ML20024B052

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Forwards Info Completing Resolution of Three Generic Items of Concern Re Outstanding Issue 8 of Suppl 3 to SER Covering Balance of Plant Equipment,Fatigue Testing & Category I Equipment Change Records
ML20024B052
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/28/1983
From: James Smith
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
SNRC-921, NUDOCS 8307050031
Download: ML20024B052 (114)


Text

{{#Wiki_filter:- - _ _ _ _ _ _ - . O l 4 i LONG ISLAND LIGHTING COM PANY SHOREHAM NUCLEAR POWER STATION L- ---.. .. -

                     .c . _ . w t     P.O. BOX 610, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 Direct Dial Number June 28, 1983                                                                           SNRC-921 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Dynamic Qualification SER Outstanding Issue No. 8 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 i

Reference:

Supplement Number 3 of the Safety Evaluation Report Related to the Operation of the Shoreham Nuclear Power Station - Unit 1

Dear Mr. Denton:

The purpose of this letter is to transmit information necessary to complete resolution of three generic items af concern contained in outstanding issue number 8 of Supplement number 3 of the Shoreham , Safety Evaluation Report. First, as stated in item (2) on page 3-5 of SSER 3, LILCO com-mitted to improve the qualification documentation in BOP SQRT i packages by including either complete test reports or summaries including anomalies and their resolutions by June 1983. This commitment has been fulfilled. The BOP SQRT packages were review-ed and have been revised as needed to add complete test reports or summaries of anomalies and resolutions. Second, enclosed are three calculations intended to fulfill the commitments and requirements contained in item (1) of "the appli-cant's response..." on page 3-8 of SER Supplement number 3. The G.E. calculations are sample calculations of usage factors for both ASME Code and non-ASME Code components.. The SWEC calculation evaluates the potential effects of f atigue "due _ to SRV cyclic loading on the dynamic qualification of, BOP plant' equipment. In the SWEC calculation, four components were chosen based on their location in areas of the plant.where SRV loads are~known to be most significant. The four components are the head tank, loop level pump, booster heat exchanger and the velan gate valvo. For all components analyzed in both the NSSS and BOP calculations, the 1 8307050031 830628 g FC-8 9 35.1 PDR ADOCK 05000 E , s . :.

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o ( SNRC-921 June 28, 1983 Page 2 cumulative fatiguc usage factors are less than one. Additionally, We enclose a summary entitled, " Fatigue Evaluation of Components Qualified by Test" in order to clarify how fatigue testing was conducted in assuring that the Test Response Spectra enveloped the Required Response Spectra and that the input loads were suSficient to cover the duration and number of SRV cycles that have been defined. This summary fulfills the requirement stated in item (2) of "the applicant's response..." on page 3-8 of SSER 3. It is a summary of an analysis of a typical shake table acceleration time history and representative SRV floor time histories in which fatigue damage from the test motion is compared to fatigue damage from SRV loads. The calculation demonstrates that the fatigue usage from a typical test sequence far exceeds the fatigue usage from anticipated SRV loads over the 40 year plant life. Thus, the three genpric items of concern are addressed. Finally, we enclose two lists of Shoreham Category I Equipment Change Records, one for BOP and one for NSSS equipment. These are provided to fulfill the commitment beginning in the last paragraph on page 3-8 and continuing on to page 3-9 of SSER 3. The lists contain field modifications made to already qualified and instal-led safety-related equipment since the September 2, 1982 site SQRT audit date. In accordance with R. L. Tedesco's letter to LILCO, dated January 21, 1981, four copies of this submittal including enclosures are being forwarded directly to Dr. Morris Reich at Brookhaven National Laboratory. Should you have any questions regarding the material enclosed, do not hesitate to call this office. Very truly yours,

                        .   .        t/
                       . L. Smith Manager, Special Projects
                  . Shoreham Nuclear Power Station s        GJG/ law S3 Enclosures cc:      J. liiggins Dr. Morris Reich, BNL (4)

All Parties Listed in Attachment 1 x r b

0 ATTACHMENT 1 . Herbert H.' Brown, Esq. Lawrence Brenner, Esq. Administrative Judge Lawrence Coe Lanpher, Esq. Atomic Safety and Licensing Karla J. Letsche, Esq. Board Panel Kirkpatrick, Lockhart, Hill U.S. Nuclear Regulatory Commission Christoper & Phillips Washington, D.C. 20555 8th Floor

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1900 M Street, N.W. Washington, D.C. 20036 Dr.. Peter A. Morris Administrative Judge . Atomic Safety and Licensing Mr. Marc W. Goldsmith Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C. 20555 . Waltham, Massachusetts 02154 Dr. James H. Carpenter MHB Technical Associates Administrative Judge 1723 Hamilton Avenue Atomic Safety and Licensing Suite K Board Panel . San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 '

                             .                                               Stephen B. Latham, Esq.          -

Twomey, Latham & Shea Daniel F. Brown, Esq. 33 West Second Street Attorney P.O. Box 398 Atomic Safety and Licensing Riverhead, New York 11901 Board Panel - U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ralph Shapiro, Esq. Cammer and Shapiro, P.C. 9 East 40th Street Bernard M. Bordenick, Esq. New York, New York 10016 David A. Repka, Esq.

            . U.S. Nuclear Regulatory Commission                                      ,

Washington, D.C. 20555 ~

                  *                                                 .       ' Matthew J. Kelly, Esq.
                    ,      ,                                                 State of New York
                                  .                                          Department of Public Service James Dougherty                                                Three Empire State Plaza 3045 Porter Street                                             Albany, New York 12223 Washington, D.C.         20008 J

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4. LOADING CRITERIA
  • U 4.1 seismic Loads The maximum seismic loads to which the RER and CS Notors are '

subjected were determined from the results of analyses performed in References 8 end 9, respectively. In these studies, detailed computer models of the entire pump and motor assemblies were developed. Response sportra analys:,s was then used to determine the induced ' acceleration at each node location due to a SSE event. The nodal

               -                   acceleration values output by these computer runs were used to find the. maximum seismic loadings by applying the following procedure:
1) In each of the X,Y, and I directions, the maximum acceleration occurring at any mode in each of .the two actor models was l determined.
2) The highest vertical acceleration occurring in either the RER or CS motor was then taken as the maximum vertical seismic load.
3) '

The SRSS was found forThe theI maximum I and I accelerations and I accelerations corresponding occurring in each motor. to the highest SRSS value were then taken as the horizontal seismic loads. The above procedure is conservative, in that the maximum seismic ' loads in the horizontal and vertical directions bound accelerations ir.

                             +     both the RER and CS actors.         -

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                             -               The seismic loads applied in this analysis are:

Vertical (Y) 2.70 g Borizontal (X) 3.44 g Borizontal (3) 1.73 g

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These loads are input to the computer model of the CS notor as forces applied at the appropriate nodes. 1 A i 4.2 Magnetic and Centrifugal Loads

    !                                        If the shaf t undergoes a deflection relative to the stator frame,
    ,                                an unbalanced magnetic force will be induced between the rotor ll                                    and stator cores.                From Ref. 2, the radial magnetic force for the

!! core spray motor is 783 lb. for each 10% of the 0.045 in. radial air l: gap which the rotor is displaced. The magnetic coefficient for the lt RER motor is less (770 lb.): therefore, the value corresponding to the core spray motor was used in determining magnetic loads. '. .( 1 . . MADE BY - . T & g=y i vemato BY y-

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                  .      - U Ts iis e.szo m ses                                                                   '

i lam'sesses ser urs aos-issa has r-FIG. B-9.1 DESIGN FATIGUE CURVES FOR CAR 90N, LOW ALLOY, AND MIGN TENSILE ,' STEELS FOR METAL TEMPERATURES NOT EXCEEDING 70lPF f ,

                                                                -   TsMe I-9.1 Centales Tahulated Values and a Fennula for Accursie                                                                               ;g laserpesamien et These Corws
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arench is to use the tensue strength kdsber etrength trees, strees een. tron seder sesept:tely reverned ler satigue Balt) and, after deter. eentration factere associated with et benang stress are shown mening the asetten modulus et the changes of tape la the part are asi. gra en left an yng.11,in shape, to afply the proper t ser leads as wall as wtuch point represents the forinata. zowever, because bending tension leads. data freen one specimen.he efetu et the escalty en obtaining a Medales . Typleal et temperature en fa hatt and . l Talee $st the tensile stress strain surves gray kan tensue strength are in the la testa ofsmaD speclanens, are shown la Fig. St. Orsy iron does right. hand graph in . II, the computed at this manner ober Boottels law and the modu. Antal leading or onalleneas will usuaDy be somewhat lower than la tendon is usutu/ deterunamed cycles are frequently encountered la' the actual load required to rapture arbitrarily as the slope et the une designing parta et cast iron, and la te part. salees unfavorable reeld. eennecting the artgin et the stress. many instances these are not osa. stresses are present in the 88 ettsin tarve with the potat . pletely reverned loads. s of reg. part, be g of the e alarly repeated stress

  • uon asu.

Elearstine of bron at frac. ngth. Bosne engineers use"the ally can be arpressed as a functaen ' tore h very (et the areer of slope of the strees strain tarve near et a mean stress and a stress range

                      .e                                                         the artgin der deteradatag me Whatever possible h destgaer to                                                          modalus of elasticity                             should use actual data froen the ha.                                       .

As indicated in Tabie it, the med. $ sed intormation avallable. W1thout 60 e slas of gray iron varies considerably proctaely appilcable test data, an es. gg more than for aiost metals.Thas.In Ilmate of the reversed bendaag C"" 8

                                                      ,,,,,r                     maing ebeerved strain to es!calete taugue lim!t of machined parts may                                             '

s stress it is essential le measure the be made by using about 34% et the ' Iao r modulus of the particular gray iron minimum spectfled tenaue attragth 30 j'/ j specimen being considered.De nu. et the partleular gade of grsy nren 1 20 / // 7- _ merleal enlue et the modulas an being considered. Tnla is probably a Iorsion is alwa a less than in ten. safe value rather than an average

                           @7M.b# N elon, just as it fe for steel.                    et the few data avausble concerning oc                                         30   -

Bardanes of 1rtm, as mass. the fatigue limit for gray iron. e i l ared by BrtneD er testers, # 9 8 3 3 4 is an average result of the Soft Thhte 13. C.mparisme of B.ekvis 3.wi. See ., anot .6 so, am grsph!te in the tron and the metaule suas of GNr l'*- 881885emens y matrtz. Yartations in graphite seae DF G'*8h8'8 r g # "' and distribution wtU cause wtde war. am,,e p 'g[;, sees.e as.a.s. m Da er M'8$.s m.,*,,g lations in hardness (particularlv Tree d twins . ures Itockwen hardneas) even thougis " "'" " ' * * "M " U",m. od sAr 3 se et th tansGe C. stterneenag

  • fta  % the hardness of the metallic matriz a ....... gas e3(e3 ets ,

3a constant. To Illustrate this efect, a ...... . tas eJ ms . as 4D08 in. per in.) and hence is sel. the microhardness of h matriz et g . . . . . . 4Ao es dom reported. De designer,cannot of stma .S.ee of hardened lion as sea. re Pw"th mociw.n e mesa,e. 5"*"*fs

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      .            u.se      mnum ens elongsuon                e m e ,s ue.uan usa uve. g = m meuan,mahownin g i< n ,g., ;; g g ;g in any "i""*s'i.a ai abes, etna, as correlatfo>n=is                       naa ,nttoat               if any hardness =. g m*ie,v '

shown in Table 12. most gray trens be attempted, the earu. et,s:n.d an taw er ar em M =um.;r

              , have bish tors:enal shear strength. graphite must be constant as to type eu.a s a not ' tra tarL.a.t.                                                              . w.t ama             t Blany grades have torsional strength and amount in the trens being caen. 8P'8                                     smes      C. orti.

88 8882**'3 C es to 64. b greater than some grades of steel. pared. It is recommended that Erin. This characteristic, along with low all hardness be amed than possilde. . notch senatursty, makes gray iron a Anap sultable material for anafung of Fetigue Unit la teverted range o[roximation stress on theoffaugue the efectof hart I

      *4                                 , particularly in the                                                                       may be obtained from 6.'agrams                                        !

eartons Seeding

  • grsdes ther tensue strength. such as F13. II. The tensUe strength  :
            .       Most shafts are subjected to dy-                                  Because fa             timtta are expen. As plotted on the horisontal azt ts                                         '

h mor* torsional stresaes and the de- sive to de e. the designer asu. represent the fracture strength an. signer should consider carefully the has incom te taformaten on der staue load (which corresponds t

      ]             enact nature et the loads. For the                                   property,            ca18 N earves for to aero stress range).The revursed 30                                              ao                                                                                                                        .,
          >*                                                                                                      Fane s. hoe                                            v.mah. reset
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_ m . . . . _ - _ . . _ _ _ . _ . . . . - . . ... _.m. _ ____ _ _ .._ . ._ . e- ' CALCULATIO'i # II600.02 tet(B) 382 CZC FATIGUE EVALUATION OF FOUR REPRESEtnATIVE CO!!PONEf4TS REVIEH STATEMENT s 1HIS CALCULATION HAS BEEF 4 REVIEHED IN ACCORDANCE HITH EHTP 6.26 i AtQ HAS FOUFC TO BE ADEQUATE. THE HETH00 CF REVIEH UTILIZED [ HAS (CIRCLE Oriel: ' A. CCf1PARISON HITH A SIMILAR PPEVIOUS CALCULATI0tff40. j

REVIEN OF CALCULATION.

C. ALTERt4 ATE CALCULATION NO. L. G 93 QE V f, e & S__ (SECTIONS /:"

                                                                            ., .E.I,. ER df            , /O[ @ 3 3
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(AN INDEPE! CENT REVIEH IS F10T REQUIRED FOR THE SHOREHAH PROJECT) N 2 E v S CQ 00 to O L I ' (*v b D s 01 - i. 4

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0-CALCLtATIOt 8 11600.02 tet(B) 382 CZC FATIGUE EVALUATICH OF FOUR REPRESENTATIVE COW ONENTS TABLE OF CONTENTS FATIGUE EVALUATION OF FOUR REPRESENTATIVE CotPONENTS LILCO SHOREHAM PRELIH. PAGE PAGE TITLE PAGE A-1 1 REVIEN STATEMENT A-2 2 TA3LE OF CONTENTS A-3 3 i REVISION STATUS TABLE A-4 4 INTRODUCTION A-5 OBJECTIVE A-10 ASSUtPTIONS A-11 HETHOD OF ANALYSIS B-1 7 DESIGN ItPUT C-1 9 HATERIALS A!S PHYSICAL CONSTANTS C-t 8

                                                                    * ,0I REFERENCES C-}

Sut!ARY OF RESULTS D-1 Ib CONCLUSIONS D-4 I fe SECTION E RBCLCH HEAD tat 4<S E-1 I SECTION F GOULDS HODEL 3196 ST SIZE 1 X 1.5 - 6 REACTOR CORE I!OLATION COOLING PLAP F SECTION G STRUTHERS HELLS CORP BOOSTER HEAT EXCHA!tGER G Yb SECTION H VELAN 10" FORGED BOLTED BottiET CATE VALVE (IttCLUDItG THE HARMED-UP VENDOR # CALCULATION 3 H-1 b

l t .' S D- 600.02 NM(B) 382 OZO

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3 CALCULATI0ti s 11600.02 tei(B) 307 CZC FATIGUE EVALUATICri CF FOLA REPRESEtITATIVE COPotIENTS INTRODUCTIOrt/CSJECTIVE IT IS NOT GENERAL PRACTICE TO AfttLYZE COtPCtfENTS FCR FATIGUE EFFECTS LTLESS THE COMPCTIEffT IS AN ASME CLASS I CC!PONEtiT OR CLEARLY REQUIRES SUCH AN A!t"1YSIS TO SATISFY tiORlW. GPERATItG CYCLIC STRESS REQUIREf!ENTS. THE ADDITICri 0F HARK II OR HYDRCDYiW!IC LOADS. HAS RAISED CCitCERif THAT SRV LOAOItG COULD CONSIDERACLY CHAtiGE THE ASSUIPTIO*4 THAT FATIGUE IS tiOT IIFCRTAtIT FOR CotPOf4ENTS OF A i:UCLEAR Pol:ER PLAtif. SRV iSAFETY RELIEF VALVE) LOADS OCCUR A FU CER OF tit!ES TERCUGH-OUT THE LIFE CF THE PLAT {T Arc ItF03E SIGNIFICANT OSCILLATItG ACCELERATI0tG ON CC!PCriENTS. THE t;RC HAS REQUESTED Att EVALUATICri 0F THE POTEffTIAL EFFECTS OF FATIGUE DUE TO SRV CYCLIC LOADItG Cri THE DYNMtIC QUALIFICATI0tf CF PLANT EQUIPl!ENT. TO SATISFY TilIS REQUEST. FOUR CCfFCliENTS HAVE DEEN CHOSEN FCR EVALUATICN. SRV FATIGUE EFFECTS HILL ACD TO THOSE FR0!! OTHER DYtlAffIC LOADS DUE To t:CRitAL OPERATION, EARTHQUAHE AtG LOCA. THUS ALL DYNAftIC LOADS ARE CCtGIDERED IN THIS AtlALYSIS IT IS THE PURPOSE OF THIS REVIEH TO CCttSIDER OrlLY THOSE CCtFotIENTS THAT HAVE BEEN QUALIFIED BY AtlALYSIS. CCfFCHENTS QUALIFIED BY TEST HILL DE TREATED IN A SEPARATE REVIEH. _ 9

  . . - .    . - . . . - . . - - - -                           . . - . - . _ - _ _ .   - ,    .. _ ~ .  .
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CALCULATIOt 8 II600.02 te4(B) 382 CZC FATIGUE EVALUATIO*t OF FOUR REPRESENTATIVE C0tPONENTS i ASStRPTIONS

' Il THE FOUR CO*PotiENTS HAVE BEEN SELECTED BASED ON THEIR POTEtRIAL ,

FOt SRV FATIGUE EFFECTS. Att EFFORT HAS BEEN HADE tCT OtLY TO PICH . REPRESENTATIVE CCtFONENTS BUT COtPCitENTS HHICH REPRESENT

  • HORST i CASES". THE REPRESENTATIVE Are
  • HORST CASE" t!ATURE OF THE COFONENTS CHOSEN IS AN ASStRFTION BACHED UP BY SELECTION CRITERIA DISCUSSED IN THE *HETHOD OF ANALYSIS" SECTION.
3) IT IS ASSUtlED THAT *ASSE! SLY" BOLTS HAVE BEEN PRETEfGIONED TO AN EXTENT CONSISTENT HITH GOOD HActINE DESIGN. THESE ASSE}CLY ,

BOLTS ARE THOSE THREADED FASTENERS HHICH C0t24ECT COtFO!IENT t SUB-ASSE!SLIES. FOR THE PURPOSE OF THIS EVALUATI0tt THE PRETENSION 4 ASS 12tED IS 70% OF THE tA.TIHATE STRE!GTH OF THE BOLYItG (REF 40 PAGE 6 3. PRETEtGI0tt IS tCT ASSU!!ED FOR COFOMENT EISE0HENT BOLTS. I C0!iSEQUENTLY ASSE!'CLY BOLTS 00 tCT HAVE STRESS CCtCEtiTRATION FACTORS APPLIED AS L0ts AS THE CALCULATED STRESS DOES PCT EXCEED THE PRETEfGION STRESS. EPSEDt!ENT BOLT STRESSES DO HAVE STRESS C0ftCENTRATI0tt FACTonS APPLIED BECAUSE PRETEtGIONItG A!C HAINTENANCE 3 OF PRETEtGION OF THESE BOLTS IS NOT EXPECTED. t t i l 4 i M 9 e i I _. ._. _

    ---   ~              .-                     _     _

m_ _ _ __ _ .. _ _ m . _  ; _ _ . CALCULATI0tt 8 II600.02 t@ttBI 382 CZC FATIGUE EVALUATICil 0F FOUR REPRESEt(TATIVE CotPONENTS METHOD CF AttALYSIS FOUR COMPONENTS HAVE BEEN CHOSEN FCR FATIGUE EVALUATION. THESE HAVE BEEtt CHOSEN BASED off REVIEN OF STRESS ttARGItG APO BASED CN BEItG LOCATED IN AREAS CF THE PLANT MIERE SRV LCADS ARE KtGl4N TO BE ltOST SIGiiIFICANT. THE HEAD TAfH HAS DIOSEN BECAUSE IT IS THE OriLY SIGNIFICANT TANH I?GICE THE REACTOR BUILDItG. THE LOOP LEVEL FUt1P AfD THE C00 STER HEAT EXQiAtGER BECAUSE THEY ARE tt0UNTED AT EL 8 0F THE SECatcARY Cat (TAItttEt4T. 82iERE SRV L'OADS ARE LARGE. THE VELAN GATE VALVE HAS CHOSEtt BECAUSE IT HAD BEEN IDENTIFIED AS CtlE OF THE t!OST SEVERLY LOADED VALVES BASED ON AN EXTEtGIVE REVIEll 0F VALVE QUALIFICATION LOADS. ' FATIGUE EFFECTS HAD NOT BEEN CCitSIDERED IN THE STRESS CALCULATIONS FOR THESE C0tFO*iENTS. H03(EVER THE FCUR CCHPONENTS HAVE ALSO BEEN CHOSEN BASED ON THEIR FOTEtITIAL FCR OPERATItG LOADS CotiTRIBUTItG TO FATIGUE. A PUtp HAS BEEff CHOSEN BECAUSE OF THE POTENTIAL FOR ROTATItG INERTIA LOADS. A VALVE HAS CEEN CHOSEN BECAUSE OF THE POTErlTIAL FCR OPEtVCLOSE LOAD CYCLE FATICUE. THE HEAT EXCHAtGER POTEffTIALLY HAS SYSTEH AND FLOH TRANSIENTS THAT HAY C0tf7RIBUTE TO FATIGUE. THE FIRST STEP IN TNE EVALUATION OF EADI COMPONENT IS TO IDENTIFY HAJOR STRESSED APEAS. THIS IrlVOLVES 50!!E JUDGEttENT IN THAT THE ORIGINAL CALCli.ATICt:S !!AY NOT HAVE CCriSIDERED STRESS CONCENTRATI0tG IN THE CHOICE CF AREAS TO BE TREA1ED Iti THE CALCULATIOff. THUS A PORTICH CF THE CottPCtlENT HITH LC11 STRESSES BUT HITH HICH STRESS CONCENTRATIOff,ifAY HAVE BEEN NEGLECTED. THE CCitPCtIENT DESIGN IS REVIEHED FOR SUCH AREAS AtB STRESS CALCULATIONS ACDED AS NEEDED. , THE NEXT STEP Irl THE EVALUATI0tl IS TO SORT OUT IDtAT PORTION OF EACH STRESS IS C0tiTRIBUTED BY EACH LOAD CASE. STRESS CCt!PONENTS OUE TO OSCILATIts LOADS AGE SPLIT CUT. 20RtML CPERATIrlG LOADS HOULD TYPICALLY HAVE THE POTEtiTIAL FCR THE LARGEST tlurEER OF LOAD CYCLES - INERTIA AND PRESSURE LDADS OUE TO ROTATItG EQUIPttEtiT. FLUID TRAftSIENTS DUE TO SYSTEll OPERATItG CYCLES. VALVE OPEtVCLOSE CYCLES ETC. ItARM II SAFETY RELIEF VALVE LOADS tJtE C0!GIDERED NT!!AL OPERATItG LOADS IN THAT THE REACTOR CUILDItG HILL SEE LOADS CUE TO SRV CPEt1ItG A t?Jt3ER OF tit!ES THROUGtt0UT THE LIFE OF Tl!E PLANT. CPERATItG CASIS EARTHOU?HE LOADS ALSO " ~ FALL ItiTO THIS CATECCRY. OTHER OSCILLATItG LCADS INCLUDE FAULTED LOADS SUCH AS THOSE CUE TO THE DESIGil BASIS EARTHQUAME. NEXT, A FCf 3ER OF CYCLES 10ST BE ASSIGN!D FCR EACH ALTERNATItG LOAD. THE C01:PCriEtiT DESION REPC'?T. DESIGtt SPEC. FURCHASE SPEC SYSTEtt DESCRIPTION.tTt SYS1 Elf LESIGli SPEC ARE DE Co*tSULTED TO ICErlTIFY trutt!'.AL CPERATItG CYCLES. THE ECUIVALENT t:UtCER OF PEAM SRV ACTUATIOtG HAS EEEN DETERitIriED FCR THE SHCREHA:t PLAriT TD E,E 900 EVENTS. THIS trJOER CCt!ES T 4 9

CALCtA.ATION 8 11600.02 teitB) 382 CZC FATIGUE EVALUATICN OF FOUR REPRESENTATIVE C0tPONENTS FRCit A CALCULATION OF SRV STRESS CYCLES FOR SHOREH44 PIPItG ANALYSIS (REF CALCtlI600.02 PP(B) 450 FG). IN THIS CALCULATION THE FULL PAtCE OF SRV ACTUATIOtG ( Arc CORRESPotCItG SUBSEOUEhT ACTUATIOfG) ARE CotGIDERED. HAlfY "LCH LOAD" SRV ACTUATIortS. SUCH AS A SItGLE VALVE ACTUATIcti. OR FOUR VALVE ACTUATI0tt. OCCUR HANY ttCRE TIHES THAtt THE 900 CALCULATED EQUIVALENT PEAK EVENTS. THE PUSER OF EQUIVALEtiT PEAM CYCLES FOR EACH SRV EVENT IS CALCULATED BASED ON A HETHOD OERIVED FRutt ASt:E III NB-3653 At:D SUtstED TO THE 900 TOTAL. THIS HETH00 "DERATES" A TYPICAL LCH-LOAD FUSER CYCLES TO A LCHER EQUIVALEt4T IUSER CF CYCLES AT THE HIGHEST SRV LOAD (SRV 11 VALVE ACTUATICit). A SIHILAR TREATHENT OF THE LOCA EVENT YIELDS A REQUIREttENT TO DESIGN THE PLANT FOR A SItCLE PIPE BREAN (REF

11) HHICH PRODUCES UP TO 200 EQUIVALENT PEAM " CHUGS" TI:E t& CER OF DESIGN CBE EVEffTS FOR THE SHOREHAH PLANT IS S. THE flUtBER OF DESIGN DBE EVENTS IS ONE.

EACH APPLICATION OF A DYNAHIC LOAD HILL EXCITE AN OSCILLATItG RESP 0ttSE HHICH HILL OCCUR DURItG THE EVENT AfD DAttP OUT AFTER THE EVENT. AN EQUIVtJ.ENT tutBER OF PEAM STRESS CYCLES ituST BE DETERNINED FOR EACH DYNAltIC EVENT StAttIrG DVER ALL THE CQP0tiENT OSCILLATI0tG. THIS MIALYSIS HAS BEEN PERFORt!ED FOR PI?ItG (SEE THE ABOVE REFEREttCED CALCULATION) Atc HAS DEEN FOUtD TO BE DEPEtOEtiT UPON CCtPONEtiT FREQUEtiCY MO STRESS LEVEL. FOR TYPICAL STRESS LEVELS IN PIPES THE UPPER BotAD Ott THE NUtBER OF EQUIVALENT HAX STRESS CYCLES HAS DEEN F0ute TO EE .3333aFN PER DYNMtIC EVENT. FOR THE PURPOSE OF CO tPCttENT EVALUATIOttS. THIS RELATIOff HILL BE ASSUltED TO APPLY FOR ALL DYNMtIC LOADItG. THE EQUIVALENT tutBER OF PEAK STRESS CYCLES FOR EACH LOAD TYPE IS THE PRODUCT OF THE NUISER OF EVENTS PER LOAD TYPE Atc THE NUICER OF EQUIVALEt{T PEAM STRESS CYCLES PER EVENT. AT THIS POINT STRESS LEVELS Ato CORRESP0t0ING FUSER OF CYCLES AT THESE STRESS LEVELS ARE AVAILABLE. STRESS COtlCENTRATICit FACTORS ARE

  , APPLIED TO EACH STRESS C0t:PattEtiT APO USAGE FACTORS ARE THEff CALCULATED.

USItG AS!!E III te-36S3 AS A CUIDE. AT EACH STRESS POINT THE USAGE FACTORS ARE SUt3tED OVER ALL LDAD CASES Atc THE SUM ttUST DE LESS THAff 1.0 {9 I

     = .               . . - . .          -. .        -.        ._-. _

P CALCULATION 811600.02 tet(B) 382 CZC FATIGUE EVALUATION OF FOUR REPRESENTATIVE COPPONENTS i DESIGN It@UT

1) THE HUteER OF DBE EVENTS TO BE CONSIDERED IS ONE. THE PU BER OF DBE CYCLES IS 10 (REF 10)
2) THE HLASER OF OBE EVENTS TO BE CONSIDERED IS 5. THE tueER OF OBE CYCLES IS 50 (TOTALI (REF 103
3) THE tu eER OF SRV CYCLES TO BE CONSIDERED IS 900 ItLTIPLIED BY THE C0tPONENT NATURAL FREQUEtCY DIVIDED BY THREE (REF 8.9)
4) THE POWER OF LOCA CYCLES TO BE CONSIDERED IS 200 MJLTIPLIED BY t THE C0t@0NENT HATLTAL FREQUENCY DIVIDED BY THREE (REF Ill
5) EARTHQUAHE APO HYCRODYHANIC ACCELERATIONS ARE TAMEN FRON THE STRUCTURAL DIVISI2( CALCULATION (REF 13) Ate EtiGINEERING HECHANICS DIVISION CALCULATION (REF 123 1

4 m

CALCULATION 8 11600.02 804fB) 38 CZC FATIGUE EVALUATION CF FOUR REPRESENTATIVE CD PctENTS HATERIALS AFC PHTSICAL CONSTANTS THE HATERIAL PROPERTIES USED IN THIS CALCULATION ARE THE FATIGUE PROFERTIES CF THE CC:PONENT ffATERIALS. THE FATIGUE CURVES IN AS!!E III (REF 5,6) ARE USED FOR MATERIAL FATICUE CHARACTERISTICS. e e~M o

                                                                           \

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CALCULATION 3 11600.02 tal(B) 382 CZC FATIGUE EVALUATION OF FOUR REPRESENTATIVE COIPONENTS REFERENCES (1) CALCULATION 3 11600.02 taffB) 25 IA " DESIGN CALCULATION FOR THE RBCLCH HEAD TA!4KS IP42mTH 026 A1B (2) GOULDS PU!!PS,IrlC DOCUttENT 8 HE320 *SEISHIC STRESS AttALYSIS OF ASHE SECTI0tt III CLASS 2 PUt!PS - REACTOR CORE ISOLATION COOLItG SYSTEH LOOP LEVEL PLAtP", DY HC00ftALD EtG ANALYSIS CO. 4-9-76 (3) STRUTHERS HELLS REPORT "SEIStfIC AtELYSIS OF BOOSTER HEAT EXCHAtiGERS" 31-79-06-33475, 1-18-80

                     !4) VELAN EllGIrlEERItG CALCULATICH 3 SR-6082 "SEISHIC AttALYSIS OF 10" FORGED ECLTED C0ttlET GATE VALVE, AS'tE CLASS 300 LB. CARBON STEEL FAJCLEAR CLASS 2" (5) ASt:E III t.PPEt0IX I FIG-I-9.1 "DESICH F ATIGUE CURVES FOR
  • CARBON, LOH ALLCH Arc itI0H TENSILE STEELS" >
                   - (6) ASitE III APPCfDIX I FIG-I-?'2 " DES 1*sM CtAtVE FOR AlfSTENITIC STEELS,
                                                             .                                                   [                          ,

i4ICHEL-Cit 20!!IU:1-IRON ALLOY,tiICHEL-IRON-CHROHIUH ALLOY Ato IIICHEL-C0rPER ALLC(" (7) ASHE III 3ECTION t0 PARA. 70-3222.4 " AttALYSIS FOD CYCLIC - e CPERATI0t!" _ (8) CALCULATION # 11600.02 tiP(E) 450 FG " EQUIVALENT STRESS CYCLES FOR

                                                                                                                           /

PIPI!iG CO*PONEriTS - FATIGtJE F'lALUATION OF SRV AC10ATI0f tS" (9) "STPESS RESP 0tiSE IN HIGH FREQUEt4CY RAtr.E -' SIMPLIFIE0 PULTI DEGREE OF FREEDC!t SYSTLH UttDER tJ2BITRA 2Y StTPORT ACCELEPATIO*1 TIME HISTORY" , r (ATTACHitEMT 2 TO REF 83 4- 'i (10) STAT:DARD RrVIiH PLAtt SECTICf 3.7.3 "SEIS!!IC SUBSYSTEH ANALYSIS" SECTIct: II-2-B "DETERifIt*ATION OF t"Jt23FR OF EART:1QUAME CYCLES" r- /

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(11) "ACRS INFORMATI0ft REQtF.ST, !!ARN II PCOL DYNAllIC LOADS", LETTER FF0H H.CHAU, HARK II CaiERS GROUP CHAIRHAM, TO HR. M.HNEIL, CHIEF - ' CEt!ERIC ISSUE

  • E, rat!CH,FRC, JULY 0, 1981 -
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(12) CALCULATION 3 11600.02 f3t(B) 215 " DESIGN BASIS AlfPLIFIED RESPONSE ' E '

                             *PECTRA FOR THE SHORCHAM NUCLEAR;PO?ED STATION"
                                                                                                                     \

(13) CALCULATION 3116C0.02 NS(BI-092 - STRUCTURAL DIVISION CALCULATIGN

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           -, -./                                              FATICUE EVAltJATI0t4 CF FO*? REPRESEtITATIVE C0t70tiENTS                                              -

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l' s (14) CALCt%.ATION s'11600.02 fCT!S) 254 " PIPE HCUNTED EGUTPHE?iT LOADS" s (15) " SPECIFICATION TOR LCOP LEVEL PtAtPS" ti9 SH1-235. ST0t4E1HEBSTYR EftGR. CORP. 5-28-80J l (16) REV 6 OF THE SEISHIC DATA SHEET DATED HAY 1982. CALCULATION <

                                                               #11600.02 tot (B) 381 CCC (17) ASilE CODE. SEC III. DIV I. SUBSECTION te 1980 (16) " STANDARD HAFOC00K FOR HECHANICAL EttGINEERS". BAUHEISTER A HARMS. SEVENTH EDITION. HCCRAH HILL (19 3 "HAfiUAL OF STEEL CONSTRUCTION" SEVENTH EDITION. AMERICAN IriSTITUTE OF STEEL C0ftSTRUCTION IttC.

(20) "FORHULAS FOR STRESS AfD STRAIH". FOURTH EDITI0ti R.J. ROARK. IfCGRAN HILL (21) "FORI'ULAS FOR STPESS At0 STRAIN". FIFTH EDTI0tt. R.J. ROARM. HCCRAH HILL (22) " DESIGN OF HELDED STRUCTURES" otter H. BLODGETT MAY 1972 PRINTING. THE JANES F. lit:COLtl ARC HELDIFIG FOUteATION. CLEVELAfD 01I0 (23) "STRUDL-SM USERS HAPUAL" (ST-346) APRIL 1980. REISSUED AUGUST 1982. P.A.RAffCOURT (25) "HECHAftICAL VIBRATI0ftS". THIRD EDITION, J.P. DEN HARTOG. IICCRAH HILL (24) !!Ef t3 TO RICM GAUTHIER FROH P.TITUS/tt.YE0VASNY DATED 4-22-83 At0 RESP 0t!SE BY J.PCMERS DATED 4-22-83 TRArtS!!ITTING THE LOCP LEVEL PUt:P EXPECTED CPERATICitAL SEQUEtiCE THROUGHOUT THE LIFE OF THE PLAtiT. (28) "1977 At21UAL COOH OF ASTil STATOARDS". PARTS 1 THROUGH 48. A!!ERICAN SOCIETY FOR TESTIltG Atc itATERIALS. PHILADELPHIA. PA. (29) ItATERIALS SELECTOR GUIDE FOR 1973". IIID SEPTEtCER 1972

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CALCU.ATI0tt 8 11600.02 tetIBI 382 CZC FATICUE EVALUATION OF FOUR REPRESENTATIVE C21P0tiENTS (31) SPECIFICATION FOR THE REACTOR BUILDItG CLOSED LOOP COOLING HATER AfD SPENT FUEL POOL C00LItiG HATER HEAT EXCHA.4GERS. NO. SH1-190 SitEC. 7-19-73 (32) CALCULATIONS NO. 11600.02-AX-3AR-1 DATED 2-2-80 Ate 11600.02 AX

                -33N-3 (33) AS!!E III, DIV I APPEt0IX I,1980
(34) CALCULATION NO. 11600.02-NS(BI-092 "CONFIRHATORY ARS" (3S) CALCULATION HO. 11600.02-NStB)-20-JA. ARS TAPE NO. 001816 (36) CONFIRHATORY SPECTRA FOR EQUIPHENT, DOCHET NO. 50-322, OCT 1981 (373 PIPE STRESS. PIPE SUPPORT. AtID DUCT SUPPORT CRITERIA DOCUMENT FOR THE S110REdAH tCCLEAR PCHER STATION, SHEC 1981 (38) hat 0AL OF STEEL CottSTRUCTION. AISC, SEVENTH EDITION.1973 (39) "!!0CERN FLAttGE DESICit" BULLETIN 502. TAYLOR FORGE. FIFTH EDITION 1964 (40) SPECIFICATION FOR STRUCTURAL JOINTS USING ASTH A-32S OR A 490 BOLTS AISC,1978 (413 CALCULATION C12846.19 tei(B) 84 IA " REFUELING HATER STORAGE TATE" m

ne 1 1

CALCULATION 3 11600.02 ret (B) 382 CZC FATIGUE EVALUATION OF FOUR REPRESEtiTATIVE C0tPONENTS DETERMINED THAT THIS PARTICULAR VALVE IS ONE OF THE HOST SEVERLY LOADED 114 THE PLANT. ITS RELATIVELY HIGH USAGE FACTOR IS EXFECTED TO BE ONE OF THE LARGEST OF ALL VALVES IN THE PLAtU

                           -- StAttARY OF USAGE FACTORS --

COFF0tiENT MAX USAGE FACTOR R8LCLCH HEAD TAtH .064 LOOP LEVEL PUlP 0.0 (BELOH EtCURANCE LIMIT) HEAT EXCHANSER .063 10" GATE VALVE .3S IT IS EVIDENT FROH THIS STUDY THAT SRV FATIGUE IS NOT A PROBLEH FOR THE FOUR C0ttPONENTS EVALUATED, ALSO BASED ON THIS REVIEH IT CAN BE SAID THAT FOR SRV FATIGUE TO BE A PROBLEH FOR OTHER EQUIPHENT IN THE PLAT 4T, THERE HOULD HAVE TO BE Art IIPLAUSIBLE COINCIDENCE OF* A) LOH STRESS HARGINS FOR SRV TYPE LOADItG B) LOCATIOtt MITHIN THE PLANT MiERE SRV LOADS ARE SIGNIFICANT Cl C0f'PONENT FREQUEttCY RESPONSE THAT HOULD A!PLIFY SRV LOADS DI LOH COIPONEtIT DA!!PII:G THAT HOULD SUPPORT THE ASSUtPTION OF FtV3 CYCLES PER EQUIVALEtIT PEAN SRV EVENT El FATIGUE DERIVED FAILURE ItECHANISHS THAT HOULD LEAD TO UttACCEPTA3LE CONSEQUEtCES. F) IttPRODABLE POOR HATERIAL DEHAVIOR ADHERING TO THE STATISTICALLY CONSERVATIVE DESIGil FATIGUE S-N CURVES (REF S,6) _ ~ g l --

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CALCULATI0tt 8 II600.02 tit (B) 382 CZC FATIGUE EVt1UATI0tt OF FOUR REPRESErfTATIVE C0tPCNENTS SIMMRY OF RESULTS

                      .THE FOUR COOFONENTS CHOSEN FOR REVIEH HAVE BEEN LOOKED AT IN SUFFICIENT DETAIL TO DRAH CONCLUSIONS AS TO THE EFFECTS OF FATIGUE
               - ON THESE PARTICULAR COlPONENTS. NONE OF THE F0lst HAVE BEEN Foute TO FAIL THE CRITERIA ESTABLISHED FOR THIS REVIEH.

THE TAtM THAT HAS EXAMINED IS AT EL ISI IN THE SECormARY CONTAItttENT l#4ERE SRV LOADIts IS RELATIVELY SitALL. OVERTURNING H0HENTS DUE TO SRV BARELY OVERCONE THE TAtM RIGHTING H0HENT.THUS ANCHOR BOLT Ate CHAIR STRESSES ARE LOH. EVEN HITH THE FAIRLY HIGH STRESS Cot'CENTRATIONS THAT HERE APPLIED TO THREADS, HELDS. AND HOLES AT THE HOLD-006N DETAILS. NO FATIGUE PROBLEM MAS IDENTIFIED. ACTUAL N0ZZLE LOADS ARE SttALL. N0ZZLE STRESSES HERE CALCULATED BASED ON HElBRANE+BEteING+ DISCONTINUITY STRESSES Are HERE HELL BELOH FATIGUE ALLOHABLES. THE LOOP LEVEL PLAFS ARE AT EL 8 IN THE SEC0 TEARY CONTAItttENT M4ERE THE SRV ACCELERATIONS ARE SIGNIFICAtlT. THE GOLEDS PUFFS ANALYSIS HAS BASED ON STATIC GS MtICH ENVELOPED THE SRV PEAN (FRJLTIPLIED BY I.31 BUT REVIEH OF THE FREQUENCY CALCULATIONS ItDICATED ZPA VALUES HERE AFPROPRIATE. MITH THE LOHER G Vt1UES APPLIED ALL THE STRESSES HERE HITHIN FATIGUE ALLOHABLES. SRV LOADS HERE Foute TO HAVE A NEGLIGIBLE ' EFFECT Ott ROTATING PARTS. THE BOOSTER HEAT EXCHANGER HAS ALSO FOUND TO SATISFY FATIGUE CRITERIA. THE VEtDORS REPORT HAS SUPPLEHENTED SUBSTANTIALLY. ACTUAL PIPE LOADS

              - FRON AX CALCULATIONS HERE USED TO QUALIFY LOHER N0ZZLE STRESSES. USAGE FACTORS HERE FOUt0 TO BE SHALL. ANCHOR BOLT STRESSES HERE SHOWf TO BE BELOH THE EtDURANCE LIttIT OF THE BOLTING HATERIAL.

THE 10" VELAN GATE VALVE HAS Foute TO HAVE THE HIGHEST TOTAL USAGE' FACTOR ITOTAL U =.353 0F THE FOUR COMPONEfffS REVIEHED. THE YOHE ASSEtDLY HAS THE LIMITING ELEHEtiT OF THE VtLVE At2 HOST OF THE STRESSES Iti THE YOHE HERE FROM SRV. (THE SRV USEAGE FACTOR ALOME HAS .33). THE VALVE OPERATOR HAS QUALIFIED BY TEST AfD THUS HAS NOT INCLUDED IN THIS REVIEH. THE I

  ~              FREQUENCY USED TO CUA!ITIFY THE ff)HDER OF REQUIRE 0 SRV Ato LOCA CYCLES HAS THE C0!BItED FUtOAlfENTAL HATURAL FREQUENCY OF THE VALVE Are PIPE.
              ' THIS HAS FOUtD TO BE 36 CPS, OtLY SLIGHTLY LCHIR THAtt THE VALVE ALONE MCCPS) CECAUSE OF RIGID SUPPORT CotDITIOltS OF THE PIPE IN QUESTION.

icRtfAL CPERATIllG STRESSES DUE TO CPEtVCLOSE CYCLES DID NOT CONTRIBUTE TO FATICUE. THE VALVE 1:HICH HAS ST'JDIED IS IN A SYSTEli MiICH OtLY CPERATdS AFTER A LOCA. BASED Ctl A REVIEH OF. PIPE HOUtiTED EQUIPi!EtIT ACCELERATI0ftSe IT HAS W

w. - - - -- - , . . . .
       - . . . - - . - - - . . - - . - - .               ,.         .-           . . -   - - - , . . - . . ..~. -     ~ . . - . - - -

CALCULATION 8 II600.02 tettB) 382 CZC FATICUE EVALUATION OF FOUR REPRESENTATIVE COIPONENTS CONCLUSI0ftS THE FOUR COPPONENTS CHOSEN HERE JUDGED TO HAVE A HIGH POTENTIAL FOR SRV FATIGUE EFFECTS AfD FCR ALL FOUR THAT HERE STUDIED. SRV FATIGUE HAS tiOT FOUtB TO BE ItPORTANT. ALL FOUR C0tFONENTS HERE FOUPD TO SATISFY THE SRV FATICUE STRESS CRITERIA ESTABLISHED FOR THIS STUDY HITH NE HARGItG. 3 1 1 - 6

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22 Vaa ric as- o. 7 G. 23 $^t o w! ^J G THE A c=.r UA L NATJAilAL. /cR a.cR U S A.) C Y CS MG H F-A ~r- EX cNAM GER /At S TAtt A 7/ Co%l A P+s RTI C ut AlR. A t~cGL ERA - 27 T $ C3 L. K VK L C-O W R 6. 3 P OUD itU 6 TO Y tf/ : /UA T V M /Il CRC-29 QU5$ Of C A Al bd O $T& & Nl bl$$ o Paom Rar 's . 34 4 3,5 ri.11 c~ o mpo,aa-a rs eOnreieuruis ro rus. r om t- Acce t eeA r/o u Le vei- f oe rire s oun=nwr oossEsst+)s rut fuMos veni rst. fes o uca.ic y h = 7. 5 d 2 Hz 39 fon pcetoo O./32 sic)Ar7Nd ELE VAT /dd 8 FT of T/?C ei S&c CAJD AW C CkJ TA /A)/VEA) 7" A R a 2'>EG / h/ E D A c pot l owwg / 42 43 44 45 46 STONE P CEBSTER ENGINEERING CORPORATION CALCUL ATION SHEET & S010 65 &-/y - CALCULATlON IDENTIFICATlON NUMBER J.O. O R W.O. NO. OlVISION D GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE b /1 6 o O . o "2. A/ /-f [6) 38? C Z C.. 1 s D YM A M tC. l o s4 'D /N 6 4 Seco.uc.e a v coa rA /N. EL . 8 er R e f ( A t. c. A cc E t. ERA TION d's b Sacriod .D vHawc E vsN T- Dorrec rted p ,m p in g , 2 *4 4% '

  • t=onst cenoa Ns n rios] H'M A~S
  • G ~ 5

'o 3 b g Hoe E-W .0$ 05 , , , , , g 4 (co) Vee ri c al_. .O5 of 't 7-9 nw. H- S 04.5 04 's 7k C n ussinj s Hoe. E - W .036 05 8 k a v ic.<r t. .04 04 '5 91 //ca. Ar- s .o76 .o7 Sh S W - A tt VArncs Simx rA n, Hon. E- W . O 6 6~ O6  % to N //2 Vaa rie,<r t .oG .oG //ca. N- s .o7 .o4 i //A S R \/ - A D3 H o e. E.- W . O7 *OC ** 12 sa Ve e rie,a c .055 -oC N 1%% Ho g. N-s .Od *o4 23 15 6 $ g \/ . & q q g VA Lvt,$ j.go g . S . w ,o3 c_f ts Is4 Vs er r e nt ,of .03 /S8 Hoe.N-s 0a o3 /5 h 5 R V - OAJE VAL vE H otc. E - w' 03 0h lS VG R'rtc al .O2$ '02 \ Og5 Hamixoor .I& ** Re p. S '5~ V'**' ' ' ' 30 $oRtZoAJT. 25 3 '--- V's a rr e nt. 2C Al cc o,gD/A.)Cw 7~c:n ACIC . S $ 7'NG A CCdJ,.45 sqA 79QN C offsCC - 33 ** M eA/T,5 ARd OG fiA)CD A3 FoLL Ows : 35 S k \/ = EMELCpg ($RV- Att.) + (SR V- CA./C) + {3QV- bgdG)' 37 LO C A = eavet ( c o + CHuc-. ) Io ., uP S ET =. { O SE + S KV ' ] '!' 42 43 rn uato ~[ase'a.ac+ (sav-nos)t],,,' 44 45 46 STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEE T s wa s, G - J6 CALCULATION IDENTIFICATION NUMBER , .l. O. O R W.O. NO. DIVIS10N D GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGEdh NM(6 ) 18 C 00. 0 2 38t CLC 2 4 sRV s +/o g. a" 10. 0 75+ 0. Cd + t? 03 = 0, N5 . ds< v. h v's g. q'MVe V x 0. 0d+ 0. 04+ 0. 025= 6]/25 e $3 s 10 18 it 13 4 IS LO C A NC k . ,4 C b. $$Y 0. hh

  • h hh VE. A . f,y y 1 404&C.04=0.08 20 UP3G V C o AJ O / 7 ? O tt/ s a

24 N e 4.. [y =. O. / 6 -+ O. /s 6)%. r. C. 2 3 ,  : ve a. p-(o.isu o.asy% o.2e ti A V $ TS O A)O/ T* / O A)O If 0 R = $. 2 D,C8~+Q.O$);C.2l vaa p;-(o.nuo.oeso.os9%o.as 34 35 36 37 38 39 AU di et 43 44 45 46 _ _ ~ STONE P. JEB3TER ENGINEEICt4G OC3PORIT;ON ~ CALCUL ATICS SHEET A 5010 65 G-/? C ALCUL ATION IDENTIF!CATIOf NUMJEF: J' g / J.O. O R W.O. N O. DIVISION t5 GFOUP C ALCU. AllON NO. 'IOPTIONAL TASK C0!ah PAGE{ NH(6) ll6 0 0. O 2. 382 CZC i-i 3 ' h E GTI MR T/ OA0 Of E M6 E O.' EAJT b &OD i \ 5 D vr T O R ED LJ c T/19 *%) 1^l YHW .*\' O2 2 L & ' LCHz,32 r i -(' A ^) D 1 A.) THi S TA 7/C coEs= F/ C /4'NTS 'wi rH R PL'c s~ 'i' o Th os t,E' FROM R6r. 3 'THJ su)G W "5 Uhso&R 7 ,, e is LQADS Wi t. l. 66 ES T/ ^4 ^4 TE D S Y HAA'O u 9t CULJIT/lbt/U ' ,4 l. i, \ is t ' ' G 1 is .A1,e .,/- '/ 'V p.7 is e- ',- s 2o  % db ' f.;. ?r!l X% y ,, ,

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d ' / g,1, }ig.g f ar ~ , f f y{14 \ o.frs - , gT y 23 o

  • i 4

14 g M ,,9, . p , Mb nd') It'A *s 5 ' , gr

  • pi: /P' es M 'k'

'I q)2 f g , 27 I E - //7 A f e 7s X V - pI f vt j,'s - 'eh 2e g ' - m ]- u so b - - \ k'3 nW' gN,V'/%, t h' f . a %%,aa ,3, ,g S-=5 , 3' J 3, < ,z o +t"t ' . .,_  : e,, _2 e*#, . 34 k 3s 37 %IztGHr or cAce unor (v$cocco) W = 2 5//7-Le se p gg ' i 39 - g 'o ' Vy =. Fv, 49 , ~ <c  % = Pz . y Nozw e Lemas (t o u t ,, c eae) <4 jr

  • N Z L 4s My Nyg - '
  • M o M ,t f .

, P ,. STONE & CEBSTER ENGINEERING COQPORATION , CALCULATION SHEET ' mio se ! '!b - N , C ALCUL ATION IDENTIFICATION NUMBER 4 J. Cl O R W.O. N O. DIVISION 0 GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE ~/t b o'o , o 2 A//L/(s) b 8 2. C 2. c ~' N O 2.T L E L o ,4 D:s '* + (3EE /*. AD O A?c'c. 32.) p*,yt ygg [,g , v  ;. . ggg %ua P  % V,. M, Mv ^h r 2 /Yo 4.- B Ls LS on~. ls JC '7. L4 Fr 43 e' i s , ty, 5 2 E' 7/8 55% 774 to 34' 6 /4 f/4 7 .9/7 ft o 5 SW4 4C2d // 9 3 Ala / / 9 4' 2 ** E - // 7 A L N3 /3 24 1734 93 8 2. o 3 8 a324 /6o4 14 u ~ j bli, 73/ 792. SS/ /623 ll 9 2. // e / h 7 Nr 583 709 10 8 2. 845 /997 2iff i ) Nt i5/O b2 oz 1584 2 2 2 2. 38/C /s 2.S ** ; e i*42

  • E - //78 s

u Nr /tos RSS3 2 944 434C 2274 SoCE ] N4 8 40 /3 72. /d4S 38S7 /359 370s Resvi.rius L o ^ otr/* s w<sN A7 C S 's

  • t 4 i = /

L 2' ae F ,t6 = 0,707 I epa. + 2' I;h; + 0. 707 E %;

  • 3 E y h  %

s: Fy8' = o,7o 7 E Pn; + 2.fal; + o. 7o7 E Vyn; + W'i 7 3 I I N / 24

  • r ,!

M x = 2 R ai

  • 7t y Wm
  • 2.9 ,2 }A Vra M* ,

70 7 A /i + Wlh*' , \/Ibi '+

w. * , v , ,

'l _ +4 0 7, 0 7 My; Q. ,2 prg q. M,,)+3M, g g '*U V,L g $ y; , M'y ' O. 70 7 f$ Hy ',,,.+ k $f', + $ M,',,.}'+ $n/H' , + *:, + k' ( VL>.- o STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET a 5010 65 g_fg CALCUL ATION IDENTIFICATION NUMBER , J. O. O R W.O. NO. DIVISION & GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE //4 od 01 A/N/8 7 - 3 8 2. C%C t if L # f // L A Fz, ' O, 70 7 q Py/; 4 } Pr. + 0. 70 72 %i; s P"y = 0.70 7 $ Pb; 4 k Vk. + 0. 707 f Vb' + W" M{=$N0;+N $Vl'*/25 / ~2. > 3 V$: ~ Ml = ",*l# {0. 707@p"c + $\/n")] + "~f# V;+ 's + 0. 701(f My", + 2& %'l; * $ Nx a;) + f N nc i=*Q & ,e A4l =. 0 707(5&c + 24$ %"u; + t FVat) + f My"a. yg + 29{V"p,. is Fg p, f z, ' = 0. 70 7(52 C+ /14 7) + 1324 " 7 *5 d + " h

  • F$., + 0. 7o 7(553 + l/ob~) = 44// / e (~ )

Ff = a ro7(sa s- //4 7) + e s s - e s t + u Ff, ~

  • o.707f- S 5^$ + //05) - 2 b~// 7=-2505 to 0 3i M,, =-774- S~fd d-20 38 - /d 28 -

*'ia(55 3 ' /105) ~ *f fS38 + 8 3/)=- 3s =-17558 er -i.e 1 36 /V1 = l' 0.707f525-l/4 7 -S 53 + //OC} + ** +#~ ' - fS S 8 - 8 b /)+0.707foM + 4524 + *a + * ,f (T/9 -94 7)+ 7 74 + S 46 d) + 203f +/623 = /2 0 73.,4 l ., g,' ,, yi3 - 94 7 + / Th 6 - ? 4 l a 7/d <.e I i My =o.70700M+ 452s + ,?(7's 77+ sv46 t " "'3* * + 19 - e4rp/in. (173 A -]732 ) =. /4 4 / 8 STONE & CEBSTER ENGINEERtNG CORPORATION CALCULATION SHEET & S010 65 & ~ d_ O CALCULATION IDENTIFICATION NUMBER J. O. O R W. O. N C. DIVISION G GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE70 t ll 6 00. o t NA f(6) 3 g 1. cZ.c Fl,=- O. 707f383 + I5/Ch r // O b + 840 +0.707{toCZ+ /584): s =5/86te. F'y'  ; = 0.70 7 f3a b -/5/o)+ 2 844 -1848 +0 7o 7hio82 +/584)~ iy - 2 S// 7 =.- 24 44:1e Mx " =-845 .2z ze. -43+S=- 3 83 7- hos2 r '58+)- 's

  • 2_* {2 344 4 /843)n-2 8 244 er -c.e)

~ 1 'e f = AfA{o.7o7(38.3 -/.Tfo -to22+ 15840 + 20

  • 4 h~ ~ f S 3 2 344' - /8 +3) +

2S + o.707 h237 + 3 8/ $~+ nN7o3 - 3202)+ 8 CS'+ 2222] H345t3 t, =. /6 0 2 3 cr. te. Fl= 703 - 3 2 0 2. + 253,3 - /,5 72. = - / 3 / 2 te ,9 >o A4; =- Q 70 7h88 7t 39ts + ,',Y7os -s a o a). + 84 S + .1 e a z]+ 22M f 13534 a + f2s53 - t 3 72)= 92SC n. e.g. 3S C o m e t a.> t o L. o so.s ss 3,  % = 7/6 - / 3/2 = - S'36 se 'e l=v =- 2 50 53 - 2 f 464 = - 43 5'2 S a <o 1 Fz = 4'4 //+ 5/8 6.- 95 9 7 a <c Mx =- 1755 S - 28244 ,fHU ,#'stsc , = - 2o 73 2 cr.<r. * .. My = M 4/t + 3254 = 2 ' ' 79rr. ce ,, Mz = /2 o 76 + /5 o2.3- Q 7/4 + $ la /2. = 3 4 34 7 ,=7 .to i -. __ _ STONE & CEBSTER ENGINEERING CORPORATION CALCUL ATION SHEET , ~ s wa ss l CALCUL ATION IDENTIFICATION NUMBER J.O. O R W.O. NO. DIVISION G GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE i // 6 M , C 1 M M[0] 'S82. C 2_ C .INERY/A 40AOS ON 91EA T F WCHA AJ6 KR,5 D u t. 7"o SAuLTED coH Df Tf 0A).5. 6 5 f' = f[' = W p = 2_5// 7 0. 2 7 = 6 78 2 te o-C o fy' c l'l= W. ql= 2 S//7 O. 2 8 = 7033 is so d bv # o --- fo,, 13 is I6 i. To rAi /- e4a 3 >= 20 F' = f z+ S ' + jl' = 65 97+ 2 6 7 8 2. = 2 3 /4 / <e 20 cc 25 Fy Fy + ll+ ll = - 4 9523 + 2 7033 = - 3 54 5 7 . Fu = - s e d u T cs /vlx = ~ S o 7 s z 27 ,g + 8 / G 782 = - /5/ 7 70,r- m 27 28 30 Ml*24674erm 3' 32 M z = 3 4 3 4 7 sr_ ta 55 '/._ean.s /s ele s o sac 3 4 7 as X: 0. 5 fl= o. 5(-SS C): - 23 8 n le 2 a Y= Q 5 Ph + l2=0.5fa5457)+ 7 ,, , _ 74 74, , " Z= Q 5 F;+ $ t z : o.S. 23/U + 24 4 74/2 :I 6 300 ce <o l'S 8 th8 40 Mx = 9 s. M:=- c.5-{- /St 7 70) = - 7ses ae, s ar n. 44 45 46 STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET n G-22 C ALCUL ATION IDENTIFICATION NUMBER J. O. O R W.O. N O. DIVISION G GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE N' i/4o0. 0 2 NHl.8) 382. c 2.c l- o ads oN H ourdrts) 4 :a o'-T-s . . _._.1. _. ! __. . _ P . . _ 4, d% _, " 4 . i. 4 . _ . . . _ o *g ,a o g

  • 7

. ,4 8 I. . 13 +, ( 1 . l D/A SOL.T(8PL). a \/eR ri cx fo ecs. l', Mi

  • 3 4 i2 z '

ha_ g i Y-22 2(as'+2s % n' W ] 23 ** 75885 ~ S6 12. ~ M 74 / ~ 26

2. (3 C ' + 2 8 ' + / 2 ' + 4 ') S c'

.6 = 54 7 5~e (ra o sic,o) 30 'Tz' alsiL.c 5 rRE.ss y = %y = 5475 = 2 8 8 2. ps, 3e A ., I.90 33 35 WMA[ b T.

  • Y* v 0 /C 'TKA)St4 6 57 Msr. m A R KA.

s6 37 EF.dQ R k-/2 5 30 39 40 44 4 42 43 44 45 46 9 STONE 8 CEBSTER ENGINEERING CORPORATION CALCULATION SHEET g_y 1 & S010 65 C ALCUL ATION IDENTIFICATION NUMBER J. O. O R W.O. NO. DIVISION & GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE

N* I I 6 0o. 01. NN(6 ) SB 2- c 2c-Crese sc >R ce <

l Oaw ewc abeeon r Ienxs.s anexe srac_e i rue ornee nasLAde :suor:rso cus.n a m c.e nauss a som rue : s.:s tr s . ._ 9 2 'o saw L os o pse e ar r 1 , y (FT)% f (fi7]Y'- (sec ' + 23/6/ ^)k pg g i ,, 8 8 14 SusAR s r-R Es.s . ! d s orr 16 ,, ~S "- 288 O ~ / $ 64 ps,' i, ,e 19 T=As .I. 14 1 Wi1E R E. As - /, 74if, sygsic s ras as AecA ( (Rs p. 36 p. 4-/25) t2 es MA.x rsN:s1.Ed ,1rRS s , To=

  • f
  • Y =- g

**)*I66+*= 28 ! 30 = 3 ME esi i 32 Apoutua r e s a r u :s s

  • e oacen ran viad imcron Kp=4 As necciwN1eansa su Aer. /7, N/3- b2 32. 3 (A), Twe

's 36 ci si m i_ sresss /s: 3. 9/ = 4 36 42 :. /4 5 6 8 esi 39 40 4i f 42 43 44 45 46 STONE O CEBSTER ENGINEERING CORPORATION CALCUL ATION SHEET s wa ss G-24 CALCULATION IDENTIFICATION NUMBER J.O. O R W.O. N O. DIVISION & GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE // C co. c2. MM(S) SS z. c 2 c- . , , . _ . ._.. _ ....._ m. _ ._. . . _ . b CCCAl2>/NG .70 . kBP, /, j .. o 07.,.TML AtNOvAPA%/M L/M/T PC A ST E R.L- WITH IHK (JLT!.MA)TC STAE.A/s7N $0 MSI S AM A AR W O. :Eh' kk 37 EEL USA?O 80 ^3 7 & A' Io 8C4.T.5) / /4 . . . e E br Tu ." . N 00 W - 3 5 @# des / 13 16

0; e L (usce <sa m ) ox.

17 18 19 20 29 22 23 24 2S 26 27 28 29 30 34 32 33 34 35 36 37 38 39 40 45 42 43 44 45 46 7 + Calf.;LATION 5 11600.02 ret (B) 382 CZC - (ATIGUE EVALUATIott OF FOUR REPRESENTATIVE COHPONENTS ,t SECTION H FATIGUE REVIEH OF: 10" FORGED BOLTED BOttiET GATE VALVE HARN NOS.1E11*tt0V 039 A,B,1G41mtl0V 034 A,B SPEC 3 SH1-88V t PREPARED BY J. H0HE O a O H. PALIE .O O to 2 g- 1 9 v . W 00 to Q N O 1 m ' c 3:1 . T --d D ' l f , i STONE & CEBSTER ENGINEERING CORPORATION l CALCULATION SHEET & $010 65 g_j  ! CALCULATION IDENTIFICATION NUMBER , {/} J.O. O R W.O. N O. ll(,60,oa, OlVISION & GROUP M #A Ctt,) CALCUL ATION NO. SirL OPTIONAL TASK CODE C, 2- C . PAGE i ~ ' VELAN SR-608k ~^L . /o" FORGED BocTED BONNET C,ATC VALVE. A.5mE class 3Cc " . . .. . 5 CARBoM STEE L . _. .. . NUCLEAR CLASS: L. . .. MAM kJ0.'s . l/EII+ M6VO.M A, S . M4I 9 Mo Vo39 A, E . Sd. La SPEC.lF*t&NT16N: SH1-88\/ t3 '* /, $dCT/OA) 2-2 /S lN' C Nos7 0RJT/ CAL Sec 770^a //a THE YOKE AhIh (REn AELAN RCPORT SR-Gb82 892/,4)

2. vat-vE /6// X /U0\/039A IS THE o R,s T CAsd E>1

/MSMCT/o^) OF TRC 'G ' L 0AD.S / R* o f>? r#C AX 3. J T HE tJEA> bord-c 'FEvortT C.M cuterE.S 6'rzEss GASE.b OM A 5"g Dss <c+ Lokh TL0s ' TH usT Lo^b , TM GTcESS {}: * Foe. EAc4 IME(STIA LohbtM6 CONDmOAJ 1S CA LtJf.ME.b BV Sv6Trage_7/drs 7tt. T%usT . L o Ab Gree.GG F I?-o M T/ff. TOTAL STRE.SG AMb .40t TIPLY/AJ4 TQ15 VA4,0E Sy' 7Hf ktYf?of'9476 Y-.AT~to of Acc.ELG42.ATIos]S , M Mtsc.sb ap ykGE.G or nit. UG4)boe EEPot?X' A2.6. Yo OMh oM PhC-46 8'$ Tiktouc>+1 8/o a' g, h STEEAS C.r>UcEnTCATicN f Ac-To re. OC E /6 COM5En.AviuG- BECAve f RE. CACT STEEL, Yok4 2' 30 WM /Jo 6 IMP Eb6E.S 3 NoTc14ES,o E bl6coMT/MutriES A C.ROSS - SEc.7/clu OF YOKE' 33 e 2 ri---6 Y /9LL Co8,NE R.S RouMbED 3. u 37 e T/t 8 Nd YWAL [ f & f)(/GA/tl*T* $ bb Yh & $$fS% sv AX - 8f, BA' 40 gg 7"}} g y#o 6? 6 y 6 THE Grev9s bue To T b 7- toAb IS SM4LL s ( ' \ - huh %w rns rwsua Acce Limr hun nymee ,, /h4 T3E4u N E6 LEc.rt.) /U TH E. F M 4 0 4. E V At,0pmo A ) 45 46 STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET A 5010 65 H-2 C ALCUL ATION IDENTIFICATION NUMBER g' ' ' J.O. O R W.O. NO. DIVISION & GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE ll 600 , o 7_ MfA (M - 'S f 7 C E-C. - FRom VELA A) l SR- fo682. PA<,6 3 . FbR SEc r/oN 2-L _ 7^HE ST8 Ess . //U rdN s/Ty' . . S 8 2. = 1320 8 PS\

  • OL O 'G'

.VA u vs =. Eg's . hoo% tTuss tot m tWtort.Lo% (P%EA 83- M) SI 2 = lO6 2[ /GE tn Y' dALUE.S : 8 M(vdow.sT CASE. MOR 12[+. (1 3 t OEPJ[' /dEVJ 'G' YALUE OE'.E l G537.f + (.l t4 (0 Sf = } 'l$ SSE ) (,530f +0 + .l6 yf ' = l.z6 ShV l (Esss)%() ti.666Y' = 6.25 /-ocA o (2. 6/ 9)N(/ t /.3al)' ' = 3.50 , A)okmAe OSE. SSE SRV LotA 1 Tz-z. /06 W5 Jco 62 5 Jos LS* ios t C /oc25 t >'l8 ATIO I4 9$.o / /g } 21,ls,'e, 6 2fe ' 3.5lo . G'= 'G' % ritS 2.+4 5 232.o 752.g 1 7 +S7 , 26 /fg 2 2 2 2. 2. 28 30 KSCr 42.5o 4 28(>- .S+4o 2.6 5 4.2. /$S'?S A) 50 /0 266$6 3, 900h. s Alp w oo @ . Woo 34 '52433 /. j SS KS = STness Conceuranrson Fne,ck 37 N * % m S E R. OF CYCLES - 4'o YK DFC lOp = MumSEK Of CVCLES AlLOWG.b Fxom 4e A Sn?E S&cTtoNlit,DW I A PPEN blC ES , TABLC .[-9. I 43 44 4S 46 STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET & 5010 65 g_3 CALCULATION IDENTIFICATION NUMBER [' J.O. O R W.O. NO. lltooo , o t DIVISION D GROUP CALCUL A TION NO. OPTIONAL TASK CODE PAGE 1 9 M OA 37z Gac USEAGE FACYORS . . . . - . - YN ? . E &$ .[OK - AccepTA BILt.r Y ^ 6 NonntAL. t- 05G. t .SSE .+ SR\l + 1 OC.A S 'o o +..o

  • _o. +

+ 200 ,yg 3Rooo /31 M 3 '2 O .5.5 A l ok d.oA3ctostoM 15 TNd Yht VES /2/ik Nb\l00k.EL AND lG4/W (00\l0MA % y . NILL ld0 T FAIL. DOE .To .FA 7*t 6ut U/\sOGR THE 19 LO A MA.) L Lotd blTION % SPfCif/E4. 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 / 42 43 44 45 46 STONE E. WEBSTER ENGINEERING CORPOR ATION -s CALCULATION SHEET a us 11600.02 NM(B) 382 OZO /bE ). LL Lc0 - SHoREHAM - # 116 0 04 0 2." RvL /1sf //./ . ' G% - DYNAt4tc. ACCELEFATtoN AT VALVE OPEPSToR C.C*. . P R o e l. E M & ; Bof NODE #: 778 SY: *W DME g/ msg a : B F-1 aua * : R/u-nre eats : 2. /w/e3 h1STEk e : /E'// MARKn: I61IV RoVo296 G(s FoR .0AD CASE OBE SSE SRV Lo c.A AP X Qa= 4x onCg (G# EATER) io . 3 3 L. , f3 o 47/2- 2,459 2l7 It Y . lo 3 < /c y }.Gb6 /. 32 / .04 3 . E 220 I .YYo CG.YC 2.G/9 , 3/o l 17 UPSET: G = NORM AL *. d o8ES +- SRv " ( LC. 82.) l Ga* f , -go' + 5 6 5 r * =, g.7 3 t ,, Gv= t ,f, 3 # /,666 ' 2 /,7 \ 21 FAU LTED: G= NORMAL d SSES + 5RVS + LocA$- ( LC

  • G) se i( ,,#f + r. c cr % 2. c re : c. s

\ te Ov' ' t\ ,jg y '+ /r G 64 '+ 4 31/ ~ = 2./ 33 G= NoRNAL

  • 4 SSEE + A PS ( LC d '7) 35 m. , k hD
  • 3 36 3e ,/f f f pOh 5*

nog . ,, Gamo= LC % on LC W 7 [GRUJEA) JuEMARKS t 3 44 45 46 , . . . . . . . . . , w i. .. . g. .m i :. . .._ . c o .s o . ..o . y _ g-CALCU L.ATION SH C ET 11600.02 NMCB) 382 OZO 2 au L I t c_O ew.eu _sopair.Hett. PAGF- hO 2 soim ._ G 's oN j$0.M l ( 3 _ ll % D. C 2- Q u (8 ]-2 TA - C*.C- _ 4 Pr+eet e.a 5 MAWFACTVft1 'S PRIN'I: - . . . . . . _ . POINT 4

  • 8. [.

6 . . r . PRoGLEM # : 0.0 7 4... R U N C fo 674670 8 . . . .. . . ._. _.!..' s MsK **: : A X. .7 E' . 3 ! .!. ._ . cA r a. : J-~/27/e A. 10 - 11 SYS7 E M W /.4. .I. / . . . : . ...._$_ l ' .. . . . _ . ' . M O V O I 03. I8 12 - 23 .Ll N E. DIES 1 G N A'T*1 ON :t* _ . . . . . . . _ _ . . ._. _. . . ._VA LV E. #: . . . . . 24 ' / /e 2s . c. t ev^ r i c> tc .._..._.-_._: __.._._ . ti o V (G,q,,) zws r. .. 16 17 E XPER f E Man ACC E L ERAT'ED GS FOR LOA D CAS.E 28 19 nBC - /NFRT/A .SSE -- /NF#7 IA SRV- /NEPT/A L O CA -1A/FR7./A. [ 22 ~( _  % , 2 96'" . ro 4 - ~ ~r Y 7 7 ~- ~ iB 28 ~ ~ 22 .- . / ST' ' 'if f 3 3 7~' ~ . i t i-l 24 g . ._....; . .. .... .. .Q 8 .g.. 2s .264. . . . .4.r 7 /, +7/ ,/ - 26 21 -.... .. 2 .. . . . . . . . . 28 -. ...._. -._._....-r-_..._.. . ..: .. .- .... _. .. . og . ~ . . CO M fM C N T*S: __.......;..... . _ _ . . _ _ 6.j.__...___..__...__.. 30 Hoc tv oN T A L 5 - 31 . . . . 32 '7 ' ,, q n w e r'-b ,. +t . . 7 .,4 pW' b+ , hc----. W. - -[ --' 34 . i . . 35  ! r I~ '[~~ ~~ as . - j 4*7&gc up.ser \  ; *2.dr#"L. ,: r - --- - - - - - - , . . ..7......__......; ._ .. . .. - . . . . ! 3S l t 3, a ' C-i ,s .. 41 V E RTi cA L > ....p.. ah g # w 'g g,e 1 . . . . . . _ , . . . . . . 44 t 4 '. l l a. 4 veser = j , / 4- 7 t + , 3 P * = 'f y , . . _ . _ _ . . . . . . . . . . .........o w i. .. . . i . y. n . . . . c m . . . .. . . n . - ,H - 6 CALCULATION GHCET t_i_co 11600.02 NM(B) 382 OZO , i n,. v.o~._.M.O a c.M M . . PAG E ((_ l 2 sua O 's on ~ boy ( 3 - s oc. ot- w(M-zst ac_- , 4 .....,~. 5 MANUFACTVRE'S PRINT: . . _ . . . . POINT 4 I I f 7- i s . . l i PROBLEM # : 0 0 . 'Z 4 . ._. . .. . . ' _. , . .. . . . . ._ R U N :'. : R 06 7 + M o. 8 . . . . . 9 MsK 4* -. 4X M. - cATE .* _5~ z 7/g.2 . 10 . ' ,- ~ 22 sys I*E"M :W ! .. . . . . . _ k.I C-k. I ...*  !

1. .! '...... M O V # ! O M. A 12 -

l 23 Li N F._ DE.S tG N ATI ON :t* l _ . ... .__ . .. ._ _. .. ... . - _VA LV E. ?? * . .. . 24 .. . . . . . _....:_ '_.' , . _ _ . _ e a 25 . _ c L EVA'ri c) M: . . . _ _ _  ! ._, ..._. _ . R O Vm(_m, e.T ii,) .. 16 17 E XP ER IE MCED ACC E L E RAT'IED GS IoR LOA D CA S E_j_ ss - s . 19 ,__ - /28);~ - /NFRT/A S5r - /NEArY1A .SR V- /NFR'17A L OCA-1AffRTJA x 2 c1 -- . +. 2 s - q;.c,7 -- - /. g9g 22 ' / 3- < 23 ._ . I4 - , .L_ . . I '?. . . . --f 24 g . .. . . . . 25 . 2. . . . . a 90 - .... oo9 . . 74. ( 26 27 l ....a.- . . . . _ . . . . . - 2S 3 . . . . . _ . . . . . . _ _ . _ _ _ ... i. ., _ _ _ . _ . - . . . . . _ . . . . . . _ . . . _ . . . _ . . . CO M M E. N 'rS: . . . . . _ _. . . ._ n . . ; . . ' . . .. l _. .. _.L . . . 30 , , i gog if o g r A t 4g .; S . ... . . _ : . _. __ _ . ._ _.. 31 . , 8 ; - . . . __.... v . . . - . . . . . . . . . . Y ~ 33 kk e , 34 . ......L _I.... i _ . .j _; . .. ... . . . . _ . . . . . . . . . -~.. . . . . .. . ... ,I . . .; . i _.. :. -. i 35 - I i' h,'1. . ,l 9 uesei =1 - , 7 5* 2 Y + ,-{ .-.._.....__..!._. 4-1-;h-+ :- - 1 38 i ! 8 39 ' ' L V.E R rI cA L 6j,s-42 . . ,  ; . 2 = . .  % . . . , ' ~_ '[i i.3 FA ut.:T E D ~ \ .. ' , L l 4. - l-t ,r'l , k-; , ~r *rT V S p 44

  • t 4.

t I  !%.  ; e.="*- O n U PSE T _. \ ,,/'d 1 - - p ,:ff' 2,.L' ~ ~~ /

. 4e
  • l 49

.n' STONE P CES97ER ENGINEERING CORPORATION CALCULATION SHEET m2. 11000.02 NM(B) 382 OZO ~ PA6 E 2a , LI LC O - SHCREMAM - # ll(o 0 0 0 2. -NN6')-254 - c tc } )' Gi s - DYNAMtC. ACCELERAT10N AT val.VE OPERATOR C.G-PRCSt.EM & ; B07 fqopg # , _716 SY: I bmDATE.12l#/2 tl A%f MSK 4 : fM - % H - 2. gun 4: R/64 9347 M: 7f2. BL 3 bTSTF.M & ! IEll MARX #*. MOV 039 8 ' l Gv4 FoR t_oAD CASE l l

  • ICBE I SSE I SRV i ' ctA i AP i .

$  % .0.24o 0.41I 3.99 l 1.932. O.19 8 Gn' 4x QR% MAM) ' ,, Y 0.278 0. 45 (, 3.303 1.ll'l 0.165 O=Giy v l' , 3 0. t?. r 0.1% l.181' O.835 0.006 - UPSET: G = NonMALt 4 oss$ + SRvi ( LC. 8 2. ) 20 h 0.260 + 3.99 ; * = 4.01 f 0.17B S + 3.303* \ ,, ev= t 2 3.31 FAU LTED: &= NORMAL d SSES + SRV* + LocAS- ( LC

  • 6)

N' O. 4 n' + 3.99'l'4 f.932* = 4.46 I) Gv" t\ 0. 4 5 (,* + 3. 3 0 3* 5 1.1 rl * = _3.15 Grs MotAL,

  • 4 ssE S + A P8- ( LC 4 7)

# 0. t 9 B = 0 . 4 (o i h 0. 4 t l* 4 36 3, OV" 0.454 + 0 165' = 0.48 ' l - ',2; NOTE : - - Ge wn 5-LC *G cA LC # 7 (3GTER) AEMARKS: 43 se 45 44 l l =n----..--.-..-._ . . _ . . . . .. STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET , a soio ns CALCUL ATION IDENTIFICATION NUMBER J. O. O R W.O. NO. DIVISION D GROUP CALCUL ATlON NO. OPTIONAL TASK CODE PAGE // dos. e 2. HAflA./' 3 7 2. C&c f2E. Ceco tATIo _.7_u_ . &, (M.VE. GT9En U)rN 'T@uGT 'rce4E VEMo'JED M-F 10" FORGEL BOLTED BONNET HUCLEAR VALVE 4 s THRUST ' 2 ~

  • TR = 0.7854
  • DI AGL
  • DELTAP
  • SEATF + GF 2

* = 0.7854

  • 9.689
  • 575.00
  • 0.30 + 3181.00 to ll

" 7 = LOO = 0 bb5, Ms-rf : [fA4 l/f'S /f//NfddV 0] ydpA A AfD ,2 , /6-f frM6 Vo34 d,8 A46 // sax /At.t.y C.f. 03 C Dt/As&d b W/AAfrc 6MAJ75. ~ V-e ; ss e, is es, .s.s c) i4 TORQUE @fb f,g des vs ee"Aris> Hc V ,, TO = 12

  • STEM THREAD FACTOR * /sep u // WM 444 c# WE

^? Cps'<scco n = 12.

  • O.0l81
  • 15900. (y l/Alvs dA W 'S evcseconc sea r ,cascwcw/ peecmes is = 3457. IN-LBS fxic rio.a A u s /.s w a s "A c s s u x 6

( i ,, MT = + P'l

  • 8 ### * * ### "# ## 'D

= 34&T + 2000.

  • 3,000 Mew ^< < sA h osius Ts,'c V4 c 'sg.

4oeo diaset 7,yg VAuts A A'e N dA M A Ltj " W IN-LBS c e.cso p e x/ u s p y ggisic, g e s g 3 24 J A s .s ts 7r) As9e vE, TMs .sren T&A "ST $A C 6 WA3 )Mt 6'3S/OCAre INTERdAL C06PLE LOADS To ^~3 e 3/ des */cd's-r- >7> rsig FAr/s d4 Lik t s / -7H E Vs w e , 28 P2 = P1 * ( L + Ll/2 ) / EAVE G eg,cou .-7y,s/me & tA rr so 2000. * ( = - - _ - - - - - 7.375 + 10.750 / 2. ) 3, ___ _ _ ______________ ,, 7.583 53 = 3363. LBS 34 3s P3 = Mf / EAVE 36 = 945W. / 604 o 7.583 = 1349. LBS ?9/ 39 l 40 en t 4. l 43 44 45 46 STONE S WEBSTER ENGINEERING CORPOR ATION CALCULATION SHEET A $010 65 H'-9 CALCUL ATION IDENTIFICATION NI:MBER J.O. O R W.O. NO. DIVISION & GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE N4oo.oe Na tW/ 332 cdc 10" FORGED BOLTED BONNET liUCLEAR V'ALVE 3 4 s BEDDING MOMENTS 6 MZP = PI

  • Li / 4 ,_.

= 2000.

  • 10.750 / 4.

8 = 5375. IN-LBS ' (n) io MZD = ( 0.50

  • f.,74+PVERT) + P2 )
  • DELTA

= ( 0. 5 0 * (.,1.59etT' + 0.) + .3363. )

  • 0.0417

= 47t". IN-LBS st /4o is MZ1 = MZ2 = MZP + Mair /4o (**) i4 = 5375. + -4Pt"; is = 484tri IN-LBS SS/S MXT = P3

  • L1 / 2 /ed

= 424*T.

  • 10.750 / 2.=. 7') / W /0* 75/z

'8 = 44EHr. IN-LBS ,, #25/ ro MXIP= P1

  • L / 2

,, = 2000.

  • 7.375 / 2.

22 = 7375. IN-LBS 25 MXI = MXT + MXIP 6d a4 = .470$ . + 49f*5~.' = 4 2 S/ + E 75 23 -J 107 7 IN-LpS //425 (sk ) MX2P= PI * ( L + Li ) /2 er = 2000. * ( 7.375 + 10.750 ) / 2. as =18125. IN-LBS 29 MX2 = MXT + MX2P = 4+e.r. + 18125.= 425 / + 'B'E 6 3' =24400. IN-LBS 32 ZZ$16 (M9) 33 MX3 = P1 * ( L+LI + L2 ) 34 = 2000. * ( 7.375 + 10.750 + 2.750 ) 3, = 41750. IN-LBS 3' MX4 = P1 *( L + L1 + L2 + L3 ) 37 = 2000. * ( 7. 37 5 + 10. 7 50 + 2.750 + 1.900 )

3. = 45550. IN-LBS
  • MX5 = P1 * ( L + LI + L2 + L3 + L4 )

= 2000. * ( 7.375 + 10.750 + 2.750 + 1.900 + 5.352 ) = 56254. IN-LBS 42 43 44 43 46 } STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET g 70 A $010 65 C ALCUL ATION IDENTIFICATION NUMBER J. O. O R W.O. NO. OlVISION D GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE //4 o o. o z. /b/$6) 312 C 2C. I 2 3 10" FORGED BOLTED BONNET NUCLEAR VALV 4 *******************************************************E* * * * * * * * * *

  • s YOKE PN 89182 6

# ~ 8 SECTION 2-2 STRESSES CASE I - LOAD PI IN X-DIRECTION 10 ,, - AXI AL STRESS AT POINT 'U' - SY2 = ( 0.50 * (.M+PVERT) + P2 ) / AREA =( 0. 50 * ( M9tXT. + 0.) + 3363. ) / 5.625 i. = .24M4 . PS I 15 SY2Z = MZ2

  • C2 / IZZ

) , =.5846. * = 1.458 /2.685 W ##'S # 4 #S#f /E 4d55 ,e 22.99 'hM PSI 19 SYXT = MXT

  • 0.50
  • H2 / IXX 2a = H&$.
  • O.50
  • I .500 /3.1641 = 42S!" 0 S/ /5/3. /c4/

= -569. PS I too ? 'SY = SY2 + SY2Z + SYXT 23 = 3&47. + .3.Wr. + .S&eY. = $98 + 2 99 9 . soo 7

2. = .6776. PSI es 4400 ("d 27

- AXIAL STRESS AT POINT 'V' - 28 SY2 =( 0.50 * .(JW+PVERT) + P2 ) / AREA ,, =( 0.50 * ( 15900. + 0.) + 3363. ) / 5.625 'o = .2&tt". PSI mn 3 73 SY2Z = MZ2

  • Cl / IZZ

't = GettY.

  • 1.042 /2.6855 = SE/Ss / o 42/$.ust 33 = 3369. PSI 3, 2 /4fo Od

SYXT = MXT

  • 0.50
  • HI / IXX

=.903.

  • 0.50
  • 3'

= .J&?ff. PSI 3.000 /3.1641 = 42S! k 5 k 3 O/Its+1 37 zo cs ru) 3a SY = SY2 + SY2Z + SYXT 3, = 30tT. + 3iiHSS. + 4+7tI. = S pg + r/4 o s e o es * = 748ttr. PSI d' 47s3 ('") 42 43 44 45 46 STONE & CEBSTER ENGINEERING CORPORATION CALCULATION SHEET , CALCULATION IDENTIFICATION NUMBER [ J. O. O R W.O. N O. DIVISION & GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE \ swoo. e 2. W M f~4 ) .B r2 c s c. i . _ _ _ i -- -A m _ ... ... e- a . i 5 10" FORGED BOLTED BONNET HUCLEAR. VALVE 4 s - SECTION 2-2 ( CONT'D ) , CASE 2 - LOAD P1 IN Z-DIRECTION . . . . - AXIAL STRESS AT POINT 'V' - io SY2 = 0.50 * ( + VERT) / AREA ,, = 0.50 *( .+ 0.)/ 5.625 2t+$ f13 's SY2X = MX2

  • 0.50
  • Hi / IXX
i. @ @iM'r.
  • 0.50
  • 3.000 /3.1641 = E2 374#,.r pA fgg

= s14+ttT;' oso-) PSI) is Ug " SY = SY2 + SY2X = 44+3'. + 4+T70~. - O / 'O ## 7 's = _! 2 : 07. PSI /0607 %) no MAXIMUM SY e SECTION 2-2.= 14H'rf. PSI ('  ;,, /060'? 22 SHEAR STRESSES as ST2 = ( 0.50

  • P1 + P3 ) / AREA 24 =( 0. 50
  • 2 000. + SWT . )/ 5.625

,3 = M . PSI 9 ' ,, .5/8 7 PRINCIPLE STRESS & STRESS INTENSITY to 2, 2 2 3o SIGMA 1, SIGMA 2 = ( SY/2 ) SQRT [ ( SY/2 ) + ST2 ) /Odo? /0607 2 2 = ( 4&Hpr./2. ) SQRT [41&teur./2. ) + .397. ) 32 ss SIGMAI = '2:^C. PSI = /og/g J/8 SIGMA 2 = M . PSI

34 - P. S

S12 = SIGMAI - SIGMA 2 5' =+5+96. - ( ~44. ) = /0C/4 - (- 9. 7) . = 14208-37 /0425' P(*SI ) se ALLONABLE STRESS INTENSITY = 262S0. PSI (REF PAGE 6 ) l .o 4&RCE'. < 26250. l /oS 1s I CONDITION SATISFIED 42 . _ . _ . _ _ . . . _ _ i 44 45 46 l STONE & CEBSTER ENGINEEQlNG CORPORATION CALCU ATION SHEET A Solo 65 f/z-CALCULATION IDENTIFICATION NUMBER J.O. O R W.O. NC. DIVISION O GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE [8 4 //6 co. s z ' NM'(8) 3g2 C 2C i i S-r.csss /c/Must ry 2)UE '?b E5 yam ~7EVA U S T~ OUl- Y

  • p;a s e awas; . C4 e e v c.+rrows MsynduSW ' WA

/ya

  • cou rwsurra.,v sf 77Yf srA'dn AMocMf& V// W
  • Yo^;A S-r4M 7;MdVS f~ ACM 73 ~/Nd "fD T4 4 57ms ,

i2 7Tse VM' 14 's 7 't = / 5 9 e o A 16 17 D/2eur 19

    • 7~p = M y STEM ~77VAEAD AAcwd *'- 7'AC-

= TQ = 12 <0,0/21 x l6900

23 2S

                                                = 345'?             /W~ dds       -

es h1T = 7*Q + Pi 6 8 = 3 45 7 m -l S. te /N TERNA L C ouPL E t GADS 29 so 31 Ps =: MT/n ve = 34n/ 7,583 = 456 uss Bunciao- Momsu1~S ' 33 >< M 20 = 0,5x TR x 0,04/7 = 0. 6~ kit '900 k0.0!!!?= 3b-a SS ss MZ2 = Mzi =Mz o = 331

                                ^

se M x 7~ = P 3 x L ll2 = t f6 t 710. 75,/2 = 24 57m-c 6. <o (4 W I. = M % T = 2 4 (lia -t a 4, Afx 2 = MK T = 2 4Cl w -us. 44 , 45 46

STONE P. CEBSTER ENGINEERING CORPOOATION CALCULATION SHEET M /3

         .h $010 66 CALCULATION IDENTIFICATION NUMBER f              J.O. O R W.O. N O. DIVISION & GROUP    CALCUL ATION NO. OPTIONAL TASK CODE   PAGEAd_[

a $g CT/ o d 2 ~2 CYAESCES C A $ F f - f. 9 4 6 Pl'/4 A~D/RECTIOM s -AgrAL c rpegs g r poi ur "fj

  • SYk =. D TR,p!g,ggy a jftG, oft
     'o S Y 22 = M a2 x Cs /Zz z = 3 5/ x l.4J~r/2.Se s r * / 79 psi
     .N                          SY yT = MX 7 k d.T *Ss/Ixx = 2471
  • 0.7*/af/3.Itt// *Td'lPS!

SY c fdl/3 + /79 +T// r 2/ 73,ost. s - A x 14 t. $ TRESS krPold T " V " ce S Y 2

  • C.T TR/C6 zT w/V/3ps /

co S Y 2 2

  • IV2 2
  • CrlIEE = 3 3 / & l 01/ 3l2.6853' = / 3d pst b YX Y v MK T x C.T#Ha/1Xx .=2trTI "0.5t3l3./d4/ * //62pst a
                                $v = S Y2 +$ y 2 3 +$ Y X Y r /t.//3 t/tB +//C2 = 2.70.6 pCi
    's
                                                                                                 $x es (A S E 2 - l 0 4 /> P / ttl 2 -DIRECTION' 27 ee                                          -A X/ A L STRESS 47 Po/N T "l/
  • s
                                   $Y 2 ' 0,y e TA lA RE4 =-C.Tx / C990,/'$~62T =/$//.$,0$t n

S v 27 = M y 2 e 0. 7 < HilZ x x =245/ *0,74lg,/4 = //62pn

   ,4 S v = S Y2 +S y2 x = /4/3 t tit 2 - 257Cpsi ss SHsA R S rRES3 EJ s.

3T2 w Pg / preg .c 454/c.6s.r = 81pst 40 41 42 43 44 45 4s

STONE O CEBSTER ENGINEERING CORPORATION CALCULATION SHEET ,y ,p A 5010 66 CALCULATION IDENTIFICATION NUMBER J.O. O R W.O. N O. DIVISION 0 GROUP CALCUL ATION NO. OPTIONAL TASK CODE PAGE 75 0

                                                                  .--             _._.--.s             +

4 (L. J *s 1- _  ?' . 6 y ' ' '

  • 7 .g , , / ..

e V L , -y ' ,/_ , ,- 1O gg ~[ / p- 's tt 14 IS s ># , , 792wcn ots dr*v.s.s / 57:26ss /urwasiry 19 l l) .. lhN $

                                                                   ~~~

at gjggtgLy & ES (*j) mr [("g-)* + 2

                                                                                                                                              ]

26 2.705 - 2 703 = sisum = 2

                                                                                       + 3                             2 70 3 rst
                                  s te H41 '; 27. 03 -~ 2703                                .--                  =. o 30                                                                                         1 31 32 34 6ex. =                  5/6MA / - SiGHA 2
   's 36
                                                         =        2 703                        /SI 37 3e                                                                                                                                                     l 39 4l
                                   /2         /5      W84G b5 L O 4AJ W& $ U Df/A AA.)C.G

( ** 43 G wsr. j 44 45 46 l

I 1 SHOREHAM NUCLEAR POWER STATION - UNIT #1 l FATIGUE EVALUATION OF COMPONENTS OUALIFIED BY TEST Supplement No. 3 to the Shoreham Safety Evaluation Report (Ref. 1) addresses the subject of seismic and dynamic qualification of safety-related equipment. It was requested therein (Item 8.b) that clari-4 fication be provided "of how the fatigue testing was actually conducted in assuring that TRS's envelop RRS's and that the input loads cover suf ficient duration and number of SRV cycles which have been defined." That clarification is provided herein. It is first noted that, with few exceptions, " fatigue testing" has not been performed for Shoreham equipment. It is a requirement that tne

         - amplitude and frequency content of test acceleration inputs bound Shoreham requirements for combined seismic and hydrodynamic loads. Also, s            for tests performed since SRV loads have been defined, the required test duration has generally been increased from a minimum of 15 sec/ axis / test to typically 30 sec/ axis / test to account for additional SRV cycles.

]' Here " test" refers to each of the five OBE (or upset events) and the one SSE (or faulted event) to' give a total of 180 sec/ axis. l In order to further quantify the number of equivalent SRV cycles achieved, I a detailed analysis of an actual Shoreham test acceleration time history . has been performed. The objective of the analysis was to calculate the fatigue damage to a family of idealized components due to the test time history and compare to the calculated fatigue damage to the same compo-nents due to the expected number of SRV actuation events in Shoreham. 1 The equivalent number of SRV cycles inherent in the test can be inferred ! from this comparison. . The primary assumption made in the analysis is that for a comparison of test'and SRV event fatigue effects, equipment components can be idealized as linear single degree of freedom oscillators. With this assumption, fatigue damage is calculated as described below. First a family of oscillators was selected. The oscillators were chosen. to have frequencies in the ranges of Shoreham SRV response spectra peaks, i.e. . 8 Hz,18H, and 30 Hz; and also at 50 Hz which is generally above the range of SRV resonances. Each of these oscillators was then subject to one or more calculated re-i actor building SRV acceleration time histories. The input building time-histories used were three representative time histories factored up such

                                                                                                                     ~

that their resultant response spectra would bound all reactor building spectra within the frequency range of the oscillator being analyzed. l - Output displacement time histories were then calculated for the oscil-laters with 2% damping and the peak output displacements were then assumed to correspond to a component stress of 30 ksi as a reference point. i The same oscillators were then subject to six typical one second segments of an actual _Shoreham test acceleration time history (Ref. 2). The peak

        . output displacements were then multiplied by the ratio of assumed SRV peak stress to calculated'SRV peak displacement to arrive at a relative peak stress due to the test time history.

j

        ----gy--   --           w-vy'-    m'-m--y-ve,m'#eg r-y- lyW 43+ 'wW 8 y+ Weit      *- F = m -

W- W9 wg-p' *yy 3 - 9--NWur% gg n iw -g e-

l

  ,_                                               2 l

The test displacement (or stress) time histories were then searched for peaks (first derivative zero, second derivative non-zero) and each pair of peaks was taken as one half of a fatigue cycle. From the mean stress and alternating stress range for each half cycle, an allowable number of cycles is found using a set of fatigue damage curves based on figure I-9.1 of ASME III. A discussion of the approach used to generate the fatigue damage curves may be found in reference 3, page 270, in which the concept of constant fatigue damage curves is discussed. The net usage factor is then calculated to be: net allowable all pairs The equivalent number of cycles at the peak SRV stress level is then calculated to be: 4 SRV cycles " net " allowable at SRV stress This number, associated with 6 seconds of test input, is then multiplied by 30 to account for a total of 180 seconds of testing (for each axis). This number ranged from 1.2 x 106 to 11.4 x 106 for the idealized com-ponents analyzed. The equivalent number of SRV cycles in the test must then be compared to the required number for Shoreham. The Shoreham plant is expected to ex-perience 253 SRV all valve actuation events and a large number of single valve subsequent actuation events. Analysis of these smaller amplitude events has concluded that they are equivalent to approximately 650 all valve events leading to a total number of 900 used for design. The num-ber of stress cycles per event has been found to be generally proportion-al to the frequency of component response, i.e., f/3. The total number of stress cycles, therefore is 900 (f/3). For the idealized components analyzed this number ranged from 2,400 to 15,000. For all cases analyzed, the ratio of test cycles to required cycles ranged from 150 to over 2000 or a minimum factor of safety of 150. On this basis it is concluded that typical Shoreham test time histories have a more than sufficient number of equivalent SRV cycles to cover Shoreham requirements. I I

1- , References i 1.- " Supplement No. 3. Safety Evaluation Input for Shoreham Unit 1, Docket No. 50-322. Equipment Qualification Branch". December 27, 1982.

2. Shake Table Qualification Acceleration Time s

History for the Kaman KDA-HR Detector. Trans-mitted to Stone & Webster Engineering Corp. from Acton Environmental Testing Corporation via letter dated April 22, 1983.

3. " Engineering Considerations of Stress, Strain '

and Strength", R.C. Juvinall, McGraw Hill Book Co. 1967. 9 'I 4 i e r

                           ~ , , _ .           .,          , , _ ~ , _ . --, , - - __ . , , , . _.- -

e e AS OF 09-01-82 PAGE 1 SHOREHAM ttJCf. EAR P0HER STATION SHOREHAH CATEGORY I EQUIPMENT CHANGE RECORD CURRENT D ATE 06-21-83 STONE AND HEBSTER ENGINEERING CORPORATION EFFECT CH DOCUMENT S DATE OF ISSUE EQUIP. AFFECTED NATURE OF CHANGE SEISNIC QUAL. F-42213 09-08-82 IH21mPtt.-060 ADDITIONAL RELAYS TO BE ADDED TO CAT.I HASS OF ADDED 8'ANEL RELAYS NEGLIGIBLE-NONE F-40424J 09-09-82 1011mPit.-021 ATTACHNENTS TO SHID / RAD. HONITOR. SYS. HASS OF ATTACHHENTS NEGLIGISLE-NONE P-3930H 09-27-82 IH21mRH-40,41 CLEARANCE PR00. FOR 02 BOTTLE RACMS HCOIFICATION INCORPORATED INTO CALC 341-CZC-NOME F-42825 09-30-82 IZ97mPte.ER1-4 ADDITIONAL SUPPORT FOR H00ULE CASES TO APPROVED BY CALC. 292-CONFORH HITH TEST HOUNTING COtCITIONS- CZC-009 - NONE CAT. 1 PANEL P-3930L 10-05-82 1H21mRH-40,41 SUPPORT OF 'HARANITE I' FIRE BARRIER SHALL PLATES ADDED TO FRAME

                                                                                                                      -NO INJACT TO QUALIFICATION        i l

(CALC 341-CZC) 10-07-82 1R24*HCC-1119 ATTACHHENT OF 1" DIAHETER CotGUIT HASS OF ADDED CONDUIT F-184818 HEGLIGIBLE- NONEtCALC 311-CZC) F-43143 10-28-82 IT47eUC-17A.B N0ZZLE SUPPORT FOR (MIT COOLER APPROVED BY CALC. 8 356-HZ

                                                                                                                      -NONE F-39452E                   11-04-82          1D11mPtt.-21,22    1" DIAMETER COPSUIT ATTACHHENT TO           FLEX CONDUIT USED ON ALL CAT. I PANELS                               C0tMECTIONS-NONEtCALC 311-CZC)

F-43727 11-09-82 IT48eRC-002A&B ATTACH SH BORE SUPPT TO REC 0tBINER HASS OF SUPPORT NEGLIGIBLE-FRAHE (CALC. 8292-CZC-0083-NONE F-42897 11-12-82 1H11mHCB-01 BATTERY CHARGE / DISCHARGE APMETENS ADDED HASS OF fJMETER NEGLIGIBLE-TO HAIN CONTROL BOARD HONE F-29608A 12-15-82 IP50ePS-113A INSTR. STD ATTi.CHED TO STRUCTURAL PLATFORM APPROVED BY CALC 363-CZC ePS-113B ePS-105A

                                                           *PS-105B                                                                                  f IP50mPT-116A mPT-1168 ePT-111A mPT-111B IC41mPT-106

PAGE 2 SHOREHAH MJCLEAR PONER STATION SHOREHAH CATEGORY I EQUIPHENT CHANGE RECORD CURRENT OATE 06-21-83 STot4E 210 HECSTER ENGIf4EERIriG CORPORATION A EFFECT ON 00CUNENT S DATE OF ISSUE EQUIP. AFFECTED NATURE 0? CHANGE SEISHIC QUAL. 7 F-40154C 12-99-82 1297mPFL-ER1 ADD TERHINAL STRIPS TO FRAHE OF PANEL hASS OF TFR! LINA' STRIPS

                                                                                                                 -ER2                                                           NEGLIGIBLEtCALC.4?92-CZC-009)
                                                                                                                 -ER3                                                           -N0 tie P-3930Q                                                   12-09-82            1H21mRH-40             APPROVE GRItOING OF FAAHE FOR INSTALL.           APPROVED BY CALC 341-CZC
                                                                                                                -41            0F HTDRO. BOTTLES                                -NONE
                                                                                                  ,             -42
                                                                                                                -43 F-44635                                                  01-07-83            1633mFT-012            INSTRUNENT STD.-BASE PLATE HODIFICATION          LARGER PL & BOLT PATTERN USED/ APPROVED BY CALC.

292-CZC -NONE H&D 5520 02-08-83 1821mHSR-21 GAP REQUIREHENTS APPROVED BY CALC.8 332-JE 052 -NotiE N4D 5554 02-08-83 1633mPRR-07 BRACING HODIFICATION. HELD CLARIFICATION LARGER SECTION INSTALLED THAN , I ~ ' REQ'O -NONE F-43822A 03-04-83 IT48mPPL-t68A TUBE SUPPORT ATTACHHEdT TO CAT 1 PfNEL APPROVED BY CALC. 292-CZC-069A 001 -N0 tie ei F-45139 04-07-83 IT48mPit-068A TUBE SUPPORT ATTACHMENT TO CAT 1 PANEL APPROVED BY CALC 292-CZC

                                                                                                                 -0603                                                          001 -NOME
                                                                                                                 -069A
                                                                                                                 -069B F-431473                                                 05-09-63            IT47mUC-17A&B          UNIT COOLER N0ZZLE SUPPTS                         APPROVED BY CALC. 8356-HZ
                                                                                                                                                                                 -NONE r
               <p-22727C 05-19-83            1N43mPPL-C01A          CO2 STAtc SUPPORT INTERFERENCE                    APPROVED BY CALC. 289-CZC
                                                                                                                 -C08/11                                                         -NONE s

PAGE 3 SHOREHAM NUCLEAR PONER STATION SHOREHAM CATEGORY Z EQUIPttENT CHANGE RECORD CtstREUT DATE 04-21-83 STONE Are HESSTER ENGINEERING CORPORATION EFFECT ON DOCUMENT 3 DATE OF ISSUE EQUIP. AFFECTED NATURE OF CHANGE SEISHIC QUAL. i F-44182 11/24/82 (NSSSISTEAH DRYER / ADDS REDUteANCY AT THE NONE-APPROVED BY CALC 309-HF t SEPARATOR - SLING / POLAR CRANE INTERFACE HEAD STRONG 8ACM , F-44890 01/26/83 (NSSS) NSIV VALVES CHANGE ON NAHCO NONE-ITEMS REPLACED HITH (.IMIT SHITCHES QUALIFIED ITFHS , F-44170A 12/28/82 (NSSS) PANELS REPLACE EXISTING LEVEL & NONE-ITEMS REPLACED HITH IH21ePtL-04.05.09.10 PRESS. TRANSHITTER H3DELS QUALIFIED ITEltS HITH ROSDIOLRiT 1153 SERIES

                                                                                                                                              /

F-32304 12/30/80 (MSSS) PANELS ADD Ptst SLFPLY FOR ROSE- NONE-ADDED ITEMS ARE QUALIF fM 1H21mett-435.634 NOUNT TRIP LR4ITS HDDEL 8 5I000 i - F-32232 12/02/80 (NSSS) PANELS ADO ROSEHOLR(T TRIP UNIT . NG!IE-ADOED ITEMS ARE QUALIFIED t 1H11mPtL-601 HODEL 85100U l P-4429 05/14/83 1D11mRE-062 REPLACE 8440 ST.,STD'l t#ff NONE *EPLACEHENT ItS' ROVES THE  ! HITH A NYLON LINED LCC(ING PAJT HOLMTING CotBITION. l

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m_ _  % l SHOREHAM CATEGORY I EQUIPMENT CHANGE RECORD GENERAL ELECTRIC COMPANY 9 1 Document # DATE OF EQUIP. EFFECT ON (FDI/FDDR) ISSUE AFFECTED NATURE OF CHANGE SEISMIC QUAL. KS-01-1127 11/3/82 1B21*AOV81/82 Replace limit switches New limit switches qualified by test 121-88524 9/23/82 IE51*TU005 Modify hardware Modifications made to conform Shoreham Rev. 1 RCIC turbine to tested turbine KS-01-2144 11/11/82 1H11*PNL602 Add relays Relays identical to other qualified relays KS-01-2148 1/12/83 1H21*PNLOO9/010/ Change pressure New transmitters do not affect the 004/005 transmitters qualificaticn of the panel TFHN 9/20/82 IE32*PDTO38 Relocate device from Device qualified at new location rack to ship loose mounting KS-01-2160 4/22/83 1H21*PNLOO4 Change pressure New transmitter does not affect the Rev. 1 transmitter qualification of the panel. KS-01-2196 4/20/83 1Hil*PNL654 Change relay New relay qualified by test KS-01-782 11/14/80 1H11*PNL601 Add Rosemount trip New unit does not affect the qualifica-unit model #510DU tion of the panel KS-01-792 11/14/80 1H11*PNL635,636 Add power supply for New power supply does not affect quali-Rosemount trip unit fication of the panel model #510D0 L

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