ML20214G498

Forwards Mechanical Engineering Branch Evaluation of Applicant Info Through Amend 8.Listed Items Verbally Submitted by Util on 720804 & Should Be Documented Prior to ACRS Meeting

ML20214G498
Person / Time
Site:	Columbia
Issue date:	08/14/1972
From:	Maccary R US ATOMIC ENERGY COMMISSION (AEC)
To:	Boyd R US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-0114, CON-WNP-114 NUDOCS 8605220235
Download: ML20214G498 (14)

Text

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AUS 141972 Roger S. Boyd, Assistant Director for Boiling Water Reactors Directorate of Licensing NASHINGTON FUBLIC POWER SUFFLY SYSTEM, HANFORD IMIT No. 2, DOCKET No. 50-397 The inforination submitted by the applicant, including Amendment No. 8, has been reviewed and evaluated by the Mechanical Engineering Branch, Directorate of Licensing. The appropriate sections of the Safety Evaluation are enclosed.

The applicant submitted the following information verbally on August 4, 1972:

1.

The applicant will use a soil damping ratio of 10% for both vertical and horizontal directions.

2.

The applicant will use a static factor of 1.5 if static analysis is used in lieu of dynamic systems analysis.

3.

The applicant will comply with Safety Guide 12 and will consider free field recorders and will install peak recorders on selected Class I equipment.

4.

If Browns Ferry or a subsequent plant prior to Hanford 2 is not accepted as a prototype Hanford 2 will be used as a prototype for vibration testing.

5.

Category I equipment will be qualified by testing to the appropriate seismic levels and including the operating mode if appropriate or by acceptable analysis if the equipment cannot be tested.

6.

The applicant will commit to identify the input transients such as valve closures and pump trips and provide the acceptance criteria for acceptance testing of piping.

7.

The applicant will commit to perform dynamic analysis of remeter internals due to LOCA. If a statis analysis is used justifiestion by test will be provided.

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Form AEC-518 (Rev 9-53) AECM 0240

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BbOS220235 720014 PDR ADOCK 05000397 A

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AUG 141972 Roger S. Boyd 2-8.

The applicant will define the stress sad pressure limits appropriate for emergency and faulted condition categories for pumps and valves within the reactor coolant pressure boundary.

9.

The applicant will comply with the proposed ANS criteria to protect against the effects of pipe whip.

10. The applisant will comply with paragraph ME 3322 regarding the stress limits of penetrations of the steel containment.

The applicant h s agreed to provide documentation on the above agreements prior to final publication of the AEC Safety Evaluation. This documen-tation should be obtained and reviewed prior to the ACRS meeting.

Odainas seed by D F P/ gepry

1. R. Maccary, Assistant Director for Engineering Directorate of Licensing a.

Plant Name: Hanford No. 2 b.

Licensing Stage: CP c.

Docket Number: 50-397 d.

Responsible Branch and Project Manager: Gas Cooled RB/S. Miner a.

Requested Completion Date 8/18/72 f.

Applicants response date necessary for completion of next action planned on project: 9/8/72 g.

Description of Responseg Safety Evaluation h.

Review Status: Complete cc w/ encl:

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5. H. Hanauer, DRTA j fkg, p/,3 4 g,.g J. M. Hendrie. L V

D. F. Lange, L i n? d (3 /C a R. A. Clark, L S. Miner, L K. K. Kapur, L

g. W. Ecu, L N. H. Davison, L J. E. Richardson, L cc w/o encle A. Giambusso L W. G. Mcdonald, L

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2 DOCl;ET ?0. 50-397 3.6 Criterin for Protection /. gainst Dynnnic Effects Associated with_a Loss -of-C..oolant Accident The app 3icent's position on pipe rupture criteria agrees substantially with thc proposed /.:;S 20.2 "Dnsita Basis for Protection Against Pipe 1.*n i p. " For piping, within the reactor coolant pressure boundary the proposed cciteria poetulated ruptures at all terminal points t.n:1 at any interncdiate points where cith?r the cumulative usaae factor exc e m's 0.2 oc the elastica 11:, cr.lculated prinsry plua secondary strecscs c::cee ' ?.0 ti: tac the co.!e al]o. i'4]c st ress intet.sity.

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pentulti-.3 at one interr.cdiate 1-oint betrecn t c rn '.ni 3 reints i: erb coarJ f: - te ple:e of t !. *: pipir er branch rim in each run vi: h J ess than three breah locations deternined on c strest or usa;,e f ~ rt ot benir.

He hC lievt. ti ut i* pl (:1an tti' 10.1 Of th.. ah0Ve Criteria Uil) provide l

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3.7.1 h isnic lu g The seisnic design responr:e spectta indicate m:plification frictors of J.5 betucen the period range of.167 to.5 ceconds and of grecte:

than 1 in the period range.67 to.03 seconds for 2% danping.

The structure and equipacnt danping is in accordc.nce with the danping f actors which have been accepted for all recently licensec' plants.

The nodified tine history to be used for cor.ponent. equipnent design is adjusted in anplitude and frequency to envelope the response spectra specified for the site.

L'e and our ticisuic consul tants conclude t hat the seicnic input criteria propond by thc applicanc provide ar acceptable basis for scionic d e.si gn.

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3.7.2 scismic_ Fvst w Analvss 3.7.3 Sc l e.nte subsvs'.e-t Au l":.es l

!bdal respon.cc spectrm: nulti-degree-of-f reedon and norra.1 r:ede-Line history r;cthods will forn the ba.scs for the analyses of all i

najor Category I structures, systu;s, and components.

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response paranatcrs vill be combined by the square root of tiie t.

j sua of the squares to obtain the nodal maxinune when tha no,1c1 1

i naronse spectrua nethod is used.

Tha absolute sum of t apansen a

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is used for in-phase closely-spaced Ircqueueles. Floor spectra inpute to be used for design and test verification of structures, i

systenn and co'.pencntt, are generated f rom the nor. awl n2de-time i

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A vertical sels :ic-syste: J y.....,1 c ;_ n r i y:.i r,.:111 4-li: onp]oyed for c1] st ruc turec,.ver.rme md ceapo.rnt.c t: hora a.r.lyr,es thc-significer structura.1 amplifications da tha f

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d 4-3.7.4 Cr it eria for Scisric furtru~entatien Pro: ram The type, numbct, location, and utilia:ation of ctroa;; notion cccc]crographs to record scimic events and to provide data on the frequency, anplitudc and },hace relationship of the scismic r

res;,anse of t.he contain.nt structure corresponde to the reconmendatic ns of Saf et y Gaide 12.

l Supporting instrumcatation vill be installed on Category I structures, systens, cnd corponente in cr*,ler to provide data

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for the verification cf the t.cist:Ic respenr,es deter :ined I

analytically for such Category I itens.

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b 3.0.2 Cmitaire m-Structure (Steel) 4 i-j The netal contain, ant s stem, which includes the vessel,

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penetration asse thlies and access openings, is a low leakage i

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steel rhell whc b vill be design d to sustain the combinatica

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of leadc recultin f ro, the Loss-of-Coolant accident, the.

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j Operational Tasis larthquake, and the conventional live and 1

dead lon b vithin th st ress lirits defined 1:1 Subsecticn B I

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of the ISU; Section Ill 1:oclear Veccelo Code for the nornal s

and upset operatire, cendit!on cat egories.

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For the co-41 nation of loadingt uhich include those calculated t.o resul t. from t:w Loss-of-Cool.1nt Accident anj the Dcsign 1.iacis

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3.9.1 avantic sir:t en / :nivsir :nd lesting The applic.'nt vill nahe provisions for conductla.g a preope;;.tional test progran as related to l'afety Guide 20, "Vibratioa :!e.wurerents on Reactor Internale." These provisions will be incorpor:.ted into the design.

Tests will be conducted to be used in the design of Category I mechanical equipnent such as fans, pu:ap drives, valve operators, to withcLand scisnic vibratory loading cc,..litions.

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The applicant h w subnitted a description of the net iodn and t

procedures that vill be used to conpute dynamic responres of the reactor internnl.: and teactor cooltat systeri (un:1ficcccd' loop) u:.5cr the LOO /. loading canditions.

i L'e fitid the cri teria, n.eth,ds and procedures delineated abeve to be receptable, i

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3.9.2 ASE Code Clas> 2 and 3 Ce panents All r.eismic Category I co:.penent.4, equip.cnt and systems in AS:lI'. Code Class 2 and 3 and outside of th2 reactor coolant

-pressure boundary, will be designed, fabricated cnd inspected in accordance with the requirencnts of the applicable codes delineated in section 3.2.2, " System Quality Group Classifi-cation."

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These items will be designed to sustain nornal loads, anticipated t

transients and the Operational Basis Earthquake ithin the appro-i l

priate code allovabic stress linits and the Design 11aals Earthquake within stress lin!ts chich nre conparable to thorc casociated with 5

1 the e.crrency operatin; coadition category.

L'c concider that these stress criteria provide eu cdequate turgin of safety for Seistaic i

Cctegory 1 systern, compencats cud equip ent.

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3.30 Sei:.mic 1)esiro of Cat r. or T Instrumcatation a_n3 Electrien] Ec u iyr.en t i

The rcactor pratcc.tive systen, engineered safcty f eature circuits and the energency power system will be der.igned to r.cet Category I design criteria. Seicafe require:.ent e established by t he seisnic systcc analysis will be incorporated into equipecat specifications to insure the equip;aent purchased or designed will nect seismic requironents equel to or in e:-: cess of the r e r,ui r enan t for Category I corcponents either by appropriate analysis or by qualification testing. The seitnic qualification procedures and documentation requirements of ILCE Std. 344,1971, "IEEE Cuide for Seismic I

Q.ni f fica t ica of Cic e.

I L] ec t ric Er,ul, :. ent for Nucitar l etter Ceaerating Ftotienc," vill be followed.

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4.2.2

.".cretor Vest el Int ernal:-

(' echanical DesIrn)

For all operating categories (aornal, upnat, ener; ency and faulted) the applicant has adopted design stress, defornation and f atigue limits for the cor( support structures which are comparabic to those cont ained in the January 1971 draf t of the ASME Code for Core Support Structures.

For nornal, upset, emergency and fcultcd design loads of mechanical, hydraulic, and thctnal origin, the reactor internr.1 components, other than core support structures, vill be desi;;ned to function vithin the appropriate nornal, upnet, energenc; and faulted coalition cr.te,ory stress linit criteria of Subsection ::P., Ecction III of th: /.'~:T Foiler and l'ressure Veccel Code.

Uc find that the der.frn criteria and analytical nethods employed fori au cceept a5]c basis for th2 desien of the reactcc i n t crua i t..

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5.2.]

Desi;:a criteric, '4cthods and Procedures (!tecctor Coolant Pressure Boundarv_)

'lhe recctor coolant pressure boundary will be a Seismic Category I system designed, fabricated, and inspected in accordance with the requirenants of the cpplicable codes delineated in Section 3.2.2, Systen Ouality Croup Classifications. The stress limit criteria specified for the norcal and upset operating condition categorier.

of the applicahic codes will apply for all normal lande end anticipated transients including the Operational Daais Earthquake.

Under the loadr, cniculat ed to resttlt from the Desir,n Ens.t.r Accidiit, the Desiga Easis E0rtiviaa' c, cod the cor..bination of ther.e postulated eventa, the ev::.penents of th. re e:. tor coc1. cat pres.ure bouudar;. s:!11 be designed tr. the cppJ icabic er creer.cv cud fcult ed ogcrating con-dition category 3.f r.it c of the appropriatt codes.

Active cocyr.snt.,

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.d valves r eyired t e carcte reliably in ordc: to ; e r f oro e s-af c ty f u.:c t ic., such :. : fe shut-do a c' tlw r.

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r In accordance with SubparcLreph N3-3622.3 of Section 111 of the AS'T. Nuc1cw Ccmponent Code, which requiret that piping shall be supported to t:ininize vibration and that the designer is responsible to observe thet vibration is within acceptabic levcis, a vibration operational test program to verify that the piping and piping restraints within the RCpB have been designed to withstand dyuanic effects due to valve closurec, punp trips, etc. will be perforced during startup and initial operating conditions. The proposed tests and the associcted actions, e.g., punp trips, valve actuations, etc., that are to be uscd in this 1.ictrea will be ci=11ar to those experienced during'rcacter operction nnd provide an acceptaH e basta for conducting the vibration operational test progran.

. O Con.<ultants The following cont,ultant has been rec,ucated to reviet. and evaluate the seicnic design criteria enployed by the applicent with reference to structures, systems, and components.

"athan M.

icwnark, Consulting Eng..ncering Services Urbana, Illinoic Uc and our consultant have revics:cd the FSt.R and applicabic amendments and find the scist ic desi ;a criteria docur.ented therein to be acceptable, 1

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