nuclear regulatory commission · hebula 'ury lnformation distrlbuiio system (rids) acorn.bblun...

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HEbULA 'URY LNFORMATION DISTRlBUI IO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol )V~5o8 A U I ri ~ iver A riE I Uhr I LSD' ~ A ~ ktl 1 t ~ h!AMc YUUNGGLUUUgU ~ Jo : 81 V3150421 busquehanna busquehanna AUTEUR Vennsy'Iv HECLVLc Ll cen UuC ~ OATh,: 81/03/09 NOTAHlltO: NU bteam electric Stations Unit lr Vennsylva bteam Electric Station~ Unit C< Pennsylva A I- I- I L I A T L 4 N ani~ Vower a Light I.'o ~ Nl AFI lLIATCUN ssng Gr ancn 1 OUCKET ¹ VBVV VvV'388 bUUJt,I: I: I-orwaras documents re tac> I i ty'e1 smi c hyar oaynami c program for qual 1iication ol'afety related equ>pmentrper NHC request ~ Uocuments w> I I suppor t beismic Quail tication xev>ew I ~air b> te aua> t scneau I ea tor dl vd lo-v3c'.v. OIb I RIUUTIUN CUUE ~ B001b <Ul'LES HFCEI VEO:Ll'R EilCL SILf'e TITLE: PSAR/FSAR AMDTS and Related Corresponaence NOTES:Send I8E 3 copies FSAR 8 all amends. Send I8E 3 copies FSAR 8, all amends, 05000387 05000368 REC IP IEhIT IO CODE/hIAh'E ACTION: A/D LICENSNG RUSHBROOKghI ~ INTERNAL: ACC ID EVAL BR2b CHEM ENG BR 06 CORE PERF BR 1,0 EMERG PREP 22 GEOSCIENCES 14 HYD/GEO BR 15 18,E 06 LIC QUAL BR MECH FNG BR 18 NRC PDR 02 OP L IC BR PROC/TST REV 20 RAD SS BR22 FILE 01 NG RR25 COPIES LTTR ENCL 1 0 1 0 1 1 1 1 1 1 1 0 1 1 2 2 3 1 1 1 1 1 1 1 1 1 1 1 i 1 1 1 1 RECIPIENT ID CODE/h!AME YOUNGBLOODr8 STAR'Wry 04 AUX SYS BR 07 CONT SYS BR 0~ EFF TR SYS BR12 EQUIP QUAL BR13 HUhl FACT ENG BR I8C SYS BR 16 LIC GUID BR hrATL ENG BR 17 MPA OELD POINTER SYS BR 19 QA BR 21 REAC SYS BR 23 SIT AhIAL BR 24 SYS IhlTERAC BR COPTES LTTR E,"! CL 1 0 i 1 1 1 1 1 1 3 3 1 1 1 1 1 1 1 1 0 1 0 1 1 1 1 1 1 1 i 1 EXTERNAL: ACRS NSIC 27 05 ib ib 1 ~ 1 LPDH 03 1 1 MAR1 8 eggy i. d 5'f TOTAL hIUMBER OF COPIES REQiUlRED: LTTR ~ ENCL

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Page 1: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

HEbULA 'URY LNFORMATION DISTRlBUI IO SYSTEM (RIDS)

ACORN.bbLUN NoHI ACLL:OV 5ol

)V~5o8A U I ri ~ iver A riE

I Uhr I LSD' ~ A ~

ktl 1 t ~ h!AMcYUUNGGLUUUgU~ Jo

: 81 V3150421busquehannabusquehanna

AUTEURVennsy'Iv

HECLVLcLlcen

UuC ~ OATh,: 81/03/09 NOTAHlltO: NUbteam electric Stations Unit lr Vennsylvabteam Electric Station~ Unit C< PennsylvaA I- I- IL I A T L 4 N

ani~ Vower a Light I.'o ~

Nl AFI lLIATCUNssng Gr ancn 1

OUCKET ¹VBVV

VvV'388

bUUJt,I: I: I-orwaras documents re tac> I i ty'e1 smi c hyar oaynami c programfor qual 1iication ol'afety related equ>pmentrper NHCrequest ~ Uocuments w> I I suppor t beismic Quail tication xev>ewI ~air b> te aua> t scneau I ea tor dl vd lo-v3c'.v.

OIb I RIUUTIUN CUUE ~ B001b <Ul'LES HFCEI VEO:Ll'R EilCL SILf'eTITLE: PSAR/FSAR AMDTS and Related Corresponaence

NOTES:Send I8E 3 copies FSAR 8 all amends.Send I8E 3 copies FSAR 8, all amends,

0500038705000368

REC IP IEhITIO CODE/hIAh'E

ACTION: A/D LICENSNGRUSHBROOKghI ~

INTERNAL: ACC ID EVAL BR2bCHEM ENG BR 06CORE PERF BR 1,0

EMERG PREP 22GEOSCIENCES 14HYD/GEO BR 1518,E 06LIC QUAL BRMECH FNG BR 18NRC PDR 02OP L IC BRPROC/TST REV 20RAD SS BR22

FILE 01NG RR25

COPIESLTTR ENCL

1 0

1 0

1 1

1 1

1 1

1 0

1 1

2 231 1

1 1

1 1

1 1

1 1

1 i1 1

1 1

RECIPIENTID CODE/h!AME

YOUNGBLOODr8STAR'Wry 04

AUX SYS BR 07CONT SYS BR 0~EFF TR SYS BR12EQUIP QUAL BR13HUhl FACT ENG BRI8C SYS BR 16LIC GUID BRhrATL ENG BR 17MPAOELDPOINTER SYS BR 19QA BR 21REAC SYS BR 23SIT AhIAL BR 24SYS IhlTERAC BR

COPTESLTTR E,"!CL

1 0

i 1

1 1

1

1 1

3 31 1

1 1

1 1

1

1 0

1 0

1 1

1

1 1

1 1

i 1

EXTERNAL: ACRSNSIC

2705

ib ib1 ~ 1

LPDH 03 1 1

MAR1 8 eggy

i. d 5'fTOTAL hIUMBER OF COPIES REQiUlRED: LTTR ~ ENCL

Page 2: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEr (215j 770-5151

NORMAN W. CURTISVice President ~ Engineering IL Construction-Nuciesr77D5381

DOCKET NOS. 50-38750-388

Mr. B. J. Youngblood, ChiefLicensing Branch No. 1

Division of LicensingU.S. Nuclear Regulatory CommissionWashington, D.C. 20555

SUSQUEHANNA STEAM ELECTRIC STATIONSEISMIC QUALIFICATION REVIEW TEAMTRANSMITTAL OF REQUESTED DOCUMENTSER 100450 FILE 843PLA-655

Dear Mr. Youngblood:

Enclosed are the following documents relative to the Susquehanna SteamElectric Station Seismic-Hydrodynamic Program for Qualification of Safety-Related equipment. These documents were requested by your Mr. Arnold Leein support of the Seismic Qualification Review Team Site audit now scheduledfor the week of March 16 through 20, 1981.

1) The GE NSSS response to NRC FSAR Question 123.1, .3, .4, .5, .6,.7, and .9.

2) The previous response to NRC FSAR Question 110.42 concerning loadcombinations for the NSSS qualification of equipment. Refer to ourletter to NRC PLA-536.

3) Part of previous transmittal of slides from PPItrL-NRC SQRT meetingof December 18, 1980. Refer to our letter to NRC PLA-602, January 2,1981.

4) Bechtel Specification 8856-G-22, Revision 4, "General ProjectRequirements for Design Assessment and Qualification of SeismicCategory I Equipment and Equipment Supports for Seismic and HydrodynamicLoads for Susquehanna Steam Electric Station Units 1 and 2."

.5) A summary of our 3/4/81 telephone conversation with Dr. Lee.

By separate transmittals, we have, on February 26 and 27 delivered the I/Jfollowing PROPRIETARY documents to your Mr, Richard Stark and Mr. Morris Reich(BNL):

3 1 03130 I4~'ENNSYLVANIAPOWER 5 LIGHT COMPANY

Page 3: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Mr. B. J. YoungbloodPage 2

MAR 8 1981

a) A. Javid, C.V. Subramanian, M.E. Tanner, G.O. Usry, Seismic QualificationReview Team (SQRT) Technical Approach for Re-Evaluation of BWR 4/5Equipment", General Electric Company, May, 1980 PROPRIETARY NEDE-24788.

b) A. Javid, P.H. Gooding, "Generic Criteria for High Frequency Cut<)ffof BWR Equipment", General Electric Company, January, 1980PROPRIETARY: NEDE-25250.

The documents in this letter complete the information requested by the SeismicQualification Review Team. All final SQRT forms (3 page forms for NSSS and4 page forms for BOP) for the audited equipment have been transmitted to you.

Very truly ours,

4AN. W. CurtisVice President-Engineering and Construction-Nuclear

CTC/mks

Enclosures

cc: R. M. StarkM. Reich

NRC

BNL

Page 4: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Pursuant to Genera) Design Criterion 2. safety-re'fated structures,systems and components are to be designed for appropriate load combina-.tions arising from accidents and severe natural phenomena- V)th regard,& the vibratory loads attr)but% to the feedback of hydrodynamic loadsfrom the pressure suppression pool ot the containment, the staff requiresthat safety-related mechanical, electrical, instrumentation and.controlequipment be designed and qua'fified to withstand effects ot hydrodynamic

. vibratory loads associated with ither safety relief valve (SRV) dischargeor LOCA blmdo~a into the pressure suppression containment combined ariththe effects of dynamic )oads arising from earthquakes.

'hk. cr)tera to be used by the staff to determine the ncceptabi)ity ofyour equipment qualification program for seismic and dynamic 'toads areIKEE Std. 344.-f975 as supplemented by Regulatory Guides X.XQQ and 1.92,

. and Standard Review P)an Sections 3.9.2 and 3.30. State the extent to'which the equipment. in your plant amets these requirements and the aboverequirements to ccebine sexism)c ancf hydroxy'naeic vibratory loads. For

. equipment that does not ace'C. these requirements provide )ustificationfor the use of other criteria.

RESPONSE

The GK SQRT P", ogre spec|ffcak)y adresses both seismic and hydrodynamicloads using the criteria Found $ n TEES-STO-344-7975; R.G. l.9c.', R.G.

'

.300; SRP 3.2 and SAP 3.l0. VASSS equ$ pnent $ s 'not considered acceptableunless Tt is qua3)fied to the'above reqvireaents. Eqvipm nt not found qva3fAedto the above requirenents Hill be requalified befor ft is consideredacceptable.

Page 5: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

QJESTMN l23.3

Identify those ftens bf nuclear steam supply system and balance-of-plantequipment requiring reevaluation and specify bury reevaluation is necessary(i.e., because the original qualification used the single frequency,single axis methodology, because equipment is affected by hydrodynamic)r ads, or because both of the above conditions vere present) for eachitem of equipment..

Response (HSSS On)y)

'SYSTEM

Safety Relief ValveNSLVF3oe Element

:Recirc. Pump HotorGate ValveHCUCRO ValvesSLC Storage TankSLC Accumul atorSLC PumpSLC Explosive ValveBHR Heat ExchangerPHR PumpF)ov Orifice Assenbl'yLPCS .Pump 5 RotorFloe Orifice AssembTy~IV He~terHSIY BEomrHPC'f PumpHPCl TurbineFloe Ori'fice AssemblyRCIC PumpRCK TurbineFlow Orifice AssemblyFuel Prep machineGen. Purpose GrappleDryer 5 Separator Sling „Head Strong BackControl Rod GrappleRefuel $ ng PlatformIn Vessel RackDef Fuel Storage ContFuel Storage Vault

821F01382)F022/F028821 8051/52 /53/5483lC00783lF023/3l/32Cl20093Cl2F009/30/ll/l2

'43A003

C4) CONC4lF004E718003EllCO02El 3 Ml2/80l4E2lCQQ'1E21N002E32B00lE32C001 /MQ2E4)COOEE4)C002

E53C003ES) C002Es)n09lFl8EOOEF38ENlFi9EOCBF19E009F20EOOZF21E003F22E005F2ZE009F22EOl2

Page 6: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Page 2

guest)on 123.'3

SISTER

CON'ROL ROOM PANELS

Reactor Core Cooling BBPower Range Honitorfng CabinetRPS Oiv. l.and 2 Log YBRPS Oiv. 2 and 3 Logical VBfiSSS Temperature Recorder YBFeedYater 8 Recirculation Instrument PanelVASSS Process Instrument PanelDfv 1 RHR/HPCT. Relay VBDiv 2 RHR/HPC1 Relay VBAOS Ch A Rel'ay VBMS'eakage Control Div 2 VBHPCX Relay VBRCIC Be1ay VSInboard Valve Relay BoardOutboard Va)ve Relay VBDiv 1. CS Relay-VBgiv 2 CS.Relay VBDOS Ch 8 Relay VBBSIV Leakage Control Div 1 VB

'adiationHonvtoring Instrument Panel ARadiation Ronitoring Instrument Pane) SOperating 85Termination CabinetsPlant Operation Benchboard

NUCLEAR BDB.ER

* H12-P60181 2-P608H72-P609812-P611812-P614H18-P61 2N2-P613 -

.

812-P613'H12-P673')2-P628

H12-PGG4H12-P620812-P622H'}2-P622H12-P623H12-P626N2-P62?812-P631872-P655H)2-P606N2-P633812-P680HT2-P700 SeriesHJ2»P853

Condensing ChamberCondensing ChamberCondensing Chamber.Condensing ChamberCondensing Chamber.Condensing Chamber

821-D002B21-D004AB823-0006AD821-OO07AO821-0008AOS23-D009AD

LOML PABELS

Reactor Mater Clean-VpReactor Vessel Level And Pressure (A)Reactor Vessel Level And Pressure {B)Recirculation Pump AGet Pump B

H23-P002H23-POK823-P005'23-P009

H23-P010

Page 7: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Page 3

Question 't23.3

SYSTEM

LOCAL PANELS

Div. 2 (8)

-PO)4-P017-PM8-POH-P022-POSZ~P058

:-P074 . Dfv. 2'POM

~PO) ).PN5PM6

~POl9~P025~P036P038

~PGO)P042P073 ÃV. l

. P034P03TP030/3l/32/33

High Pressure Coolant Infection 8Reactor Core Isolation Coo1ing AResidua) Heat Remova) Channel AResidual Heat Removal Div. 2 Channel 8Recirculation PumpsDr@we)l Pressure Local Panel ADr~el'l Pressure Local Panel 8Hain Steam Isolation Va'tve Leakage ControlCore Spray Local Panel AStandby Liquid ControlPain Steam Flog jl/BHigh Pressure Coolant Inaectfon Leak Det.Core Spray Channel SMain Steam Flo~ C/0High Pressure Coolant InjectionReactor Core Isolatian Coblfho Leak Get.Hain Steam Flow A/8Fein Steam Flow C/QHa)n Steato Isolation Valve Leakage Con.High Pressure Coolant Injection D)v. l AReactor Core Lso)at'on Coo'fin9 Oiv 2 8 .SRH/ERR

Page 8: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

IgE YISI t21A

Describe the methods and crfterfa used to deterwfae the 'acceptaMlftyof the orfgfna'I equfpeent quaifffcatfon to meet the requfred responsespectra of Xtem 123.2 (iff)-

RESPONSE;

The methods end crfterfa used to determfne the acceptabHfty of the orfgfna)equfpment qualfffcatfon >nay be found $ n Genera1 Electrfc Company'sProprietary reports: HEbE-24788. Sefsmfc QunlB'fcatfon Re@fee Team (SgRT)Technkca'l Approach for Ra-Eyeiuatfon of BMR 4fS Kqolpment"„and HEM'-25259"Generfc Crfterfa For Hfgh-Frequency Cotoff of BMR Equfpment".

Page 9: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

QJESTRN 323.6

Describe the methods and cr iteria used to address the vibration fatigue .

cvc3e effects on the affected eqvfpment due to required 'loading condftions.

Response

'Vibration fatigue c>c)e effects for NSSS equipment designed to AQK coderequirements ms reviewed at CE by NRC consu3tants f'rom Satte3'fe PacificHortbmst Laboratories on October 7, 3980. The consu3tants stated satis-faction sfth the GE approach which encoepasses OBE, SRV, tberea3 andpressure cycles.

Non ASNE Code components qualified by test address the "strong motion"'hase of seismic and SRV dynamic. motion sufficient to generate nmximmequ$ prent, response these 'loads are contro34)no. GE testing genera34consist of 5 upset and 3 fau'3ted test of 30 seconds each which is about50'reater than required to address strong motion vibration.Non ASIDE Code components qua3ified by analysis genera33y ha.ie not, inWM~X, iQti'M'ac5ess . v>irm5Ow ah%:Clue cycre er Facts. 'in mnh.

~use<- mrs e<GwM are not .ad zez> qF tb~~>ACsaf)ne xesseA,

Page 10: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

If there are any problems pleasecontact Dahvidah at 8+408/925-2609This is the ninth of 9 pages

QUESTION 123 b

.Based on the.methods and criteria described fn Items 4 and 5, provide'he results of the revfm of the original equipment qua)ificat$ on with. identfffcatfon of fl) equipment which bas faH&f to eeet the required

response spectra and required requa)$ ffcation, and f2) equipnent whichwas fowd acceptable, together with the necessary $ nforaetion tIo jostifythe adequacy of the oÃginal qualification.

Response

Refer to the Response to Question 'l23 3 for the lfst of equfpment .

reevaluated by GE on the Susquehanna SQRT Program. All of the equfpmentlisted is qualified to SqRT Criteria w:th the exception ot the foHowfng:

821-F022/F028S31-F037/FO32CIZ-F009/FOlo

F011/FOl 2~ C41-A003

C41-FOX

~ E32-BOD1E41»CG02EH-EQOZF22-E006

, F22-E009

Hl2-P608

H23-P030-P03l-PN2-P033

163C1168

R72A8005

272A8006

HSIVGate ValveCRD Valve

A/E pipe acceleratfons requiredA/E pipe accelerations required

Si.C AccumuTatorSLG ExplosiveValve

HSKV HeaterHPCI TurbfneRCIC TurbineInvessel RockDef. Fuel StorageCont.

Power Range .

conf tor ingCabinet

SRR/LRN Pane)s

Test requiredTest requiredAnalysis of lube oil pipfng requiredAnalysis requi redAnalys)s required „

Test required

Test required

Flow Transmitteron H23-POD

Switch on H12.-P863

Switch on H72-853

Test required

Test required

Test equired

Data r.'equi red from'endorOperabfl fty def)ectfon ana7ysis requiredOperability deflection ana)ys$ s required

InforaQtfon to justify qua)iffc&tfonf'r the Site Audit will be availableInformation to justify qua) ification$ s avaf lab)e for NRC audit at GE-San

cif the equipment selected by the ."lRC

at the site for NRC inspection.of the venainder of th equfpm ntJose.

Page 11: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

UESTION 723.7

Describe procedures ind schedule for completion of each iten identiAed$ n Ltan 723.6 lj that r u0res re galiffcation.RESPONSE

The response to gvestion'23.6 'fists the equipment 'found by GE to requirerequa7ff$ cat1on along arith a statement defining the work to be performed.Nl requa4$ iicat4on vill be completed on a schedule sufficient to. permitNRC rev$ M prior to fue) load.'

Page 12: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

P~ ~

UESTION 123 99—To confim the extent: to ~h)ch the safety related equipment meets, therequirements of General Oesfgn Criterion 2, the Seismic qualificationReview Team (SgRT) vill conduct a plant site review. For selectedequipment, 5gRT vi3l rev$ e~ the coueined required response spectra (RRS)or the combined cfynam$ c response, examine the"equipment configurationand mounting, end than determine whether the test or analysis which hasbeen conducted demonstrates comp)iance with the RRS if the equipment +asqua'\if$ ~d by desi;, or the acceptable ana)yt>cai criteria $ f qualified byana)ys$ s.

The staff requires that a "gus)frication Svaeary of Equipment," ai sho~non the attach d pages be prepared for each selected p)ece of equipmentand submitted to the staff tm ~eeks prior to th& plant site v)5)t. Theapplicable should cake available at the p)ant site. for SQRT review e)4the pertinent documents and reports of the qualification for the selectedequipment. After the vis'rt, We applicable should be prepared to'submit,certain selected docteants end reports'or further staff rev$ er.-

M'SPOUSE

GE submitted "Qualif)cation Svnmry of Equipment" f'orris to PPSL onFebruary 20, 198T far the items of equi~ant selected by the AC forthe site audit hl'f pertinent documents and reports required to showqualification or" this selected equipment to the SgRT Cr iter ia xil'f be'ava$ 'fable at the site for the audit.

~ 6 ~

Page 13: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

ATTACHMENT 2

Page 14: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

SSES-PSAR

3088%'XOH 110 4Q:

FSAR Sections 3. 9.3, 3.9.0 xai 3. 9.5 cefereace several tables(3.9-2, 3.9-6, 3.9-17, 3.9-27, et" j that describe the variousl.oadinq combination considered in the design of ASNE Class 1, 2,xni 3 components, component suppocts, core support stru"tures ~

control rod driv compoa nts, aad other reactor internals.Qe have had discussions vith the Nark II Owner's 3caup concerningthe Load combinxtioas appropriate foc the design of BQR Nark ZKplaats. Ouc position vith resp "t to load combinations has beendocumented as Attachm at h to Enclosure 5 of the HR" lack IIgeneric Acceptaa"e "rit ria far Lead plants. this -taff positionis repeated her as Enclosure 110-2. these loadiag combinationsare applicable to the Susqu hanaa plaat.

Zh refore, pcovii a commitmeat that all AS'!E "lass 1, 2, aad 3components, '=omponent supports, core support stru=tures, "ontroLcod drive components, aai >ther rexctac internals have been vcvil.l be analyzed oc oth rvise qualified in a™cori@ace vithEnclosure 110-2, as mvdifi 2 by th folLoving tvo clarificatioas:

Cb)

Por Load cases 1 and 2 all ASNE "ode Service Level B

requirements're to be met, including fatigue usage factorrequirements, xai should take iat~ a""ouat all SRV dischargeload effects (initial actuatioa cad continuous suppressionpool vibratory) taken for the number of "ycles coasisteatvith the 00 yr. design life of the plant.P'or load case LO, SRV should be assumed to be one SRY.

QQSPOQS E:

Non-NSSS

Por load cases 1 aad 2 as ideatified in question 110.42,enclosuce 110-2, all ARNE =o2e Service Level B c quire~eats,includiaq fatigue consideration foc Class 1 =omponents, aremet for piping ia aon-HSSS ~ s scope.

Por load cps 10, SRVz (oa SRV) i" no't aasidecei incombinatioz vith DBh indecent loaves. Hovevet, the loadsresultiag from condensation oscillation and "hugging areconsidered in "ombinatioa vith the effe"ts vE SRVADS .

PSAR Thales 3 9-17, 3.9-LB, 3.9-23 and 3.9-27 are revised tvreflect the loaDing combinations aad acceptxace criteriathat are us 2 foc ASHR "~X "lass 1, 2 and 3 c>mponents an2their supports.

BEV 17, 9/80 110 02-1

Page 15: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

SSES-PSLR

NSSS

Load Case L coabinations aeet the cited staff position.Qeneral El "tric believes that tha loading coabination 3BE +

SRV~~y (Load "ase 2) ought to be consid red as an Emergencycondition- Zh classification of this los probabilitycoabination of l~ads as Emery ncy (Service L val =requirements) is consistent vith ll the encounter frequencyof the OBE, 2) the nuaber of conbined stress cycles expectedover the plant lifetime, and 3I tha intent of tha BSHE coda.Hovever, response to "ontinuad ragulxtory staff inquiry, GEagreed to aaat Upset Liaits (Service Level B raquirementslvithout fatigue analysis. The considerations for notconducting tha fatigue analysis involve the saxe technicalJustifications enumerated above Por load casa 10, SRV(one SRV) is not consider d in .combination with DBA indecentloads.

REV. 17, 9/80 ) j0 42-2

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TABLE 110.42"1

Load Case N SRV

ACCEPTANCE CRITERIA FOR NSSS PIPING 6 E UIPMENT

SRVADS OBE SSE IBA DBA(5) Acce tance Criteria(5)

B(l)

B(6)

D(3)

X(2)

X X(2)

X(2)

D(3)

D(3)

B

c(

NOTES:

(l) For load case l, all. ASHE Code Service Level B requirements are to be met, including fatigue usage.All SRV discharge load effects will be combined with mechanistically associated loads and taken forthe number of cycles consistent with the 40 yr. design life of the plant.

(2) Loading du'e to DBA/SBA/IBA is determined from rated steady-state conditions.

(3) Piping functional capability will be assured for essential piping per Enclosure 110-2 or" NEDE 21985;

„'l,

I I ~ ~II

'.,(4) Not'.used;I I ~ ~ I ~ ~ ~ ~

.,(5) ,'IBA and DBA,includes,all..associated loads such as annulus pressurization, pool swell, chugging, etc.IlI ~ ~ ~ .I ~ ~ ~ III ~

~ ~ ~ ~ ~ I ~

.(6) ."For load case 2I Iall ASHE Code service requirements are to be met, excluding fatigue usage.

(7) For specific load combinations refer to Table 3.9-2.

Rev. 17, 9/80

Page 17: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

ATTACHMENT 3

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OAD COMBINATIOilS 'i'ID ALLOt'ABLE ST,ESSES

(BAsis: SECT. 3.10C.1.4 8 3.10c.1,5 oF FSAR TAB( E 5.4

oe DAR..

~CSES

OBE

OBE + SRY

SSE

OBE + SRV + LOCA

SSE + SRV + LOCA

L '~1 STRESSES

1,25 Fs

1,25 Fs

1.50. Fs

1,50 Fs

1.50 Fs

. FS = ALLONABLE STRESS FOR NORMAL'ONDiTiONS (EXi! AISC ALLON)

. 'NOTE: DEAD LOADS AND OTHER OPERATiNG LOADS ARE ADDED TO THF

ABOYE CASES'

Page 19: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

4

CT N 0 RE ONSE SP CTR

0

0

0

ENVELOPE FLOOR RESPONSE SPECTRA

CONBINED SPECTRA OF VARIOUS DYNAfHC LOADS (GBE/SSEi SRVi

LOCA)

0 ASS SUYi

0 SRSS

EXAHPLE (NEXT T>!0 V!E'f-GRAPHS)

~ ~ ~

~~

~ ~

o'~ 4~ ~

~ ~

\'I

~ ~

C T

~~

~ ~~ ~

I\~,\ ~

Page 20: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

ATTACHMENT 4

Page 21: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ ~~ ~ ~

00> I

~ ~

~ ~ I 0 ~ ~

~ 1 0 ~ ~ ~ ~

~ Q 0 ~ \ ~

~-

C 9C ~

~>~ SEEW --=-oo oo

ao ao

%%855.. ~WNHK"

amma

rAH

o ~ s ~ e> ~ ~ t!r~o>y o I

~ .~ oo ~

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IKRKIKEiuVIIRFLRRMkRSISRIII5%5%RRRSEPS2IRb85ÃSR%kPM~GK% i oo'F&ipRERP~~~

aaF" M.MNRXW~~RaR &XIRR5&EE~Klo~

~o

~ ~

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KER~ ~ ~

ao

Page 22: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ ~ ~ gpgg'~ion 8856-G-22Revision 4

GeaZAL MGKCT

DESIGN ASSESBEZZ AND QUALIFICAYEON

SEISKEC CATEGORY I E@IBQ!ÃT AND EQUIBKÃZ SUPPORTS

KB.

SEISMIC AND EKBGDYNAKEC BROADS

1 0

2 0

3o

4.0

5.0.

6.0

7.0

S.o

9.0

10. 0

'11.0

@[ Aypealix A

Scope

Equipnent Classification

Equipnent Location

Dynamic Loads and General Des~ Criteria

Load Ccmbinations and Allowable Stresses

Qualificat5.on Methods

Dynamic Ana3Zsis

Testing,

Ccmb&ed Ana1psis and Test~Ed.dence of Compliance

Certification of Compliance

Quipnent Qualification Report Suaaaaxy

NZE: gee applicable RESKNSE SPEClBA Load Canbinations and AcceptanceCriterM are included Wth the Material Requisition or TechnicalSpecification cover~ that" item-

(P2Za-lrZ)

Page 23: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~~

» Speeit'i.an 8856-0-22Hevtsion 4

»»»»»L |»»1»»» BKÃVBIWK»HR

DESIGN ASSiZPKMP AND QUALIFICATIONQP

SEISMIC CA~BY X KgXBfEVZAND EQUZEMBU SUPPERSP3R

SEISMlC AND HYIRODYE&ZC lDADS

1.0 SCOPE

1;1 Genera1

This Specification covers design assessment and» qualification of seismic Category I equipnent,

.- -..... equIIment supports and systems for seismic andhydrodynamic loads by anQysis and/or testing f'rthe Susquehanna, Steam Electric Station Units 1 and2 in accordance wi&methods and procedures speci-fied herein. Mherever the word "equipnent" occurs,it shall &elude equipment, equipnent supports,equlpnent anchorages, and systems furst.'Red by ~Seller-

»

1.2 Mod Included

»»»», ~

1 2 1 Submitting Q~Ms for.'~~ and a~vM of all methodscies, and procedures to be employed to as-sure ccmpliance with the seismic and hydro-dynamic requirements as defied here&.

1.2. 2

1.2.3

~»'»»ld . » ~.~lsupervision, and the performance of all oper»ations and incidentals necessary for dyneinalysls, design, and/or testing of,the equip-ment as required herein.

Runishlng of calculatIons and/or dynamic testdata for the equipment as required herein.

Purnishizg the interface reactions due to allrequired load ccmblnations at the suppor ~ pointswhere the Seller's Items are supported.

(P22B-1/3) »

Page 24: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Specifica51on cog ~c-

. Revision 4

l03 Work Not Included

Purvdahing of calculations or test data to in-sure the adequacy of equipaent supports pro-vided by the Ever.

Definitions

. Seismic Category I Equipment: Equipaent that is es-sentihl to emergency reactor shutdown, or otherwiseis ess'ential in preventing signif1cant release ofradioactive material to the envtrorment or is neces-sary to keep the plant in safe shutdown condition.

Safe Shutdown Earthquake: ~ earthquake which isbased upon an evaluation of the maximum earthquakepotential. Xt is Chat earthquake ~ch produces themaxhnzn vibratory ground nation for whi.ch Category Istructures, systems and ccmponents are designed Co'enal functional.

Operat~ Basis Eart;hquake: Ghat earthquake which, could reasonably be expected to affect the plant sitedur~ the operating 1Lfe af the plant; it is thatearthquake wMch produces the vibratory ground mo-tion for which those features of the nuclear power

. plant necessary for continued operation vd.thout un-due risk to the health and safety of the public aredesigned to remen functional.

Response Spectrum: A plot of the m~mnn responsesof s~e degree-of'reedan linear systans of dif-ferent natural frequencies at given damping valuessubJect to the same specified base motion.

R.oor Response Spectrum: Ghe response spectrum of afloor motion. Chere are, in general, response spec-tra for two perperdicular ?qr&ontal directionsand one vertical direction.

Required Response Spectrum (HHS): We response spec-trum of a motion for. which a piece of equipnent or

'ystem1s required to be qualified. Ches motion isthat defined at the equipnent sUpport-

Test Response Spectrum (TBS): '2m response spec-trum of the test Kaput motion.

Page 25: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ ~

Specif i.cation 885 2Hevtsion 4

Dynanic Degree of Preedom: Coordizmtes for whichaccelerations are considered in the equations ofmotion.

< 4 w~Rw1

Narrow Bard Response Sp.ctrum (NBHS): A responsespectrum wbich has a high peak caused by existenceof a 1arge annunt of humonic notion at scme fre-qmncy, usually caused in floor sp ctra by theresponse of a building in one of its modes. Narrow band response spectra shaLL be. designated assuch by the Buyer on the spectra furnished by theBuyer to the Seller.

NaturaL Prequency: The frequency at which a bodyvibrates. freely, without the application of ex-ternal forces in one af its naturaL nodes.

Natural Node: One of the characteristic shapes ofa body in which in free vibration all points de-scribe a synchronous motion.

Ploor Accelerat1on: Ghe accleration of a particular

fran a given motion applied to the foundation levelthe buQ."'"~. Tne ~num floor acceleration can

. be obtained fran the floor response spectrum, as theacceleration at?dgh frequencies (in excess of 33 Hz

loads and 80 Hz. for hydrodynand.c load),and is scmetimes referred to as the zero perLod ac-

. celeration (ZPA).

Ground Acceleration: 9he acceleration of the groundresult~ from a seismic event. The maxim groundacceleration can be obtained fran the ground responsespectrum as the acceleration at high frequencies.

'aLfunction: The loss of capability to initiate orsustain a required function or the ird.tiation of un-desired spurious action.

Sine Beat: A cont~ous sinusoid of one frequency,amplitude aadulated by a sinusoid of a lowe.r fre-quency.

Transfer function: A canplex function of frequency~ch represents the transmissibility of a systanbetween the output motion at a given point and

'heinput motion.

Page 26: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Sp=cification 88 22Revision 4

References.

1.5.1 "ZEEE Reccmnerded Practices for SeismicQualification of Class 1E Equipnentfor Nuclear Power Generat~ Stations"IEZ Std. 30%1975.

1+6 Bibli ra

1.6.1

1.6.2

1.6.3

"Seismic Qualification of Electr ic Equip-ment Tor Nuclear Power Plants" U.S. NRCRegulatory Guide 1.100.

"General Prospect Requiranents for AseismicDesign and Analysis of Class I Equipn ntand Equipment Supports for the SusquehannaSteam ELectric Station Units l. ~.2.".Specification 8856-G-10 Revision 3.

"Seismic Qualification'- Philosophy andMethods" by C. V. Roberts and G. D. Ship-way. Journal of the Power Division,Proc. of ASCE, Vol. 102, No. PO1,Jan. 1976 pp. 113-120.

2.0 EQUIPS CLASSIFICATION

Allplant equipn nt is classified as either Seismic Cate-gpry I or Non-Seismic Category I. %he equipnent technical.specification will designate the classification of specificequipnent. ~ Specification 8856-G-22 is not applicablefor equipnent.which are not Seismic Category I.

3.0 EgIPPHV LOCATION

Equi.pmnt are located within the several buildings whichccmprise the Susquehanna Steam Electric Station. TheResponse Spectra correspording to the equipnent locationare issued. with the equipint technical specification.

4.0 rmeMIC rOADS AND @FERAL DESIGN CRITERIA

All equipmnt under this specification shall withstanddynamic loads result~ fran (a) Seismic Loads and (b)Hydrodynanic Loads in addition to all other applicableloads. 9he method of canbination of these dynamic loadsand acceptance criteria.are provided in the equipnenttechnical, specification. Rim functions of the equip-ment instrumentation and'controls or other parts, which

Page 27: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

. Specification oogaRevision 4

. are. necessary for the functional requiranerits of the equip-ment shall not be ~red Men these dynsad.c loads areapplied simultan ously in accordance Mth the applicableload canbinations. 'le funct1onal requireaents of the

. equipment are stated in the equipnent technical specification.

4.1 Seismic Loads

Seismic Category I equipn nt shall Mthstard sinM1-taneously the borstal and vertical Canponents ofSupport motion caused by the "Operating Basis Earth-quake" (OBE) and the "Safe Shutdown Earthquake" (SSE)

The Seller shall be responsIble for assuring that theequipnent is designed. for the followimg conditions:

(a) Tjo rezafa functional. so that a safe and orderlyshutdown of the plant can be achieved arxi ma~M'tain d after experienc~ a SSE ~ch has beenpreceded by OBE's.

(b) To renal operational and to perform itsfunctions as required for the continued opera-tion of the plant dur~ and after experienc~an Operating Basis Earthquake (OBE).

The functional requireuents of the equipn nt dur~and after-SSE ar OBE are stated as above unlessothe~se stated, In the equipnent specification.

Qualification (testing an4/or. analysis) sha11 bedone for required load ccmbinations specified Inthe equipnent specification for both. the OBE arx}SSE

4.2 dr c Loads

The equipnent ard equipM.nt supports shall Mth-stand dynand.c loads associated with Main SteamSafety relief va1ve (NSRV) discharge thermo-hydro-

l dynand.c phencmena and Loss-of-Qmlant accident(LOCA) hydrodynamic phenanena in addition to seis-

'd.cand all other applicable loads according to:.load canblnations given In the equipnent technicalspecification.

Page 28: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ .. '. Specif1cat:ion 88<6-2'Revision 4

I

4.2.1 Loads Due to SHV Ac~tion

Loads due to SHV actuation is considered asa nodal operating condition loading. Responsespectra due to syrrrnetric ard asyaretric SHVdischarge loads:~ be considered in theequiprent assesszerrt.

4.2.2 Loads Due to IQCA Related Loads

LOCA irxluced loads on the SSES containrMntstructure are characterised by leads associatedwith poolswell, cczdensation osc11lation andchugging loads as mll as long term LO:A loads(due to air bubble pressure).'esponse spectradue to al1. these conditions shall be consideredM the equipaenf; qu~icat1ons.

Ghe above'hydrodynamic 3.oads are developed inthe suppression pool of the containmentstructure; however,-all structures that are incontact Nth the contadrrnent structure atthe foundation or any odor level wQ3. alsobe affected by these loads.

We appropriate response spectra for hydrodynznicloads for the subject equipnent are contained inthe, equipnent technical specification. Weseresponse spectra are developed based upon a finiteelement dynamic analysis of the contairment structureaxd adjacent buildings, sub)ected to input motiongenerated from the conteiment response.

*

5.0. TOAD CCKKNAT10NS AND ALElMABLESTRESS'11

Seismic Category I equiprent shall be designed for theloads ard load ccmbinations given in the material requisi-tion or the equipnent technical specifications. For allload ccmbinations ixrvol~ dynand.c loads, the effectof both hor~ntal and vertical dynam.c loads shall beconsidered. as arising frcm excitation M all three principaldirections and ccmb&ed as specified for the particularmethod of qualification.

Stresses ard deforpations due to the ccmbined loads shallbe within the limits specified In the material requisitionor the equipment technical specifications. Ghe stressesand defozmations due to the maxltmum effect of the canb1ned

'oadsshall rea~ within sich 1frnits that the requireaentsaf Section 4.0 regarding the dynsnd.c loads and the

functional'equiranentsof the equipnent as specif1ed 1n the technical: specification are net.

(P22B-1/8)

Page 29: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ Specific tlon 55> '-c~'evision

6.0 QUALEF~CA~ON METHODS

In the absence of more specific directions in the equf.pnentspecification, the Seller shall prove the adequacy of thedesign of the equipnent by one of the folio~:a; Dynamic analysis (Section 7.0)

b. Testing under simulated conditions. (Section 8. 0)

c. Canbination of Cesting and analysis. (Section 9.0)

%he choice shall be based on the practicality of the methodfor the function, type, st, shape, and ccmplexf.ty of theequ5.pmnt anl the reliability of the qualification.

For the qualificaion of electrica1~ amtxol systaas, anR instxurrentatianequipnenC, requizeaents outed. in, the ~-'344-73 shall also be fol-1 d. 'l' b th ~

ftt'he

Se1ler shall clearly Justify the'election of the methodof qua.Lification.

The Seller may elect Co consult with the Buyer with respectto setting up a qualification program.

7.0 IZNANKC ANALYSIS

7.1 Methods and Procedures

. The dynamic analysis of various equiprent can beclassified inta three cases according to the rela-tive rigidity of the equipaent based on the mag-nitude of first natural frequency as below.

(a) Structurally simple equipnent —that equip-ment which can be adequately representedby one degree of freedan system.

(b3 Structurally rigid equipnent - thaC equip-aent whose fundanental frequency is:...

(i) greater than 33 Hz for theconside-'ationof seismic loads.

(ii) greater than SO Hz for the conside-ration of hydrodynamic loads.

(P22B-L'9)

Page 30: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Specif 1cation ~6-G-22Revtsion 4

t

(c) Structurally Ccmplex equ'~nt - are +~sewhich cannot be classified as structurallysimple or structurally. rigid.

When the equipmnt is structurally s&pleor rigid in one direction but ccmolex inthe other, each direction may be classifiedseparately to determine the dynamic loads.

711 Res nse ctrum Anal sis

The appropriate response spectra for speci-fic equipnent are, issued with the equipaentspecification for OBE, SSE; and hydrodynaad.cloads. Response spectra are based upon thdynamic analyses of the supporting structure-and represent th dynamic response of a singledegree of freedcm system at a particularlocation within the structure. Response spectraplotted in terms of acceleration versus frequency,correspond to various locations within tbbuildizgs and are identified with respectto the points noted on 0he mathanatical'adelfor each direction of vibration to be considered.~s may include the vertical as wel1 as boththe N-S ard E-'N horizontal directions. Znaddition, each response spectrum correspondsto a particular damping ratio, i.e., theratio of damping af the single degree of freedomsystem to critical damping.

r ~

Ghe horizontal seIsmic response spectra pro-vided have been generated with respect to amaximum horizontal ground acceleration of0.05g corresponding to the OBE, and a maxi-mum ?urizontal ground acceleration of 0.10gcorrespo~ to the SSE unless otherwisenoted. 5he vertical response spectra arebased on ground accelerations which are 2/3of the horizontal accelerations.

7.1.1.1 Structurall S le ui

'or equiprent which is structur-ally simple the dpnmnlc load~(either seismic or hydrodynamic)shall consist of a static loadcorresponding to the equipnent.weight tom s the accelerationselected frcm the appropriateresponse spectrum.

(P22S-1/10)

Page 31: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ Specification 885 22Revision 4

'he acceler'ation selected shallcorrespond to the equipnent's naturalfrequency, if the equipMnt!s naturalfrequency is knom. Zf the equipnent'snatural frequency is not knom, theacceleration selected shall correspondto the max&urn value of the responseBpectras

7.1.1,2 Struc

Por 'equipnent ~ch is structural1yrigid the seismic load shall consistof a static load corresponding tothe equipn nt weight tim s the ac-celeration at 33 Hz, selected franthe appropriate response spectrumand the hydrodynamic loading shallconsist af a static load correspond-ing to the equipnent might timesthe acceleration at 80 Hz., selec-ted fram the appropriate responsespectrum e

7.1.1.3 Structural C lex ent;

(a) For the purposes af analysis ofstructurally 'canplex equipnent,the equipnmt may be idealized by

, -.any nathematical nadel ~ch ade-- quately predicts the dynand.c pro-

perties af the equipnent. 'Ihe'adel shall be adequate todefine the dynand.c behavior afthe equipnent &thin the frequencyrang,e of interest. 2m mass andstiffness of both equipn nt appen-dages and supports shall be consi-&red M the mathematical nndel afthe equipn nt if the interactioneffect is significant. All properties shall reflect We in-serviceoperating conditions as closely aspossible. Ghe frequencies and audeshapes sha11 be detexadned. 'eeffects af coupling between vibra-tions af the equipnent in allthree global directions shall beconsidered, if significant.

{b) The dynamic model shall includesufficient number of nades so thatthe Inclusion of additional andesdoes not result in a+re than 10percent increase in the response.

-11-

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'pecification 88~22- 'Revision 4

(c)

I

Cate sloshing effect of any containedliquids shall be in"1&ed, if

sig-'ificant.

(d) The spectral accelem.ion per nudeshall be obtained ~ the appro-priate response spe"trna, which hasbeen provided for the appropriatedamping value. Tn c tezmining the .

spectral acceleration fran the re-;.sponse spectnxn st~ be the

largest:-'alue

on the curve ~ the frequencyin question is varied by +105.

(e) Ejnamic response in t rms of,inertia forces, s¹ars, mcments,

'tresses, and deflect1ons shall bedeteradzmd for response to dynamic ...excitation in each of the globaldirections for each mode. Theresults of the individual modes,shall be ccmbined by the squareroot of the sun of'he squaresmethod except th following pro-cedure shall be ~ for closelyspaced mades: for tm consecutivemodes which have frequencies thatdo not differ by more than 10$ orless of the lower frequency, the

es of tease aades shall be--respons':caabined by the sun of the absolute

va1ues method box canbining withother modes by t¹ square root ofthe sum of the squares method.

(f) Xn the particular case where thereis more than one equipment frequen-'y

located within the frequencyrange of a widened regrow band re-sponse spectrun, th floor spectrumcurve is to be apped in accordance with the criterion describedbelow. Ties is based on the factthat the act;ual ~ctural reso-nant frequency can possibly assmneonly one single value at one time,anywhere within the frequency range,defined. by fJ + Dfg, but not arange of values. Consequently,

-12-

Page 33: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

I Specif ication 885Revision

4'nly

one, add not all of these'quipment modes can be in resonantresponse at one time, with a m~pi-tude indicated by the peak spec-tral value.

The criterion is Q.lustrated bythe followizg example:

Let there be three equiprent fre-quencies7 (fe)17 (fe)27 and {fe)qthat are within the frequency ratiteof a spectral peak on the floorspectrum curve shown in 9'igure

. 7-1 (page 25). Pollowirg the rea-soning- previou:~ given, this.spectrum curve is not to be used

; ..directly to obtain the mdalacceleratious, e.g., Al, A2, audA, but ia to be used accordtug too 'f the three possible waystudicated by Figures 7-1(b) to{d). 2m one that produces thelargest total response shall beused for des~.

7.1-1A. Ctree nents of' Yotions

Gh responses such as Mternal forces,stresses and deformations at any pointfran the three principal orthogonaldirections of the dynand.c loads shallbe canbined as follows:

The response value. used shall be theaaxMum value obtained by ad~» theresponse due to vertical dynamic loadwith the larger value of the responsesdue to one of the hor~ntal dynamicloads by the absolute sum method.

7.1 1.5 Static Coefficient Anal sis

~ is sn alternative mettled".ofazelysis which is acceptable forver~i'tructural integrity offrame type structures such as'mem-

. bers physically similar to beamsand columns that can be represen-

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SpecXf icatloa 88+G-28'. -" Revision 4

ted by a simple model. No deter-adnation of natural frequencies ismade but, rather, th response ofthe equiprent is assumed to be thepeak of the response spectrum atdamp values as per Section7.1.1.6. Ches response is thenmultiplied by a static coefficientof 1c5 to take into account the ef-fects of both multifrequency exci-.tation and multinade response. Inthis analysis, the dynamic forceson each canponent af the equipmntare obtained by multipl~ thevalues of the mass and the accele-ration. She resulting force shouldbe distributed. over the canpomntfn a manner proportional to its

"aass distribution. The stressanalysis may then be per formed ina normal manner-

7.1.1.6 A ro riate Earns Values

Unless othe+6.se approved. by the buyerthe folio~ dzap~ values shall beused for the des~ assessm nt:

."1). Load Canbinations invol~OBE but not hydrodynamicloads c

2) Load Canbinations solvingSSE but not hydzodlpnand.cloads

3) Load Canbinations involvinghydrodynamic loads, or seis-mic and hydrodymaic loads.

She response spectra wiI1. be at-tached 'to the material requisi-tion or the equipnent specifio-ation.

Xf the Seller has evidence (suchas test results) that the actualdamp~ value of the equipn nt isdifferent. than that specified by'he Buyer, the Se11er may su?mitthe evidence and request thBuyer's approval to use a dif-ferent damp~ value.

(P22B-.1/l0)

Page 35: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ ~rSpecification 8856-G-22Re~ion '4

7.1.2 Time Histo Anal sis

Th1s analysis shall be 'done by an applicablenumerical integration techniqu . Ghe dynand.cinput shall be the time history motion at theequipnent support location(s). Xf a tomhistory analysis is necessary, the Sellershall request the Ryder to furnish the theehistory at the required locations.

7.1.3 Non-Linear Anal sis

Ifa non-linear analysis is necessary, arequest for permission to perform such ananalysis shall be made by the Seller to theBuyer and the procedure for the analysisshall be sulked.tted to the Buyer for appro-val prior to the performance of such ananalysis.

7.2 ui t Pi Interaction Ef'fects

~e interaction between the equiprent and the at-tached piping can be significant under dynamicloadings e

To deteanine the effect of the equipaent on thepiping the Seller shall furnish the matheaaticalrmdel(s) -of the equipnent as described M Section7.1, Men the fundam ntal frequency of the equip-ment is in the non-rigid range, as defined M Sec-tion 7.1.

The model shall &elude structural nembers at eachpiping connection of significance so that the stiff-nesses of all six degrees-of-freedaa at the pipeconnection are described. %he stiffness and massmatrices of th mathematical nadel shall also beMcludede

7.3 Nozzle Loads fran er Suo lied Pi

In scme cases piping furnished by the Buyer'ay .

'ttachto the equipnent (for pumps, tanks, heat ex-changers, etc.) furnished by the Seller. The equip-aent shall be designed to withstard the loads im-posed upon it by the attached piping. In additionto the app1icable pressure loads, the equipmentshall be capable af resisting the following nozzleloads which are du to.mechanical (non self-limit-ing) 1oadIirg of the piping system, M accordancearith the criteria stated in the material requisi-tion or equipnent specification:

(P2ZS-7n)

Page 36: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

~ ~

Specifkcat10n056-G-22.Revtsion 4

(2)

Noaral ard Upset Hne~ency and FaultedLoads (except pressure) Loads (exce C ressure)

Q~ PorceShear ForceBerdfng NcmentTorsiorsl Ncaent

0.03 SA0.06 SA030 SZ0.15 SZ

0.06 SA0.09 SA0.50 SZ025 SZ

where "A" and "Z" are the axial area and sectionnudulus of the attached piping. "S" is the allow-able stress va1ue f'r the piping material at Cheoperating temperature, according to table I-7.1or I-7.2 of the ASK Boiler and Pressure VesselCode, Section III- To account for the. effects.af 811 self-limit~ loads such as the thermalexpansion etc., besides the above loads the noz-zle shall vlf.thstand an additional load of T-70 (Q)

250where 'T's the taacerature af the nozzle in de-grees Fahrenheit anl 'Q's the respective valuesof Column (1) above. Unless otherwise stated inthe material requisition or specification, themechanical nozzle loads, pressure loads, and self-limit~ loads are considered to occur simulw-

- neously. We Seller shall state if he cannotmeet the nozzle load requireuants given in thissection. Alternate methods of providing for nozzleloads must then be provided. In either case, thecalculated loads which are based on the analysesaf the actual piping systems will be provided tothe Seller for concurrence at a later date.

8.0 ZZZrm

S.l General Criteria

In lieu of perforndzg dynand.c analysis, dynamic ade-quacy may be established by providing dynamic testor previous dynamic envirozxnental (performance) datawhich denanstrates that the equipnent meets the dy-namic design criteria as designed in Section 7.0 ofthis specification- Such data shall conform to oneaf the fo11o~:

1

{P22B-7/2)

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Speci'ication oo>~~~Revision 4

1. Performance data of equipnent ~ch, under thespecified, conditions, ?as been sub )ected toequal or greater dynanic loads than those tobe experienced under the specified dynanicco&i.t5.ons e

2. Test data frcm previously tested ccmparableequipnent ~ch, unchr sind3ar conditions,has been sub)ected to equal or greater dynamicloads than those specified.

3. Actual testing of equipaent 'In operating con-C.tions sImulating as closely as possible theactual installation, the required loadingsand load ccmbInations.

In general, horLzontal and vertical ccmponents of.motions shall be used in aLL three prIncipaldirections. Alternatively, a series of biaxial orurd.axial tests may be used to sImulate sImultaneousInput in all three prInci~ directions.

Ghe minImum CIme duration for each condition anddirection shall be 30 seconds, and, in no case,less than required to produce desired amplifica-tion. Ghe equi'elected for testing shallbe the actual purchased equipnent or identical-- .equipment unless s~cifically approved by Buyerprior to test..The Seller shall sulxnit to the Buyerthe test program for ream prior to testingaf'he equipnent.

8-2 Acce table Test Methods

The cont~ous s~soidal test, sine beat test, ordecaying sinusoidal test superimposed on randem

.nution, is acceptable when the applicable flooracceleration spectrum is a narrow band responsespectrum. 0th rwLse, raritan natIon test (orequivalent) with broad frequency content shall beused. See Section 8.5 for test acceptability.

(P22B-7/3)

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Specif icati8856-G-22'Revtsion 4

I

8.3

8.4

Gee equipnent Co be tested shall be mounted M a man-ner Chat simulates the actual service nuunting. Cateorientations of the equignent during the test shallbe documented. Cate nethod of'ounting the equipnentCo the vibration generator shall be docum nted andshall include a description of any interposing fix-tures. The effects of such fixtures must be eval-uated if they are only used during qualification andnot for in-serif.ce mounting.

8-5

Sufficient monitoring equi.Zaent shall be used Coevaluate Che performance of the equipnent before,during, and after the test. ln. addition, enoughvibratLon mnitoring equipmnh shall be provided "

. at the location which s&nilates the base of'heequipment mount to allow dhtermina.Cion af themagnitude, frequency and/or tine history of'heapplied motion depending on the type of test.

Test Acce tabiliWith the appropriate test m Crud selected in accor-

'ance with Sect1on 8.2, the equi'an be quali»fled if the test response spectra {THS) envelopes therequired response spectra (BHS) attached Mth theequipaent technical specif1cation, for the appropriatedamping values (see Section 7.1.1.6). We Im&mnnacceleration of the shake table motion should beat least equal to the zero period acceleration (ZPA)of the HRS.

8.6 Device Test

A device is defined as any single piece of equip-mnt mounted, either singly'r in a group Wthother"devices, on a larger equipnent unit or sup-port+

(P2ra-7/4)

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Specification 6-G-22.Revtsion 4

Devices shall be tested m an op etio~» nnde tolevels at'least as high as the levels dictated byservice requirements. Devices aay be tested ei-ther by.itself on a shaking table, or as part of anasseahly test.

If the device is tested by itself', the shaker table mo-t1on for the test shall be determined M one of thetwo folio~ ~sra.. Direct monitoring of th device support motion

in an assembly test M ~ch the assezbly sup-port motions satisfy all of the requirementspreviously stated in this section 8.0.

b. Deteradnatiort of the" assembly transfer functionfoi the device support location and applicationaf this transfer to an assembly support motionMch satisfies all th requireaents for a testaction previously stated M this section 8-0.

8.7 Assembl Test

An assembly is defined as two or mre devices shating a'camnon mounting, or supporting; structure.

Assemblies may be tested in an inoperative mode withactual or simulated devices installed. 9he dynamic

~ properties of the devices shall be simulated Mthsufficient accuracy to yield. the same dynand.c prop-erties fot the assembly with the actual devicesinstalled. Asseahly testing hall meet all the re-quirements for testing stated in this Section 8.0.

8.8 Post Test Ins ction

8.9

9he tested item shall be thoroughly inspected f'rany danae sustained during test~. A detaileddescription of damage and repair, accanpaniea byillustrations, and/or replacement shall be, in-cluded in the test report.

t RQ.function

If the equipnent fa53.s or malfunctions or wQ1 notoperate after the test, the Seller shall redesignthe system azxi resuhnit to the Bger drawings anddata for approval. A new test shall be conductedon the redesigned equipment to show canpliance'iththe specification at no additional expense to the

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~:, SpeciZ1catfon 885&4-2Q.'evision 4

Buyer. %he Seller shall resubmit the test programto 'the Buyer for approval prior to retestlng, ifthe test~ program is altered.

Modifications not affecting the function may be madeto the equlpnent during the test~ process and re-vised draN~s, Justifications and other documenta-tion resuhai.tted based on the final acceptable teston the

acidified

equlpnent. Such undiflcations aresubject to acceptance by the Zhger.

9 0 COMBE'KD ANALYSIS AND TEZKNG

There are several instances where the qualification of'quipnent by analyst alone or testing. alone, may not

be practical or adequate because of its size, or= itsccmplexity, or Bar~ nznber of'M9Zar conf+urations.In these lnstances a canbinatlon of'nalysis and testingcould be most practical. Cate folio~ are generalapproaches:

(a) An analysis could be conducted on the overall as-seably to detente its stress level and the trans-missibility of motion frcm the base of the equip-ment to the critical ccmpxMnts. %be critical ccm-ponents would be reunved frcm the assembly and sub-Jected to a simulation of the end.rorxnent or a testtable.

(b) Exper~tal methods may be used to aid M the formulation of'he mathematical madel for any pieceof equipaant- Node shapes and frequencies may be

'etem1nedexper ~tally and incorporated into amathematical aadel of the equipnnt. Ghe model andsubsequ nt analysis shall me t all the requirem ntsof Section 7.0

Por those equlpnent which have already been quali-fied for seismic loads, the canbined analysis andtesting approach can be used'for qua.Lifying theequipuent for canbined selsad.c and hydradyn'nnlcloads. In such cases, the Seller shall sulxd.t aprocedure to the Buyer for approval prior to adopt-~ such a procedure.

(P22B-7/6)

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'

Spec&icat1on 8856-Q2Hevtsion 4

10.0 EVEDBJC:- OP CGbiPLiAN~r.

The Seller shall sulxd.t evidence that his seismic Cate-gory I equipuent satisfies the requirements of this spec-Ification. We evidence of ccmpliance is subject to ap-proval by the Buyer prior to fabrication (or prior toshipment of starward off-the shelf Itens) of the equip-aent. '2m Seller shall suhnd.t the '~uiprent Qualification.Report Sugary" shown In App ndix A with the qua1ificationreport. The evidence of ccmpllance shall be of one ofthe follow~ forms:

10.1 Anal sis Qualification Re rtThe report for equipment qualified by analysis shallbe presented In a step-by-step fozm which Is [email protected] by persons skLlled in such analysis.

i -'

a. 'escriptionA general description af the equipment shall begIven with drawings, fIgures and photographsas necessary. %be Infomation ~ &elude a

'escriptionaf'ow the equipnent functions drySzg o'perations.

b.

co

Design CriteriaCate design criteria shall be documented, stat-

allo~ables and referencing applicable cod s.The deformation limits required to keep theequipment functiona1 shall also be stated whereapplicable.

Lo@2izg Conditions'Ihe specific loads and load canbinations usedIn the analysis and the design of'he equipnmtshall be stated.

do

e.

Nathanatical Model~ section shall svnnarize the mathematicalhandel, assumptions and properties. A gustifica-tMn shall be provided for any damping valuesused In the analysis that are different frcnr.tlmse in Section 7.1.1.6. If'he equipnent;.Is

'upportedat two or narc locations, a statementshall be made Indicating how the effect of thedifferential support displacanents Is considered.

Ccmputer ProgramsA description of all canputer prcgrams used Inthe analysis shall be provided, togeth r withthe prcgram capabQ.Ities, Its nEne and source.

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,. Specification 8856M2~ 'evision 4

Analysis Techniques%he report shall state the techniques used toanalyze the mathematical aedel of the equip-m nt, and shall show calculations.

Analysis Results9hls section of the report shall 'sunmarize theindividual loadings considered.and also thecanbined results.

The appLt.cable design response spectra, t~histories, or nahum 'g'evels shaU. beidentified for all three ma)or equiprent di-rections, (two horizontal and one vertical).

~ Zf nndal analysis is used,'aude 'shapes, fre-quencies azxL modal responses shaLL be pre-sented.

h. Sumnary of'he Analysis'XhLs section shall sulu'ize why the equiprentis acceptable, based on ccmparison af predictedresponses and allowables. Ghe calcu3ated de-formations ~ch may affect functionally sha11be canpued to values which would cause ma1X'unc-.tion. The section shall also &elude a sunnyand a conclusion with reference to the analysisWere information for the conclusions can bereviewed.

*4

~ A

10.2 Test Qualification Re rt)g

The report for equipment qua1ified by test~ shallbe presented in a step-by-step form which is read"tlyauditable by p rsons skLLled in the review of suchreports.

bo

DescriptionA general description of 'the equipment shall begiven with drawings, figures and photographs asnecessary. 9he information shall include a de-scription of how the equipnent functions dur~ .

operation.

Design Criteria%he design criteria shall be docum nted, sho~allowables and referencing applicable codes.

5'eforaationlimits required to keep the equiprentfunctiona1 shall also be stated where applicable.

(P2~n)«22

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SpecIfication 885 22Revtsion 4

Co

d0

e.

Loading ConditionsGhe specific loads ard load. ccmbInations used inthe qualIfication of the equipaent shall be doc-um nted. If any. of the loadIngs and load ccm-binations of the equipment specIfication are notused, a Justification shall be provided. '2m ap-p}kcable design response spectra, tim histories,or maxImum 'g'evels shall be Identified for allthree maJor equi@rent'irections, (Wo horizontsl

'rdone vertical).

Test Pacility~ report shaL1 include a description of thetest facility which conducted the test and/orprepared the test report. It shall Includethe name ancL the location. of the facility.Eyd.pmnt MountingThe mountIng of the equipment on the vibrationmachIne shall be described. Ches should Includepictographs.

Egulpaent Location and Or IentationCate equi'ocation and orientation relative.to the forcing functions (response spectra,time histories, etc.) shall be described.

h.

ClassIficationNon-Seismic Category I devices and parts In Seis-mic Category I assemblies shall be identIfied bythe Seller-

Operational Settings~ operational settings {or range of settIngs)for adjustable type devices shall be described.Tests for different settings shall also be de-scribed.

. Nonitoring SystemThe report shall Include a full description cfthe annitorIng system used durIng the test, in-cluding the location, type, calibration,,'etc. cif.all mzd.torizg devices (accelercmeters, straingages, etc-).

~ %

Test NethodThe report shall Include a caaplete descript1onaf the test met?ad used to qualify the equi',including excitation durations, vibrational am-plitudes, etc., as specified In Section 8.0

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. Specif1cation tlay~ic; 'evision 4

k. Test Data'e test data shall include co~ibration historiesof the test equipment, photographs of the equip-ment during testing, test response spectra andother relevant data fran th test.

1. Results and ConclusionsThe results and conclusions frcm the test shallbe briefly surrnarized. The results shall becanpared with performance requirements for theequipaent.

10.3 Canbined sis/Test Re

Gha report for canbined analysis/test qualifcationaf equipnent shall meet all of'he applicable re-quirements of Sections 10.1 and 10.2- Ghe report

. shall be presented in a step-by-step form which is~ readily auditable by persons st.led M the review

of such reports.

CERPZFZCATXON OP CQPLTANCE

All test data, des~ calculations, data, ard certifica-tions submitted shall be s~ed and approved for ccmpli-ance to the spec&~ication under the seal of the registeredprofessional eagineei in the State of Pennsylvan& or thestate 1n which the equiprent was nanufactured prior tofinal acceptance'

Page 45: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

Specii'ication 8856-G-%Revf.sion 4

Al

5

lIl

5

l: I

lt

Ap

I

5

5

1

l

lll

Ag

AI5

1"2 A

5

ppmlLEL(VV~5Cad

l .

(fQ (fQ (f/'f/'~e$ (EA (/e~5

~fe)4'l

I 5

A~ ~

Il~

I l(l.

AJ ~fAzj

I .

o'> (y <g e >+

%pure 7-1 Diagrams Illustrating the Use of FLoorSpectrum Curve When More Chan Che Equip-nant Prequency is Within the WidenedSpectral Peak.

'25-

Page 46: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

clf'ication 5556-G-22 .

evtslon 4

APPENDIX —

A'UIPKNT

QUALIFICATIONHEPORZ SUMNHY

C 1

Sheet 1 of 3'

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Specifi'cation 8856-6-22%vision 4

On

EQUIPNEÃZ QJALIPICATIOH REWRAP SUNi%RRY

No.

&port No.

Item

RBVe

Beference.~PSht Noe

2

3e

Z'quipaant name

Wuipnent Specification No.Seianic Category

Tag No.

BBVe

5-

~ ~

7e

8.

10.

Seismic qualification specification used

Spectrum curve used {RLgure No.):

Or+M of dim nsions, loads and material properties (~s.,specs., codes, etc. as applicable)-

+uipneut is stock item or specially designed item

Equipnent is qualified by ana?ysis

Equipnent 1s mechanical1nstrunmntation

electricalother specify)

Certification and signature of an authorized person that theequitant is qualified to the .required levels.

11. Epntplut is a motor pump reupanel , switchheer, tustnnneutother~specify)

12. Schematic sketch of the canplete unit.

13. l3escription of method of operation and control of equipment.

14.

15.

Criteria for behavior during a dynamic event includingoperat~ and dynanic load canb1nation.

Bpxipnent is located in the Bx11ding at ele-.mtion and is attached to the floor .

fiigl th (

16. I@scription of the anstlytical approach (such as natheaaticalnadel rigid or flexible system, single or miLtidegree offreedan system, etc.)

17. Sundry table of equipnent frequencies as detemMed byarQysis or exp.rimentally {by scanning) and as used toqualify the equipnent.

Page 48: Nuclear Regulatory Commission · HEbULA 'URY LNFORMATION DISTRlBUIIO SYSTEM (RIDS) ACORN.bbLUN NoH I ACLL:OV 5ol)V~5o8 AU I ri ~ iver AriE I Uhrktl I LSD' ~ A ~ 1 t ~ h!AMc YUUNGGLUUUgU~

ication 8856-0-22Be ion 4

t qualification Re rt Smn~ (cont'd)

18.

19.

20.

21.

Ehmp~ factors used in the an.~sis.

Justification for use of dampir~ factors other than those permittedby the specification.

Descr1ption and verification of'aaputer programs used.i

Description of the testing approach (such as b~~ial, triaxia1 test~,s~ated plant operation, testing frequency range, frequency interval,type of frequency wave frcm inputs, etc-)

22. 1@me and location of testing facility.23. Yathod of monitor~ and locations of aanitors during test~ of

equipment.

2l.

25.

26.

270

28.

Rnction1ng of equipnent during and after testing.

Thst levels of component locations shown to equal or exceed specifiedtest response spectra.

Codes, standards and specifications and the extent of their ccmpliancewhen qualifying equignent by test~.E'fects of equipment mounting assed in analysis or used during test~as compare to actual mounting

Summary table showing canputed stresses and deflections for operatingseismic and canbMed seismic and hydrodynamic conditions for equipnmtcanponents and anchorage canponents, capped with allowable stressesand deflections.

29. Ehactions at equipnent supports.

30. Naterial designation (AKN, etc.) f'r equipment ccmponents considered inanalysis.

«(Refer to report page or sheet nunber in this 'colm+. K not applicable,specky "N.A.")

P22-15/2

A-3

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eu i

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LOAD COMBINATIONS:

These were transmitted to the NRC on 8/28/80 as Page 3 ofAttachment N to PLA-536. This was in response to NRC Question110.42, and the entire response will be telecopied to Arnold Lee.

IMPLEMENTATION OF LOAD COMBINATIONS:

The GE SQRT Program uses outputs from the GE EquipmentAdequacy Evaluation Program which combines dynamic loads bySRSS as accepted by the NRC in NUREG-0484.

The individual items associated with the load combinationsare added as described below:

Steady State Events (e,g,, Dead Load, Pressure) - Absolute Sum

Time Varying Components (e.g., Maximum Seismic, Maximum Hydro-dynamic) — SRSS

Components of Events (e.g., Maximum X-Load Due to Y-Earthquake) — SRSS

Modal Response-SRSS, except for closely spaced modes where effectsare combined by Absolute Sum, Double Sum, or Grouping.

Details for each item of equipment are contained in thatequipment's Design Record File which is available for audit.

FJL/kes3/4/81

PENNSYLVANIA POWER IL LIGHT COMPANY