 0. Foster Georgia Po.e ::.
- Rooutst for exemption free nesd to analyze large pricary lec:
pipe ruptures as the design basis for Vogtle Electric Geners'. g ) l Planti, Units 1 & 2 (title abbreviated),' 2/05/85. L 955211 Page 23 of 62 Pages Oste 9/25/88 T.swision No. i nn
Df 5tGM $PTCIF) CATION DETMLS wu =c-can ia-. c ::..e. e. Form 5464' 8 s v-i n 3.1.6.1 Neutron irreiistion for the piping is less thant la.C.t egr the 40 year plant life. 3.1.6,2 No additional thickross is required for corrosion /eresion of austenitic _ stainless stesi. am 3.1.6.3 The anbient tempersture for the system ist J during shutdo=3 a: can vary betweenE. Ja,c,r, during operation at an ancient pressure oft Ja.c.e 3.2 Design.*ressure, Dasion Temoe-ature, and Design Weenandcal L:s:s 3.2d Design Pressure and itecerature Detailed intermation on the design pressures anc temperatures ':+ all pertions of the ciping systems governed by this specificat*:- ts contained in the line_ lists prov'.ded in Appendix C. 3.2.2 Design Wechanical Lesds The design mechanical ionds, the effect of whien must be c:n:9e: with the design pressure effects for ccmparison with the criea9 stress intionsity limits 3t the design temperature are: Weight - Weight loads oue to live weight contisting Of the weight of the fluic contents and deadweight consisting of the weignt Of tha piping, insulati n, and other loads pt.=manently imposed c::- the piping during operating conditions. 3.2.3 Other Mechanical Leads 1 Oper uing Bast Earthauske (OBE) - Mechanical loads cause: ty t e inertia portion of the OBE, l Valve Thrusts (Presurizer Safety /Rslief Valva including RVHV va've piping systems).
- l. cads due to the opening of the pres-
-suritor safety or relief valvet or RYHV valves discharging ic:: seal water and steam through the valves, down the discharge ct:", . system, and into the pressuri2er relief tank. 3.3 Operating Coaditions The piping and fittings shall be designed and analyzed fer the temperature and pressore transients under the normal, upset, emergency, f aulted, and test conditions contained in W Systaas Standard 1.3.F (SSI.3.F) Reactor Coolsny System Cesign Transients and W Systen Standard 1.3.X (SS;.3.X) Auxiliary Equipment Design Trat1sients' as emended by Appendix D. In addition to these transients, the fol~ lowing shall be considered. 955211 Page 25 of 62 Pages Oate 9/25/88 Revision No. 4 l c ., w i. . w.-m== I
'0251G5 SPICt0 CATION DET-MS
- m u : u. m : m.. e :.
Form 540488 3.4 System Bounda*4es 3.4.1 G,e ee r a l 3.a.1.1 The :;undaries, including the ANS classift:ations, fer t
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ano fittings :f the Class i lines in or to the sys,ves ces:etto: in See:4 cn 1.1.2 are 1 0: ate: ser matically ;n the fle-ciag a s e ?"0. iced in 4::encis B. The selves and intermediate ::ene:; : s in t*e Class ! lines are also shcan schematically en the f1:a diagrams of 4 :en1ia B. Tne flon diagrams of a::encia 5 :: :: provide infc*mation certaining to bouncaries and ANS : 1 45 0 0:1-tions for in-line anchors and small vent and crain line ::a e:- tient provice: by the C%ner. This data, including cire sic s :' all piping and fittings governec by tnis 5:ecificati:n. is :: :e defined in the drhwings called out to be provice: Dy the responsiDie : ganizations in 3e tion 3.4.2. 3.4.1.2 Ea:h boundary is.: a, At the fir'; :ircu-f erential weld Of the ;rimary e; i er: t aczzle, tranen connection nortle, valve nozzle, se in-lire ancher; t*e connecting weld shall be censicered Da*t Of t~e
- iping,
- b. leactor :::lant lo:D Diping "N" stamcing certifi:ation 0:en*
caries in: luce the wolds to tne primary cornp:nents and tre branch line no221es but not tne = elds to the oraeth line ::- zies of the auxiliary piping. Souncaries for other s.,s s s within the Westinghouse sccce of N" state;ing res;oas': 9 are delinettsd by tne drawing described in Section 2.2.a. 3.4.'.3 U:en ::mpletion of the final design analysis the interfr.:e for:ss, moreents, or cisplacements at boundaries shall te documented in cosign calculation packages. The informatien #:- Unit #1 is in GTSD Central Tilm GAE/145/1A and in lettees GD-12492 dated 3/25/87 and GP-12453, dated 3/25/97. Tne information for Unit e2 is in GTSD Central File GAE/145/1 A a : in letters GP 13275 dated 2/2?/88, GP-13281 dated 2/24/S8, GP 13357 dsted 3/23/B8, GP13120 dated 12/19/87. GP-13500 cate: 5/4/B8 and GP 13530 dated 5/13//88. 3.4.2 Interf ace Information Certair, interface data, which is not necessary for initial f design of the piping governed by this specification, is re s're: to perform analyses for verifying the design of these oiping systema for all requirements of this document. In order to define eyecific boundaries and to consider the effecte of acjacent piping and support structures, the interf ace data saa include:
- a. specific dir.sansions of the piping and locations of coconents, supports, and connections 955211 Page 27 of 62 Pages Date 9/25/88 Revision No. !
i _ - -. -.. - = e..,,., m + m.
i 4 OtSION SMCIFtCATION DOAR$ M8**4 0.5s su r e< m e%. Foem 546423' '3.4.2.1.5 Confirmation that the information called out to be providec i- - Sections 3.4.2.1.1 through -3.4.2.1.4 reflects the as f abricatec/ as installed configuration, as applicable, or provice the corresponding significant differences e,r the corresponding actual-as*f abricated/as-installed data for the informasion I called out to be providec la these sectiens. p l' 3.4.2.7 The Deer is responsible for providing or cavMng to be prov d es : to i piping stress aralysts: 3.4.2.2.1 Certified-for construction /tertified for analysis layout drawings of the RCL and pressurizer surgs line inclucing the following information: i
- a. location and type of all shop and field welds including tre location of the RCL closure weld.
- b. piping insulation weight information,
- c. location, type, directionality, ant' spring rate / stiffness matrix information for all supports (spring hangers, restraints, snubbers, etc.) on the pressurizer surge line.
If any of these supports are integrally attached to the piping, the associated strasc indices must also be provicec. 3,4.?.2.2 Certified for-constructien/Cortified for-analysis isometric crawings of all piping systems in W scope-of analysis other than the RCL and pressurizer surge line. Small liees attac e: to these piping systems not within d scope shall also be included. The following informatio3 shall be proviced with e draaings:
- a. locatien, +.ype, directionality, and spring rate / stiffness matrix information for all supports (spring hangers, restraints, snubbers,etc.)
- b. location and type of all s5ep and field welds
- c. size, schedule, material, and insulation weights for all 4
piping and fittings
- d. location and details of appurtenances and integrally atta: ec i-supporta. if any, including the associated stress incices f
- e. strsss indices for piping produr.ts not covered by NB-3680, if say
- f. iocation and type of all anchors and branch terrainal points
- g. piping clacsification boundaries a m.. -:cw 935211 Page 29 of 62 Pages Date 9/25/88 Revision No, a f
gigge =g 018&a it etNeo u u_______.___
DESiON 5FEStFICATION OETAILS msNwe hve-** :mw form $46428 3.5 - De s ign,_B,,n i s 3.5.1 ' General
- 3. 3.' 1.1 For the Class 1 certions of piping the design rules of Subarticle NS 3600 of the Cece for Class 1 piping components shall ce met. Design for pressure leasing and the stress aac f atigue analyse
- sns11 de perferried using the criteria defin3:
in Subarticle tid-3630 of the de. 3.5.2 Leading Cemb,inations and Stress Limits 3.5.2.1 The leading conbinations and associated limits fer the red re: i leading conditions for the simplified analysis (Subarticle NB-3550 of the Cece) uthed of evaluation are given in table 3.5.2.1 1 " Leading Ce.einstions and Stress Evaluation for Class 1 Piping." 3.5.2.2 Leading cocinations and stress evaluation reevireunts for pres'.utizer saf ety anc relief valve c:de Class 1 piping are given in Table 3.5.2.1.1-1. 3.5.2.3 Leading ced:isatiens and stress evaluation essuirement:, f or briv ond RVLis Class 2 portions per NC-3550 ara given in Table 3.5.2.1.1-2, 3.5.3 Analysis Resvirements 3.5.3.1 Analpical Medels /11 analytical r.9dels shall be based upon the infc.-matico cal'e: out in Ser. tion -3.4.2 to be previced for the piping analysis governec by this spmcificat,ien and +he equipment cata pr: sics: in Appendix i. -3.5.3.1.1 The interaction between components. coepenant su: ports, pi:i g supports and piping shall be considered in the analysis. l 3.5.3.1.2 The efforts of the auxili6ey'llnes, inciuding main steam _ ace feedwater piping, en the RCL and tne RCL en the auxiliary lines shall be considered in the aulysis. 3.5.3.1.3 For the Chis 1 auxiliary piping governed by this specificatien,. interfacir.g with acjacent nen Class 1 piping. the analytical models shall be extended by either of the following wthods: L J1.c.e 955211 Page 31 of 62 Pages .Date ' '25/88 Revision Nc. 4 O '#' 'O 3 % '4*8W30M
pf,$4Gg'{PjplFICAT10N OETAtLS 5 3 %.e.,,, i, -.. :.y.. 3 N,07E5 FOR f ABLE 3.5.2.1 J I I p.t.e _ 9552k1 Page 33 of 52 14ges Date 9/25/08 Revision Ne, A O ' $IN ih I ib IIMM
h I OESiOM SICIFICA1')ON DETAll.3 = s* *c.t se c a.c = e. w g. Form 54 W68 3.5.3.2 Seismic Analysis Requirements 3.5.3.2.1 The response seectra modal analysis technioue may be use: ' analyze the Class 1 pi:4ng in W scoce cf analysis, as defiaec in Section.1.1.3 for the OBE aAd SSE. applicable response scectra cefining the OBE and SSE are provided in Appene'n F (Section 5.6 ef this specification). 3.5.3.2.2 ' e seismic analyses shall be based cn the CBE and SSE being initiated at tne nertal full power ccmcition. 3.5.3.2.3 The percentags cf critical damping aslues to be use: in tre seismic analysis are given in Table 3.5<3.2.3-1. Alternate damping values given by NSWE Code Case N-411, Ref, e Section 2.2.8, may be used for as-analyzed er as-built anai ses s proviced: The ciping system analysis is based en the response spectrum method. Incressed ciping displacements are verified to remain =ithin acceptable limits. The alternate damping criteria is used in their entirety andexclusivelyinagivenanalysis,i.e.,isncttote mixed with damping v4 ues ps:r Reg. Guice 1.61. Verification that increased piping displacements are acceptable is provided. Alternate damping values per ASME todo case N-411 are net a roved for use in connection with multiple input response spectra analyses. 3.5.3.2.4 For piping systems interconnected tetween floers of tha containment internal structure and/or building, tne envolc:e c' ~ the respective floor response spectra shall bt used in the seismic analysis. 3,5.3.?.5 ine piping shall be analyzed for the struitaneous occurrence c' three earthquais components: two orthogonal horizontal anc c e vertical. Three separate unidirectiet.at analyses shall be performed as follows: first analysis for the response spect.m in the north south direction, second analysis fo-tne rescense spectrum in the east west direction, and third analysis fer tre response spectrum in the vertical direction as defined by the applicable responsa spectra. The three directions of shock may be applied indepundantly in each direction with subsequent combination into a total response, or the three directions of shock r.ay be appliad simultaneously to the mathnaatical mocol. cwm:.m g 955211 Page 35 of 62 Pages Cate 9/25/B3 Revision No. a j!h Sh
' DESIGN SPECIFICATION DETAILS
- 8* *t t it t.t :-a.c =m a.. c.
Form 546428 C i i 1 i t )*,c.e .4 w 9 4 7 w '.e wm% 955211 Page 37 of 62 Pages Date 9f25/88 RevisionNo.i .iu.i. ei n. imr= 1 l
gge<Ahumuswse 4-Additionally..for relief valve piping with a comon loop seti, the analyst shall v>rify that the rest critical combinations - i among the power operatied relief valves discharging-are envele:ed. ~ -l If more critical concinations are evicent, the valve thrust i loses associated with these cases shall also be applies to t*e i pressurizer" 5ARV piping system. 3.5.3.3.2.1 C 3.5.3.3.3 Ja,c.e 3.5.3.4 PlW EreaK AnalyMS AQrwe n u ine effect cf pipe break on all the piping governed by this specification snail be considered in the analysis of the system. In particular, the following items shall be consi:e e:. As specifically approved by the U.S. NRC, Ref. Section 2.2.9, the postulation cf ruptures in the RCS main loop is no longer repuired. In addition, the dynamic effects associated with t*e previously postulated RCS main loop pipe breats need no longer a to be coniseer.e. Th.se dynamic.rfecta that no.d ne longer ce considered include: Asymmetric pressure loadings in compartments Pipe whip restraints Jet shields Jet reactions 3 Decompression blowdown waves Missiles Reactor internals design NOTE: -Design criteria for supports (exclusin of those restraints specifically designed for pipe rupture loadings) for heavy equipment are to remain unchanged at this time.
- Also, design requirseents for ECCS containment and equipment qualification are to remain unchangui at this time.
o ~-,..,,~ m 955211 Pago 39 of 52 Pages Date,9/25/88 RevasionNo.i
- iste tg Wine it-antate
DES 3GN SoECIFICATION DETAILS
- 8'"*'wu n o t,.: en.w w
~g Fctm 546428 3.5.3.4.3.3 The effects of jet impingement en the RCL for tre postulated breaks referenced in Section 3.5.3.a.3 shall be evaluated in a manner censistent with Chapter 7 of ANS 59.2. [ 3a.C.e Required interface information, as defined in Table 1.1.5.'. 7-2, for the costulatec breaks referenced in Section 3.5.3.4.3 e a :e proviced by the ciping analyst to the C6ner for use in the Ove-scope of responsibilities associated with jet impingement f:r these pipe breaks. 3.5.3.4.3.4 In the evaluation for the breaks identified in Secticn 3.5.3.4.3 in the pressurizer surge, RHR suction, and accumulater lines, t e faulted concition stress limits shall be met for all RCL dpic; c' all loops, 3.5.3.4.4 Not used (Deleted). 3.5.3.4.5 An analysis shall be performec on the Class 1 piping fer the effects of a main steam line pipe break and a feedwater line pipe breat. Double ended guillotine breaks shall be postulated :: occur independently at the SG nozzle / main steam line anc 50 nezzle/feodaatarlineweldjoints. The responsibility fer providing the thrust time relationship to be used at the ass e: main steam line pipe creak locations is incicated in Secti:n 3.4.2.1.a. If pipe break locations are identified by the Owner (as recWe: by Section 3.4.2.2.4) in the main steam or feedwater lines tnet may result in higher Class 1 piping system loadings than from tae above assumed breaks, these breaks shall be evaluated'in tne :':e break analysis per the requirements of this specificatien. 3.5.3.4.5.1 The effects of jet impingement on the Class 1 piping systems ':r the postulated breaks in Section 3.5.3.4.5 shall b$ evaluatec n a mannar consistent with Chapter 7 of ANS-58.2. In particular. :: Analyze for maximum jet forces on top of the SG, the broken en:." the main staan line shall be assumed to dispiace laterally one outside diameter of the line. Required interfaen information, as defined in Table 1.1.5.1.7 2. for the untulated breaks referenced in Section 3.5.3.4.5 snail :s provided by the piping analyst to the Owner for use in the 0*ner scope of restonsibilities associated with jet impingement for thete pipe breaks. l
- = m; w. w 4 955211 Page 41 of 62 Pages Date 9/25/88 Revision he. 4 i
. w... l
l OtsicN SPtCIFICATION DETAILS - '* N - " 4 ' * * ~'*~ a i Form Sa64*S 4 .l j I ' Table 3.5.3.6.1-1 also defines applicatle load combination letter cesignatient that correspond to the applicable load combinations in Table -3.5.3.5.1-2 of this specification for the various operating conditions. After tF4 valve classification and load combination have been determined from Tabis 3. 5. 3. 6.1-1 and Table 3.5.3.6.1-2 of inis specification for the eparating condition being evaluated, the loads resulting on t5e valve from the ciping analysis shall be properly combined and compared a -limits defined in Table 3.5.3.6. gainst the appropriate allowac'e 1-3, Tables 3.5.3.6.1-4 and 3.5.3.6.1-5. Table 3.5.3.6.1 3 defines the operability / structural integrity nozzle end load limit criteria for W supplied Class 1 valves interfacing _with Class 1 piping g:verned by this suscification. Tabla 3.5.3.6.1-4 states the coerabilityt structural integrity nozzle end load limit criteria for Owner su; plied Class 1 valves (if applicable) and Table 3.5.3.6.1-5 provides acceleration limit criteria for Class 1 valves interfacing with Class 1 piping govsrned by this speclficati:. 3.5.3.6.2 The piping analyst shall verify that all allowable limits defire: in this specification have been met for the valves listed in ao'e 3.5.3.6.1-1. P 4 <..,..., <,,e 955211 Page 43 of 62 Pages Date 9/25/B8 Revision No a
. -.. - - ~. ~.. t ,4 DE$iGN SPECIFICATION D1TAlt.$ m s+we.H t s c-o.c st**.ea c. = Form 5:4428 t TA4Lt 3.3.3,g,1 1 (54st i et 3) vatyt-afgylstatut5 4 i l 1 i 1 l 4 i l 1 i .ja c.e 955211 Page 45 of 62 Pages Date 9/25/88 Rev4 ion No, i. l- _,,w _...,... -.., -........ -.,.,........ -,. - -.... 1 m.
SESIGN' ;PECirlCATION DETAILS esN-osu e.oroc u..%.. Fonn b60429 Notes for Table 3.5.3,6.1-1 C 3 J ja.c.e n.,~. e, 955211 Fage 47 of 62 Pages Dats 9/25/88 Revision No. 4 .in.... m l l
]g%myw~~ ~.~ e.ein414.nv for t.s. 3.s.3.s.1 1 i \\ -_ (. 1 i l l I l I ]&.C.t .~.1 w t. verpr.,- m-, 955I11 Page'49 of 62 lages Date 9/25/88 Revision-No. 4 ~ =. .,i.- -ei io u.
l pt,s40,N,llg*icAtioN orrAiLs mmx,a,am m., TABLE 3.5.3.6.1 3 N022LE h D LCAD LIWITS FOR E SUPPLIED VALVES [ 'J f ja c.e .wsw w.,, e-955211 Page 51 of 62 Pages Oste 9/25/88 Revision No. A emem--- -w _ __, m.a_%.,eyy. m,. 4*Me tQ l'Me16 5224
-.~ . -.. _ - - - -. ~. -. _ - {t,b g g d+aemmwaemaa [ t 3.5.4 A.dciitional ae,quirements e' 3.5.4.1 R9 Quire: leads en primary acwhe.ent from the pioing analysts, gg d# fined in f adla 3.5.4.1 1. shall be provided to W f or verification of the adecuacy of the primary ocuicTnent. l r 3.5.4.2 59ecort osds 3.5.4.2.1 Resulting leads 03 3rimary equipment supports and ML pica restraints for lead \\ng conditions from the piping analys'.s I g,overned cy this specification shall be crovided to W Sverce: .tructure Design for =erifi44 tion of the adottuacy ef"these
- supports, 3.5.4.2.2 Resulting loads on piping succorts and restraints, other t c.-
the succorts described in Sectien 3.5.4.2.1, for loscing cce:'- tions frer, the Dicing analysis governed by this specificati:e shall be proviced to the Owner Tor verification of the ace:.a:, of these supports. L 3.5 4.3 Bottom Mounted Instrementation Tubing 3.5.4.3.1 Analysis of the bettem mounted Instrunntation thimble guice tubing is-proviced by the recuirerhents of Westinghoute i Specification-955544 Revision 1. i. .i I ) i ) -r- - 953211 Page 53 of 62 Pages Oate 9/25/68 Revision g, g e i, ein. e-mm . _ _. ~,. _
i ptig' canon otTAIL's .e-*** *n u ew m... tA8LE3.5.4.11(SUPPlEWENT) A00!T!0NAL LOA 05 OATA MOU! RED FOR PRIMARY E0VIPutNT(1) t 1 l l 1 i B. s i e 5 4 ja c.e minwo I 955211. Page $5 of 62 kges Oste 9/25/88 Revision No. 4 J15 4i OIM OM . 4 -.v .,.,.,._w. ....we. .,w. v.,,.. ..,.,w,o-._... .y .,..w.,
' Il0N t "8- *c c.u s.n-e n cu% korm SdFfCtFicATION DETAAC 25 s F 5.0 AP,PPO!XINr0RwAt!cw The design and analysis information contained or referenced ta the following accendices applies to the GAE/GBE units. Con'ir-mation of the latest revisions for the following docunents may be obtained from the Vogtle PIP. 5.1 apceacia A Fivit$ystem Descriotten}, 5.1.1. W fluid system descriotien document nv4ers for the RCS. CVC$. bR$ and $l$ are listed in Table 5.1.1 1. TABLE 5.1.1 1 W Fluid System Descriptien Document $ystem Document W. RC$ 50 GAE/G8E 281 CvC3 SD GAE/GBE 282 RHR$ 50 GAE/GBE 283 S!s 50 GAE/GBE 264 Note (1):lt is the responsibility of the analyst to identify the ccrrect revisien to fluid system description documents to use in the analysis. 5.2 ,Appendit B - Fluid System Flon Diagramn 5.2.1 W fluid system flow diagram numbers for the RCS, CVCS. RMRS. r ind 513 are listed in Tahle 5.2.1-1. l IOLE 5.2.1 1 FluidSystemFlow04aaram[1) System Uni t 1 0.o. No. Unit 2 Dwc. No. Sheetts' g l Le and 1094E74-1094E74 1 RC 1094E69 1872E05 1-2 CVCS 1094E70 1872E06 14 1094E76 1094E76 1 RHR5 1094572 1872E08 1
- 515.
1094E71 1872E07 1-3 ' RTV 1094E75 1094E75 -1 (1): It is the responsibility of the analyst to identify the ccrrect revision to the fluid system flow diagrams as provided in the Wegt'e P!P. l / vmwow, 555U1 Page 57 of 62 Pages Date 9/25/8! Revision No. 4 L ei i i, e m. ie mm .. ~ ~..,..
A S mi s d4 3 __ u N m 3 -u+ - a-co aw i 5.6 Appendin r seismic design Date 5.6.1 The aceroved response spectra OBE sad SSE. for the Georgia Power Company Alvin W. /cgtle Nucleer P16nt (GA[/GBE are contained in the attachments to the following Bechte],Po.or l letter 55 1494 dated January 31, 1979, and is ofi file Compary[ngineering Mechanics Department. in the This spectra, as l geneested, reflects the criteria change from a two camponent (2 0) earthovake to a three cortonent (3 0) earthawake and contains the terstenai certhquate input as required by the NR;. t P I k am, 955211 Page 59 of 62 Pages Date 9/25/88 Revision No. 4 _w._ -==. i.u.m .-=,,~,,e--,- .-,,,,yi - ~ ~ - r .-,,-t--~,.e ~, -, --.r,,r+-- 4-,,--,-.---- -r"~--
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