ML19319D579

Forwards Request for Addl Info Re Reactor Internal Structure,Reactor Coolant Pressure Boundary,Seismic Design Criteria & Pipe Whip Criteria Submitted in FSAR Vols 1-5. Response Needed to Complete Div of Reactor Stds Review

ML19319D579
Person / Time
Site:	Crystal River
Issue date:	12/09/1971
From:	Case E US ATOMIC ENERGY COMMISSION (AEC)
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8003170749
Download: ML19319D579 (22)

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Peter A. Morris,' Directer, Divisica of Reactor 1 Licensing CRYSTAL RIVER NUCLEAR GENERATING PLuiT-UNIT 3,' DOCKET NO. 50-302'

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.p Adequata Cresponse1:to_' the-enclosed request for additional' inforestion are required before~we'can completo 'our review of the subject application. - Thio

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request,. prepared bylthe-DRS. Mechanical Engineerbg Branch, concerns ~ the reactor internal. structures, reactor coolant pressure boundary, scismic daaign criteria and pipe whip criteria suhitted in voltnea 1 through 5 of the F3.C.

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TLic re ;uant reflects the ee:sents of our. consu1 tant, Dr Roland Sharpc of John t.. Blume Associates which wre contained in his letter of.~.pril G.

1971.

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ADDITIONAL INFOP.MATION REOUEST

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CRYSTAL RIVER UNIT 2 NUCLEAR GENERATING PLANT DOCKET No. 50-302 A.

Reactor Coolant Pressure Boundarv 1

The list of transients that have been used in the design of conpenents within the reactor coolant pressure boundary as specified in Tabic 4-8 of thc'FSAR appears to b ineceplete.

Identify all desien transients and their number of cycles, such as control system or other system nalfunction, component malfunctions, transients resulting fren any single operator errer, inservica hydrostatic tests, etc., which are specified in the AS?E Code-recuired " Design Specifications" for tha coepenants of the reactor coclant pressure boundary.

Categori:c all transients er combination of transients with respect to design Cases 1 throu;h IV of paragraphs 4.1.2.5.1 and 4.1.2.5.2 (ccuparable to the operating condition catenories identified as "nor.al", " upset", "cnergency", and " faulted" as defined in the Sta=cr 1963 Addenda of the ASME Section III Nuc1 car Vcasel Ccde).

Describe the program which will be used to record and naintain an accounting of significant transients occurring during plant operatica and to conpare the service nuuber of transients accumulated with those specified as the pernissibic nurber of transients for which the plant ir designed.

2.

Epccify the Code Case Intert,'rctations (Spe:1-1 ",ulings) that have acca inplcmnted in conjunction with the cc penent cies d2hneated in E

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Table 4-2.of the FSAR.

3.

Pacagraph I701.5.4 of the ANSI B31.7 Nuclear Power Piping Code requires that piping shall be supported to prevent excessive vibration under startup and initial operating conditions.

Submit a discussion of your vibration operational test program which will be used to verify that the piping and piping restraints within the reactor coolant pressure boundary have been designed to with-stand dynamic effects due to valve closures, purp trips, etc.

Provide a list of the. transient conditions and the associated actions (purp trips, valva actuations, etc.) that vill be used in the vibration operational test program to verify the intcarity of the system.

Include these transients introduced in systets other than the reactor coolant pressure boundary that vill result in significant vibratica rcspense of reactor coolant presaun bcundary systems and components.

4 Specify whethar the design criteria uhich have been used to exanine the effects of pipe rupture have considered postulated pipe breaks to occur at any location within the reactor coolant pressure boundary, or at linited areas within the system.

Provide confirnation that both longitudinal and dircumf erential type ruptures were evaluated and deceribe the basis for your design' approach.

5.

Provide a more detailed description of the reasures that have been ined to assure that the containnent lirer and all essential equipeent within D

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- l 3-1 the containment, including components of the primary and secondary coulant systems, engineered safety features, and equipment supports, have been adequately protected against blowdown jet forces, and pipe whip.

The description should include:

a.

Pipe restraint design requirements to prevent pipe whip impact.

b.

The features provided to shield vital equipment from pipe whip.

c.

The censures taken to physically separate piping and other components of redundant engineered safety features.

d.

A dcocription of the analyses performed to determine that the failure of lines, with diancters of 3/4 inch or less, will net cause failure of th: contain::nt liner under the most advarac design basis accident conditicas, e.

Tha nalytical methods which were used.

6.

Provida tha stress or deforna tion lir.its end the design codes or c:andards applic:ble te the principal reactor ecolant nfsten conpenent supports (i.e., supports, res traints "snubbe rs", guides, etc., as applied to vessels, piping, punps, cnd valv(s).

7.

Raported service experiences of P' R stcar. generators have dencnctrated thst fic induced vibration end ccvitatien effect can cause tube thinnin;3 and corresten and erosica nnchanis s both fren prirary an t

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N, secondary' side may contribute to further structural degradation of

- the tube integrity during the service life-time. The failure of a group of weakened tubes as a consequence of a design basis pipe break in the reactor coolant pressure boundary could impair the capability of c=crgency core cooling systers to perform their intended function.

In order to evaluate the adequacy of design bases used to prevent such conditions from developing in the steam generator during service, the following additional infor-mation is required:

(a) State the design conditions cnd transients which were specified in the design of the stecm cenerator tubes, and the a:plicable design stress intensity linita asacciated with Canec I throue,h IV of paragraphs 4.1.2.5.1 and 4.1.2.5.2 (conscrable to the

" normal", "e:act", "e.ncrgency", cad "fcultad" operatinc conditien categorica).

Justify the basis for this selection.

(b) Specify the nargin of tube-vall thinning which could be tolerated 4

eithout exceeding the allovabic strcss limits identified in (a) above, under tha postulated condition of a design basic largest pipe brcak in the reactor cecicnt pressure boundcry during reactor operation.

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(c) Dancribe the inservice inspectice ubich vill be enployed to en:mina the integrity of staan r ?nerator rubcs e.s a means to detect tube-uall thinning bey:nd cc:pt2ble linitr. :nd vacther cuccur nteri_1 S

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'J' 5-vill intentionally be provided in the tube wall thickness to accommodate the estimated degradation of tubes during the 4

service lifetime.

J 8.

Submit a copy of the su. mary technical report en overpressure' protection which has been prepared in accordance with the require-ments of paragraph N910.2 of the ASME Section III Nuclear Vessel Code.

9.

The applicable code summary. of Table 4-2 for conponents of the reactor coolant pressure boundary only cddrcases safaty and relief valves.

Provide the desica criteria and identify the design codes applied to all c:hcr valves within the rea:ter coolant pracmsrc boundary (e.g.,

AS:!E Code for Pc-pa and Velver for : ucicar Pcvar, A::SI B16.5, MSS SP-66, etc. ).

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I B.- Reactor ' Internals 1.

Identify the prototype reactor (i.e., the initial reactor of the

.same design, size, and configuration) from which vibration test data is applicable in evaluating the desi;n adequacy of the Crystal River Unit 3 core support structures to withstand flow induced vibration effects.

If a prototype reactor is specified, provide a detailed comparison of the applicable design parameters for the Crystal-River and prototype units verifying that no significant design or fabrication differences exist between the subject reactors which could caterially affect the vibrational response chcrceteristics of the reactor internale. However, the use of prototype results are valid only if the analytical nethods and procedures cr.nloyed for 0 '

prototype have been ecnfir--d by rn ::ceptnble preoperatienti vibrettan test program.

Provide the test data cad supporting enalyses which forn the basis for the EAbcock.4 '.Jilecx vibration r.cspcnce 7:cdicticas or if the validity of the nethods c ployed ccnnot be de=anctrated at this tira, include in your response a statenont of your intent to inglerent a preoperational test program which includes the = ensures given below:

1.

A vibration analysis and test program should be developed.

The

_ test program should be suhaitted for revicu prior to the perfern-nnee of the ccheduled preeperational functienni tests.

The vibration testin; should h: cenducted with the fuel ele: cents in the core structure cf the reacter internals (or with dur v 6 -

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elements which provide equivalent case and flow characteristics).

Testing may also be conducted with dum core structure not loaded with fuel elenents provided such conditions can be de=enstrated to result in vibrational characteristics which, for the purposes of the test, will yield conservative results.

The testing may also be conducted both with and without the core structure loaded with fuel.

The test progran shculd include:

a.

a brief description of the vibration test program, includin~

instrunentation types and diagrc=s of their locatica, which vill be used for -:acurenant of vibratica re penses and thosc parauAtcrs which det'ine the input forcin; functions, b.

the planned duration of the te:t for ror-21 operctine r-inc to assure that cll critical components are subjected to at 3

least 10 cyclea of vibration, the cdditienal test duratica for other than norral cperatine c.

i acdes to assure that the nunber of cycles i=pecad on the

' critical corponents is sufficie t to analyze their cdaquacy n

to withstand vibraticas under these' operating nodes, i

d.

th2 descriptien cf dif ferent fleu :tedes cf cperaticn and transients to vidch the interrals vill b2 cuhjected curin:

the tcat, i

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the predominant response mode shapes and the estimated range

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of nuncrical values of the response of the major components of the reactor internals in terms of amplitudes and, where appropriate, the anticipated values of the parameters which may influence the input forcing function, under those flow modes of reactor operation, which are shown by the analyses to be the most critical, c

f.

the test acceptance criteria and the permissible deviaticas frcn thece criteria, and the beces upcn which these criteric were estchliched, g.

a descriptica c:. che incpection prcgran which will be felicwed af ter :he conpletien of the vibrction tests, including tha arcr, of reector internals subject to c::ct-

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ination, the nothod of enanination, tha desir.n access provicions in the reactor internals and the specialized equirnent to be ceployed for perfor=ing such exaninctions.

2.

A vibration ecs: progran should be inplenented during the pre-2/

operational functional testing progran to ceasure the response ~

of the reactor internals and, where appropriate, the values of those parancters which will define the input forcin: functions for the core critical esdes of reactor creration.

The data obtained by thcac recsurceents on recetor internals chould be

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~ Fracecacy 'end ceplitudca c f *ribratien, in ter c of velocitici, acccl2rc tier.c onl dicnic:cn:nts or ::rrira.

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. to verify that the cyclic stresses in the cenponents, sufficient as determined by analyses of these data, are within the accept-forth in the design specificatiens able design stress limits set the and applicabic ccde requirenents and that the resulta neet acceptance criteria of the vibratica test procram.

The extent of the nc.tsurencnts should be determined, for each 3.

individual case, en the basis of the design and configuration of those structural ele:enta of the reactor internals important to

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safety and their predicted behavior as determined from the vib-The type of vibration test ratica analyses used in their design.

the number of neasurenants taken, and the ir.s trur.cntatien uc ed,

devices uithin the rocctor shculd be distributica of measuring adequate to detect t.he presence of laterci, vertical, and ter-of vibr:tien (e.g., beam, column, cad chcll sional raplitu.e3 nodes of vibrations, as applit:ble to the gcc=etry of the internals) and at suf ficient locations to determine the points of predoninant nexinun vibratory oscillations.

Af ter the reactor internals hcvc been subjected to the significant -

4.

flou todos expected during service lifetire under norcal reactor operation, and other uodes of reactor operation, visual and non-destructive surfccc examinations of recetcr internals sho conducted to dctcet any evidence of the cffects of vibraticaz.

ennzinnticas chauld be c:nducted folleving rcroval of the The; internsis fren the reactor ve:scl.

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The areas examined should include all major, load-bearing elements of the -reactor internals which are relied upon to retain the core structure in place, the lateral, vertical, and torsional restraints provided within the. reactor vessel, those locking and boltin; devices whose failure could adversely affect the structural integrity of the internals, and those critical locations on reactor internal components as identified from the vibration analyses.

5.

In the event citber the inspecticas of reactor internals reveal unacceptable defects or the 'results of the vibration test progra-fail to meet the specified acceptanca criteria, a report shculd be prepared and sub: itted ta :ha Cc:missien for review, which includes an etaluccicn an.i a description of the corrective acciens planned in order to' jus:ify the adeluncy of the recctor internals design - to withstand tha vibrations ancected in service.

6.

If the tcat and ensuinctica progran is acceptabic, a' sun,2ry of the results obtained fron the vibration tests and inspection should b2 submitted to the Cermission af ter conpletion of the terte.

The suenary should include:

a.

a description of any dif ferences frca the sp2cified vibration test protran, instrumentation retding snomalies and instrunant

failures,

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a comparison between the measured values of vibration responsco including the parameters / from which input forcing functions 3

are determined and the predicted values from the analysis.

This comparison should be nade for those ccepenents of the ranctor internals for which the acceptance criteria under C.f. have been established with respect to the different modes of T

vibration, an evaluation of =casurements that exceeded acceptable linits c.

or of obsarfations that were unanticipated, and the dispositica of such deviaticas.

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Other Safety Related Fluid Systees and Connonents

1. - Describe the design and installation criteria for the counting of the pressure-relieving devices (safety valves cnd relief valves) within the reactor coolant pressure boundary and on the main steam lines outside of containc.ent.

In particular, specify the design criteria which have been used to take into account full discharge loads (i.e., thrust, bending, torsion) imposed on valves and on connected piping in the event the valves discharge concurrently.

Indic:te the provisions nade to accomnodate these loadc.

2.

Paragrpah 4.1.2.5.2 of the FSAR states that design cases III cad

- IV, cc, parable to ;..e "enernency" and "f aulted" cor.ditiena defined in Sectica III, have been applied to racctor coolant pressure i

boundary (RCF3) conpenents.

Identify cn/ other cenpenents or cystens that _rs not a part of the RCPS for which design Case IV stress linits will be applied.

In the event that Case IV stress linits have beca applied to any systen o-t conpenent exclusive of the RCT3, -provide the bases for such application.

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D.

Seismic Desiasi Criteria and Analyscs t

1.

Submit the seismic design spectra specified for the Maximum flypo-thetical Earthquake. -

2.

Identify the =ethod of' seismic analysis (modal analysis response j

' spectra, ccdal analysis time history, equivalent static load, etc.)

or empirical:(tests) analysis which has been employed in the i

design of the listed Category I structures, systems and components.

1 Provide a nore detailed descriptien of all rethods that were ceployed I

for scismic cn lysis including denpin-values, descriptiens (shetches) of the cathematical models empicyed and the precedure for lumpinq f

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3.. Submit the basis for the nethods used to deternine the pessibic cocbincd hori ental and vertical caplified respcasa leadium4 fo r the seise.ic design of structuras, systems and compenents includio; the following:

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-(a) The pcssible combined horf: ental and vertical amplified response loading for the seieric design of the buildtng s td floors.

(b) The possible conbined horizontal and vertical r.rplified respense t

- loading for the seicnic design of equiph.cnt and components, including tha effect of the seismic response of the buildina and ficors.

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(c) The possible combined horizontal and'vertic.al amplified response loading for the seismic design of pf; Eng and instrumentation, including the effect of the seismic response of the building, floors, supports, equipment, component, etc.

4 If a fixed base has been assuned in the cathematical nodels for the dynamic systen analyses, confirm the validity of this assumption by prov,iding summary analytical results that indicate that the rocking and translational response are insignificant.

Include a brief description of the rathed natheratical nodel cnd damping values (rocking vertical, trans1htien and torsion) that have been used to consider the soil-structure interaction.

5.

Describe the method which '.: s coployed to ccasider the torsional rodes of vibration in the seismic analysis of the Class I buildina structurcs.

6.

Provide the structura catcriel pr pertics cud soil r,tructure interaction which were used in sainnic design analysis and tae bases for selecticn of these properties.

Deceribe the reasures which will be taksa to assure tha't the calculated recpensa ef Class I structures will conservatively raflect the cxrceted variations in the pericds of vibration of the structures, l

7.

The use of both the r dal analysis respenca cpectrum and tine history provida a chcch en the reapcase at relected points in

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e the station structure.. List the response obtained from both methods 1

i at selected points in the Class I structure to provide the basis a

for checking the seismic system analysis.

6 nercribe the measures taken to ensure that the failure of Class II or III structures vill not adversely affect Class I items.

i 9.

Describe the evaluation performed to determine seismic induced n

effects of Class II or III piping systc=s on Class I piping.

10.

Indicate the canner in which the crane located in containeent is held on its rails to preclude dislodgement during seismic c:: citation, 11.

With respect to Class I (Sci; ic Design) piping buried er otherwisa located outside of the containment structure, describe the seismic design criteria cmployed to assure tha t nilevable pipinc, tc d stru:~

tural ctresses are not exceeded due to dif ferential nn eenant at support points, at containncat penetrations, and at entry points into other structures.

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Describe the seismic design. criteria employed to assure the adequacy of Class'I mechanical components such as pumps, heat exchangers, and

- electrical equip =cnt such as cable trays, battery racks, instrunent rack: and centrol consoles.

Describe the measures taken f or seisnic i

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a restraint to meet these criteria, the analytica,1 or testing methods employed to verify the adequacy of these restraints and the nethods utilized to determine the seismic input to these components.

13.

Describe the criteria cap;oyed to determine the field locatica of seismic supports and restraints for Class I (seisnic Jesign) piping, piping system components, and equipment, including placement of snubbers and drapers.- Describe the procedures followed to assure that the ' field location and characteristics of these supports and restraining devices are consistent with the assumptions made in the dynonic analyces of the syst'em.

14.

Describe the procedures used to account for the nunber of carthenche cycles during one scianic e /cnt cad specify the number of loading cycles for which Liass I sy-stees cnd components are desir,ned for in this cvent as decernined frca th2 expected durctica of the scisnic cotions or the numbcr of rajor cotion peaks.

The following inforcation requests are specifically related to GAI R port No.

1729 "Dynanic Analysis of '/ Ital Piping Systens subject to Saisnic Moticna",

i referenced in the application.

1.

.The -comparison for a single degree-of-freedon codel rethod identified in " Seismic Analysis of Equipnent Mounted en a Massive Structure",

J. M. Biggs and J. M. Reca:ct and referceced in C.'.I Report Mc. 1729 4

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may not be sufficient ly conservative for multi-mass systems.

Provide

cais for and the conservatism in the use of this method, by demon-strating equivalency to a multi-mass ti=e history method. Alter-natively, other theoretical methods or experimental analyses and tests may be submitted in justification of the use of the proposed design method.

2.

Provide the design criteria which epply to the dynamic analysis of valves and other in-line system components which by virtue of their i

gecnotry and size introduce significant torsional monents into the piping systca.

~ 3.

Provide the design criteria and analytical precadures which apply te piping and rhich takes into account the differential move ent between floors at different c1cvaticac.

4.

Fredominant enas and compliance of structuras, sys tens and cer_penents will affect the respcase c2 the cysten.

Provide the criteria used in formulating the cysten analysis which takes in:e account the coupling of those predeninant mass conpliance*

effcets in the systen dynamic analysis.

5.

In phase or out-of-phase displacements at dif fercat elevattens between (cquipnent) pipinq and tha building ray produce hi,,h atrcsses er defor-r.atiens in conacctin; piping.

Provice the crlteria cnd ann.1vtical

,i precedur3 used in the s;s ten On e.1. sis t a account-f o r in-phase or cu t-of phasa displacer,?nt o f tha culleir, equiprent cad nipin:.

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Provide the design criteria used to. compute shears, moments, stresses, deflections and or accelerations for each mode as well as for the

- combined Lctal response,' including the criteria for combining closely spaced codal frequencies.

7. "The presentations of the methods of dynanic analysis are general and the precise techniques used.for the system and piping analysis are not suf ficiently described to permit evaluation of their applicability and design conservatism.

Provide sufficient detail concerning the methods r

and procedures used including the rather.atical models and analytical results for najor piping systems.

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Seisnic Ouality Assurance Describe the design control b=asures which will bc in:tituted to assure that adequate scismic input, including any necessary feedback from structural and systen dynamic analyses is specified to vendors of purchased Category I cceponints and equipment.

Identify the respon-sibic design groups or organizations who vill assure tha adequacy and validity of the analyses and tests employed by vendors of Category I components and equipment.

Provide a description of the review procedures to be utili:cd by each group or organization.

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Scismic Instrumentation 1

With respect to scismic instrumentation, submit a statc=ent of ycur intent to impicment a progran such as described in AEC Safety Guide 12, Ir.str'm ntation for Earthquakes (April 9,1971).

Provida the basis and justificatien for elements of the proposed progran which differ substantially fren Safety Guide 12

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