ML19221A850
| ML19221A850 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1976 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.020, REGGD-1.020, NUDOCS 7907100101 | |
| Download: ML19221A850 (8) | |
Text
s e- * %
Revision 2 U.S. NUCLEAR REGULATORY COMMISSION May 1976 g
REGU ATORY GU DE OFFICE OF STANDARDS DEVELOPMENT REGU LATORY GUIDE 1.20 COMPREHENSIVE VlBRATION ASSESSMENT PROGRAM FOR REACTOR INTERNALS DURING PREOPERATIONAL AND INITIAL STARTUP TESTING A. INTRODUCTION B. DISCUS $10N Critenon 1, " Quality Standards and Records," of Reactor internals important to safety are designed to Appendix A. " General Design Criteria for Nuclear Power accommodate steady-state and transient vibratory loads Plants,' to 10 CFR Part 50, " Licensing of Production for the s:r. ice life of the reactor. This guide presents a and Utihzation FacditiesJ requires that st ructures, comprehensive vibration assessment program for use in sy stems, and components important to safety be verifying the structural mtegnty of the reactor internals designed, fabricated, erected, and tested to quahty for Cow-induced vibrations prior to commercial opera-standards commensurate with the importance of the tion. The overall program includes individual analytical, safety funct;ons to be performed. Section 50.34, " Con-measurement, and inspectior programs. The term "com-tents of Apphcations: Tecnnical Information,' of 10 prehensive" appears in the title of the overall program to CFR Part 50 requires the applicant to determme and to emphasize that the individual programs should be used specify the margm of safety associated with normal cooperatively to venfy structural integrity and to estab-operation and anucipated operating transients.
lish the margm of safety. For example, the anidytical program not only should be used to provide theoretical This guide presents a methed acceptable to the NRC verification of structural integrity but also should be the staff for tmplementmg the coove requirements with basis for the choice of components and areas to be respect to the mternais of hght water-cooled reactors' momtored in the measurement and inspection programs; 2
during preoperational and initial startup testing Inser-the measurement program should be used to confirm the we inspecuens and msenice monitonng programs to analysis, but the program (i.e., data acquisition, redue-verify that the reactor internal components have not tion, interpretation processes) should be sufficient y l
been subjected to structural degradation as a result of flexible to permit definition of any significant vibratory vibration during nomial reactor operation are not modes that are present but were not included m the covered by this guide. The Admory Committee on analysis, the inspection program should be considered Reactor Safeguards has been consulted concernmg this and used as a powerful tool for quantitative (e g., as ar.
guide and has concurred in the Regulatory Posinon.
indicator of maximum total relative motion) as well a qualitative (e.g., establishment of boundary conditions by inspection evidcnce at component interfaces) verifica-I Reactor mternais, as uwd m this regubtory guide, comprise core support structures and adjommg mternal structures Core t:on of both the analytical and measurement ptogram support and mternal structures are defined m Article NG Il20 results.
of Secuon 111 (Nuclear Power Plant Components) of the ASMI-Boar and Pressure Vessel Code.
The origmal guidelines of Regulatory G,uide 1.20 2Consaten t with Regulatory Guide 1.6 8. "Preoperational and were refined in Revision I to mcorporate items that truttal Stdrtup Test Program s for w a ter<oole d Power would expedite review of the apphcan t's vibration Reactors," preoperational testmg as used m this guide consists assessment program by the NRC staff. Generally, this of those tests conducted prior to fuelloadmg, and mtial startup was accomphshed by increased specificity m the guide-testmg refers to thow tests performed after fuelloadmg.
1.nes for the vibration an alysis, measu re men t, and
- Lmes mdwate substantnc (har.ces trom preuous nsue.
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w hedahng uemfu at Huses of tL open. : ue uNa-se#entiy modi 6ed m Jesign (e g, as in item 1.3 below )
remams a Vahd Prototype relatne to its on: nal deugn n.m au ssmcio y wm.
The onana! caidelmes sened as tne basis for testme 1.3 Conditional Prototy pe. A Vahl Pmtotype that later expenenses adverse m servis e vibration many prototy pe and smular-to-prototype t reteared to m this guide a3 non protots pe) reactor u,ternais Operatmg phenomena and su b se quently ha3 been modified m expenente anJ the tendency :or the desyn of sub a n a ncen.en t, des:gn sue, or operanng conditions is Conditional Prototy pe l'pon satisf y u+
sequent reastor.nternab to differ somewnat imm that desmnated a conj:nons desenbed cisew heie m tha guide the Condi-s the muub daignatcJ proton pes n vme mstanses, "1Jde the hJsh l?rs '!i nt s, an d noirphiltil) pJ s [aW!is a tiunM Prototype sen es as (b t reference deslen foi tmm.hiftah to apply rnaltmg m in ced for Nonfrototy pe. Cat @ry 111 and l\\, reactor internal 3 nme-conmnm _ s ase+3 s ase re sola no of r s ;or inter-wnfieur ations nJ! daelbtatitins Jn d sarresn
,en.g s!nta; age w.
14 Non-Prototy pe. Categors 1. A rea tor mter ment program nos contiguration w nh substantiaMy the s.une arrange.
Reu w I espa ;Jel er th preu n Jav z ens me nt. desten. sue and operatmg conduions as a and outhn ' an appmpnate co:
a :nsn e uh anen geatied Vaha Prototy pe an i for which nommal dufer-auessmem mgr: i fo each dass T v iL ufw nons e enses m arrangement, design. sue, and operatmg condi-cefined m eMuon F Nnon C.1 bemw. In gen rd th.
t:om have been shown by test or analysis to hae no ng p r o gr.a s symbcant effect on tht ubratory response and espa :ded dawth ans
.m J corn s
, u eunation of tho>e reactor mternah important to safety dow for tb uz mcer certam co: Anu 01 ; mten pc J wm a ds e rse r0 actor inter lO IhJ? nase expen.
t mservice vibRhon pher amena as htm:cd proton pes anj
- 1. 5 Son-Prototype. Category 11.
A reactor for the use. under tertam conditions. m reactor m ternis mtemals cennguration wnh substannath the same sue and operatmg conJinons as a specuied Vahd Prototype, e rev <ts snucturany dnsnHar trom th, that are m m c
desmuted prors pe as hnuteJ ne -p rot on ;'es The out with some component arrangement or design differ-e v an de d dassu h anom make the u se of this cmde entes that are show n by test or analy sis to hase no
' cdnpatible wnh Jeup and operatn c expene te. 'Reu.
ugniGcant euect on the ubratory response and excita-non of those unmodified reactor mternals m1portant to uon 2 retams tne espanded casubcanons of Reusion 1.
I % re chances m N wrrespondmg sibranon assessment safety.
- programs and m tne reportmg of reW s wer ude as a l res.;it of substanme pubh< comn ents and addmona)
I.6 Limited Valid Prototype. A Non Piototy pe.
l staff reue(
Category 11 or 111, reaeor internals configuranon that has successf ully sump;eted the appropnate comprehen-sive ubranon assessment program and has uself expen-C. REGULATORY POSITION ensed no adverse mscruce vibranon phenomena. An T he Jass:ncan.ms prouded m i dao n pourn n C i operatmg Vahd Prototype that ha> demonstrated extended satisfactory m3ervice operation subsequent to a shouiJ be used by the apphcan: m a wn/c th rextor deugn mod:ticanon may be considered a Umned Vahd mrernals atcordme to des:en, og mg paon t tert and ht pount d Jokr> ; es Th_
Prutotype clatn e to the modified reactor mternals the opeuung exhne se cor.hguranon. A Condit una! Protutype that has demon-appropnate compehensne uhrato a3 ew :n r procram should then be estabhubed fro: tL pde esspeUned urated exteNed unmetory inscruce epenn m may be considered a Unuted Vahd Prototype f or that dasuGcano > m tL u <eco.ng sciem uns of this
)* lide The(Umprehensies[branic asWss;nent pro ran,s outhneJ m uns p are su;mman/ed m h;ure 1.,
il Son Prototype Category 111. A te wtor mter-nds configuranon with substantiily the un arrange-
- 1. Classification of Reactor Internals Relathe to the ment, deswn, su e, and operatmg conJurons as a Comprehensive Vibration Assessment Piogram speaned Condmonal Prototy pe witn msufhcient op r W history to panfy a as a Lmae d Vahd 1.1 Prototype A reactor mternais monGguranon, C'#"'es m arrangement, design, sue, and N IC that, because of a.s arrangement. desy. sue, or operat-
"I U"8 'on num should be show n by test ur analy sis a tirst ol-a#md or umque mg condinons. represents t haw no s gmticant ef fect on the vibratory respor:se desipi for which no Vahd Prototy pc exists and ex;ttanon of those reactor mternals important to CIE 1.2 Valid Prototype. A reat tor mternds sontig-uraton that has succewfully vompleted omprehensn e vibration assessm ent program for Prototype r 'ac t m l A Son-Prototype, Category IV. A reactor mter-nMs connguranon with substannally the same arrange no adverse taser m e mterna!s and has expenenced vibration phenomena. A Vahd Prototype that is sub-ment, design, su e, and operatmg conditions as a 125 077 m
/
N PROTOTYPE Unique or first of a kind
\\
/
Analysis. Extensive Measuremant, and Full Inspection Inserv.m problems resulting in component or
[ Valid Prototype operational modifications [ Conditional Prototype
(
j\\ Valid Prototype modified
\\
Limited f
j Extended satisfactory /
rat n g inservice operation /
\\
/
\\
/
/
N NON PROTOTYPE \\
/ [ NON PROTOTYPE h
\\
g
/
CATEGORY 111 NON PROTOTYPE CATEGORY ll
\\
CATEGORY l
/
Similar to Valid Prototype
{
Substantially Similar to
,I
/ \\
/
o a to e y
j y
d te en
\\
Analysis and Either Analysis. Limited
/ /
Analysis, Limited
\\g Extensive Messurements Measurements, and ss / /
Measurements, and
/j Full inspection
\\
/
or Full Inspection Full Inspection Limited Valid Prototype NON-PROTOTYPE CATEGORYIV Substantially Similar to Limited Valid Prototyp/
e
\\
Analysis and Either Extensive Measurements or Full Inspection Reactor internals configuration for which comprehensive vibration assessment program is defined.
(
Summary of comprehensive vibration assessment programs.
Reactor intemals reference design which, together with its test and operating C
experience, provides the basis for a specific comprehensive vibration assessnwnt program.
Indicates alternative paths FIGURE 1 - SUMM ARY OF COMPf ?HENSIVE Vf BRATION ASSESSMENT PROGRAMS s
1.20-3
specified lanuted Vahd Prototy pe, w here n. naal differ-ciently simulated by the test conditions should tv ences in anangement, ucs:gn, sue, and opvatme condo ident:fied. )
tions hau been aown by test or analyus to hase no ugmfaant euca on the ubratory response and exata.
- 6. The anticipated stru u aral or h> J raube tion of those. aster internals important to satety.
vibratory response (defmed m terms of hequeno,
amphtude, and modal contnbutts n) that is appropnate A>>ouated with the Prototype anti the f ategory l, ll, to each of the sensor locanon: for steady state and 111 and IV Non ISototy pe c!assifhattons are the antiapated transient preoperational and startup test comprehensne uhration anessment programs delmeated conditions.
m regulatory positions L.2 and ' i and summanzed m hgure 1 The forecomg clawfications are defined 7 The,est xecptance entena with permissible reiatne to the three prototy pc reterence desun classin-dcviations and t'te baus for the entena. (The entena canons o e~ VahJ Protuty pe. Condition 2 Prototype, should be estabhshed in terms of maumum allowable Lumted Vahd Pretotype t upon whose deugn, test, and response levels in the structure and presented in terms of operatmg expenence th e.ndnidual c om prehensive maximum allowable response lesels at sensor locations )
ubration assessment propams :ue bascJ
- 2. Comprehensive Vibration Assessment Program for 2.2 Vibration Measurement Program Prototype Reactor Internals A vibration measurement program should be The comprehensae ubranon assosment propam developed and nnplemented to venfy the sauctural should be unp:ementeJ in conjunsnon wnh preopera-miegity of the reactor mternals, to determme the nonal and iruua! startup testmg it shou!d consist of a marg:n of safety assoaateJ with steady-state and antia-ubratton analysis, a ubration measurement program, an pated transient conditions :or nmmal operation. and to mspecuon propam, and a cerrelanon of their results.
confirm the results of the vibration analysis. The vibranon measurement propam should mclude a 21 Vibration Analysas Program desenption of:
The ubration analyus shou;J be performed for
- 1. The data acqumtion and reduction system, those steady-state and anthipated tranuent condicons includmg:
that correspond to preoperanonal and m ual startup test and normal operatmg condinon> T he ubranon analysts
. Transducer ty pes and their speancations, submittal shoald mJade a summan of' meludmg useful frequency and amphtude ranges
- 1. The theorctwM st r u s t u ral and hydraube
- b. Transducer positions, whhh should be models and analyneal formu at ons ur scimg laws and sufficient to momtor unmficant lateral, verthal, and scale models used m the analy us torsional structural motions of major reactor internal components m shell, beam, and ripd bcdy modes of
- 2. The simctuui and hyaraube system natural ubration, as well as sigmficant hydraulic responses and frequenues and assoaated mode shapes whth may be those parameters that can be used to confirm the mpat exated during steady-state and annapated transient forcing fun non operanon.
- c. Precaunons bemg taken to ensure acquise 1 The esumated random and de termims u" tien of quihty data (e o. optirnuation of synal to-naise foremg tununons mclud:ng any sery low-frequency mo, relatm4 of recordmg t mes to data reduction components, for steady-s:at; and annapated transient requirements choice of mstrumentanon system) opennon
- d. On-hne data evaluauon system to proude
- 4. The < dm, t e d structural and hy d rauh' tmmediate venfionon of general quality and icvel of a
respon ses for ste ad y -stat e and anuapated transient data' operation (The random, determmtsnc, overM1 mtcy; rated maximum respon>e, any very-low fre.iuency components
- e. Procedures for determmmg hequency, of response, and t, e level of cumulatae fatigue damage n
modal content, and maximum values of response.
snould be idenafied )
5 A companson ef the cauated structural
- 2. Test cperating conditions. mcludmg and hydraube responses for pregaanonal and mitial startup test.ng with those for nor:na! operation. (Normal a All steady-state and transient modes of operating conditions that are not a;curately or suffi-operatwn.
1 2 5 0 7,,9 1.20-4
El testmg m
- 2. A tabubtion of spesitte ms;'estwn areas th it j
b Ib plan J Jaranon o
noi m al c; o t.y omes to ensmc thmt eacn cnncal can be u>cd to venf> segments ut the ubranon analy sis conenem d i i a.. bcen sab es ed ii at at 10' and measurement program.
i i! s lb:.!!n c t (I c s m1Falcd a1 !!1e h west l'
t y sles t
qac sy for whnh J,
com;vne n t t.
. wmtb ant
- 3. A de>cuption of the inspection p:ocedate.
strutturai :es;n mc ) { rior to th< tinal m, u tion of :he meadmg the method of exanunation (e g.. usua! and reJsla intern.m
[he da ra!mn of Icsting for non-nondestroCtive surf ac. exammations) method i,f asu.
prom:s pe re u m mternah shudd be no less tLn that mer;tation, accen proustons on th; reactor mternak for tl.e anhaK eference reactor m:emah O e. Vahd.
anJ specia!Ued equipment to be employed danng ita Condinenah or I.mu'ed Yahd Prototy peh s pections to detect and quannty eudence of the effects of ubration lhsposition of fuel a3sembhes (Testm3 t
should be perturmed w nh ie reactor miernals unpor-2.4 Documentation of Results tant to utety and the tuel as>embhes (or Jum:n>
assembhes wiach proude equnalent dy nama ma33 and Thu results of the ubratmo analy sts. measure.
tb chara tensnes t m pesinon The te st may be ment. and mspecnon programi should be reucacd and cendacted without real or dummy fue, anembhes it a
- orrelated to determme the extem to which the test can be show n by analytical or experunenta
- means that acceptance entena are satatied A summan of the sush conditions w d' > teld consers atn e re>ults )
resats should be s ihmuted to the Commmma m the form of prehnunary and final repon,
- 1. The piehnunary repon should sannneve o 2.3 Inspection Program eviuanon of the raw and, n necessary hmned pmc med data ad the rnalts of the m pcenon progam anh The m>pesne program should proude for ta th< test ameptana <mena. AnomJoas data
' "C ' t mspections of the rs miernals pner to and foUow-that could ben on the struc; nal unegnis et the m toi ma operation at ti caJy-state and tran>ient modes t conditions for regulatorv nuanaQ sheu:J he identified, as she dJ the methoc to Ansist ent with N ud f or nakang sud data.
3 posnion C 2 2 2.
T!e reactor.nternals sh ould be remmed trom the icacar vessel for these mspections if 2 U tL reults of he comprehensne ubrenen remos al a not feasible, the ir s;s c tio ris should be as3enment propam re acceptable, the final report perfonned by means et exammanon equipment appro-shou!d melude-pnate for m situ inspectmn The mspection propam shoa!J mJude
- a. A desenption of any denations trum the s p e cihed measurement and mspecnon pregrams.
1 A tabu;ation of a!! rea tor mterna! compo.
includmg instrumentation readmg and mspection anomahes. Instrumentation ma:f unction >. and deviations f.ents and losal areas to be mspected, nJudmg.
from the specified operatmg condinons, All major load-beanng c:ernents of the a
- b. A companson between the measured and reastor internals rehed upon to retam the core support analy tically deter:mned modes of stru ct u r a, and structure m posnmn hydrauhc respense (mcludmg tho>e parameters hom b The lateral. vert a!.
and torsional which the mput forcing function a detenmncd) tor the restramts prouded within the vessel purpose of estabhshmg the vahdt> ot the analy us.a techrnque, c Those lodme and boltmg components w hose fadure ould ads ersely affec t the str uc t u ral
- c. A determmanon of the margm of safety c
associated with normal steady otate and anthipated mtepity of the rea tur internals.
transient operanon, d 'Ihose surf aces that are ir own to be or d.An ev a!uanon of measuren ents that may become contact surfaces dunng operation.
exceeded acceptable hauts not speculeJ a3 test Those critical locations on the reacter acceptance cntena ur of observations th.it were unmuce mter nal components as identaied by the ubration pated and the disposinon of such deviations analy sis.
- 3. It (1) m s pet tiun of the reactor intemah
^
f The inten<
of the reactor vessel for reveals defects. endence of unacceptable monon, c
evidence of loose parts et ureign matenal.
excessive or undue wear, (2) the results from the 125 Ot0 1.20 5
measurement program fail to satisfy the specitied test compoute report should be assumed by the appheant for acceptance entena or (3) the results from the analysis, scheuanng purposes.)
measurement, and mspectwn programs are meonsistent,
- 5. The p:ehmman and tmal reports. whnh the final repert shou:d also melude an evaluanon and desenptmn of the modifications or actions planned m together summante the rauits ' ' tn : ubunor. analpas, order to justify the structural adequacy of the reactor nyasu re men t, an ti mspestio: programs, w iG he pre-mte rnals.
sented to the Commasion wuinn ou and lou Jays, respecinely. of the s omple non at uhunon testmp 4 The enestmn. storace, anc mamtenance of all records relevant to the analysu, mea 3uNment, and
- 3. Comprehensive Vibration Assessment Programs mspection phases et the comprehensne ubration assess-for Non-Prototype Reactor internah ment pregum should be consistent with Regulatory Guide 185, "Collectmn. Storage. and Mamtenance of Non prototype reactm mternals trrportant to Nuclear Power Plant Quahty Assurance Records. ' which safety should be subjected durmg the preope anonal and desenbes a method acceptab:e to the NRC staff for imtial startup test program to all sigmficant flow modes complymg wnh Cotenon NVll. "Quahty Assurance associated with normal steady state and anticipated Records,' of Appenda B. "Quahty Assurance Cntena t unslent operation under the same test condinons for Nudear Power Plants and Fuel Reprocessmg Plants,
unposed on the apphcable prototype. Evaluanon of the to 10 Cf R Part 50 effects of such operation on the structural mtegnty of the non-prototype reactor mterna!s should be based on 2.5 Schedule the results of a comprehensne vibration assessment program developed for the specific non-prototype classi-A schedule should be estabhshed and submitted ficatwn (i e., Category 1, !!,111, or IV). The comprehen-to the Commusmn dunng the construction permit sne vibratwn assessment programs for non-prototype review. The schedule should provide that reactor mtemals are authned below. These programs should be whedule 3 mi documented m accordance with 1 The reactor mternais design w t!! be ciassified the guidehnes for the ;rogram defineated in regulatory in the Prehmmaa Safety Analysis Report (PSAR) as a poutwns C.2 4 and C.2.5 for Prototype reactor inter-prototy pe or a reuhc cateparv of r > wrototy pe. The nal.
classaicano may he.evned m the hd har ty Analysis Repmt if s<hedule changes wnh respes t to the preu-3.1 Non-Prototy pe, Category I oush des:pwd reterence reactor make such reclassife anon app >prute (if the mtemah art classified as 3.1.1 Vibration Analysis Program s
n on-p ro to t y p the apphcam should identify the apph-cabic prototype reactor niemals m the PSAR Expen.
The Vahd Prototype should be specified and mental or a:uh ncal yasniicanon for the non-prototype sufficient eudence should be provided to support the classaication should be presented danng the construe.
classification Non-Prototype Category I tmn perma.cuew )
The vibrahon ar.zysis for the Vahd Proto-
- 2. A comnutmen: wdl be establahed dunng type, which includes a summary of the antiupated the construction permit renew regardmg the ssope of structural and hy dradic response and test acceptance catena, should be iodified to account for the nommal the comprehensne vibration assessment program.
differences that may exist between the Non-Prototype,
- 3. A dexnption of the ubration measurement Category 1, and Vahd Prototype reactor interna:s and mspection phases of the comprehensive ubration assessment program win be submated to the,Com-31.2 Vibration Measurement Program mission m 3a t tiae n t tim e to pe r ant unhzation cf Commnsion recommendanons. (A 90-day comment and The nbranon measurement propam m ay be review penud by the staff should be assumed by the omitted if the u%ection program is implemented.
apphcant for ssheduhng purposes )
If a measurement program is trnplemented :
4 A summary of the nbration an dysis pro-heu of an mspection propam suffiaent and appropnate gram wdl be subnutted to the Commission a mimmum mstrumentation should be incorporated to venfy that of 60 days pnor to submittal of the desenpnen of the the nbratory response of the Non Protaype. Catepry I.
l uhrauen m:aarement and inspection programs. ( As an reactor mternals is consistent with the results of the al te r n a t n e.
the m formatm, m tha report may he uhration analy sis, test acceptance entena, and the submitted to the Co:mmssion in conymetmn wnh the ubratory response obsened in the Vahd Prototype The report specified m regulatory position C.2.5.3. In this vib ratwn measurement program should include a case, a 12nday commen t and renew pened for the desenptwn of the data acquisitwo and reductwn 125 081 l.20-6
operstmg condinons consistent with reccetion systems and test op< atmg condnions con-O systems and test sist ent with the general guvames tor the vibranon the general guidelmes for the ubration measurement measurement program dehneated in regulatory postt.on program deimeated m regulatory pouhon C22 for C22 for Prototype reactor mternals.
Prototype reactor mternals.
v Sufficient and appropnate mstrumentation 3.1.3 Inspection Program should be used to define the vibratory response (i e.
If an mspecuon program is implemented m frequency. amphtude. modal content) of those reactor heu of a ubration measurement program, the guidcimes mternal components important to safety that have been modified relauve to the VahJ Prototype for the purpose inspection program dehneated in regulatory for the of Jemonstrating that the tera acceptance triteria are posinon C23 for Prototype reactor internals should be sausfied and estabbshing the margm of safety.
followed The mspection nrogram may be omitted if Sufficient and appropriate mstrumentation the vibration measurement program is implemented.
should be used to monitor those reactor mternal How es er. if sigmficant discier ancies cust between c:..ponents important to safety that have not been modified relauve to the Vahd Prototype to confirm that anticipated and measured responses for specific compo-the vibratory response of such components comphes nents, those components should be removed from the guidelmes for Non-Prototype, Cetegory !!,
reactor sessel and a usual exammation performad.
with the Compenents for which removal is not feasible should be reactor internals and consistent with the results exammed m situ by means of appropnate inspection obtamed for simtlar components during the measure-equipment In any case, the mterior of the reactor vessel ment program on the Vahd Prototype.
should be usually checked for loose parts and foreign 3.2.3 Inspection Program matenal.
An mspection program that f ollows the 3.2 Non-Prototype, Category 11 guidehnes for the inspection program dehneated in regulatory position C23 for Prototype reactor tnternals 3 2.1 Vibration Analysis Program should be unplemented.
The V1hd Prototype should be specified.
and suthetent endence should be prouJed to support 3.3 Non-Prototype, Category 111 the c'assification Non Prototype. Category II, whrh requires demonstrating that the structural differences 3.3.1 Vibration Analysis Program that cust betw ee 1 the Non-Prototype, Category !!,
and Vabd Prototype reactor internals have no significant The Condiuonal Prototype should be g emnen d effect on the ubratory response and excitation of those ea h ucal or p
unmodified Non-Prototype. Category 11. components.
endence should be prouded to support the classificanon N n-Prototype Category 111, as well as to demonstrate The ubratmn analysis for the Vahd Proto-the apphcabthty ot data from the ubration measurement
~
which mcludes a sumrnary of the anticipated n the Prototype to the Conditional Prototype.
pmgum ts pe, structural and hydrauhe response and test acceptance It should be demonstrated that; cntena. should be modified to account for the structural differences that eust between the Vahd Prototype and Non Prototype, Category 11, reacto: mterrals
- 1. The Conditiona! Prototype a su b-stantially similar in arrangement, design, size, and Test acceptance entena should speciially operatmg conditions to the Non Prototype Category ill, be estabhshed for those Non-Prototy pe. Category 11, reactor mternals.
reactor mternal components with structural differences
- 2. Response modes attnbutable to the relative to the Vahd Prototype.
mservice nbration problems and ensumg component oi operational modifications do not significantly affect the 312 Vibration Measurement Program applicabihty of the results of the vibr:. tion measurement A vibration rneasurement program should be program on the Prototype to the Conditmnal Pmtotype, implemented on the Non-Prototype, Category 11, reactor or response modes attnbutable to the inscruce ubration prob: ems and ensuing component or operational modifi-internals dunng preoperanonal and initial startup eations do affect the applicabdity of the results of the 8
testing.
vibration measurement program on the Prctotype to the The ubration measurement program should Conditional Prototype, but the effects are hmited to include a descnption of the data acquisition and structural components and response modes that permit 1.20 7
Jear separation ut these effects from other results of the regulatory position C.2.3 for Prototyps reactor internal >
ubration measurement program.
shou.d be implemented Detads concernmg the ads me ubration 3.4 Ncn Prototype, Category IV expenense of the Conditional Prototy pe should be prouded, a3 should expenmental or analyncal mforma-3.4.1 Vibration Analysis Program tion whkh demonstrates that the ubranon problems assostated wah the Conditional Prototype hase been The bmned Vahd Prototype should be corrected f or both a and the appheab:e Non-Prototype, specMed. and sufficient endence should be pr uded to Category lit, reactor mternals.
supp ;rt the dassification Non Prototyp(, Category IV.
The ubrauon analy sis on the Prototype t the Condiuonal Prwutype, which meludes a summary of.
3.4.2 Vibration Measurement Program the anucipated structural and hydraube respone -d A uhration measurement propam may be test acceptance enteria for the measurement propani on omated if the mspection program is implemen'ed.
the Prototy pe. should be modihed to account for the component or operatwnal moddicanons apphcable to if a measurement propart is unriemented in the Condiuunal Protot> pc and Non-Prototype Categen heu of an mspesuon propam, sufficient and appropnate lil. reastor miemais-mstr2 mentation should be incorporated to venfy that the ubratory response of the Non-Prototype, Category Test aaeptance entena. with permisskle IV. reactor mternals is consistent with tne results of the deuations. shuu:d be specified for reactor mternal ubrauon analy sis. test acceptanse c ritena, and the components unportant to sa fe t y. Each component vibratorv response for the referene d I mited Valid should t - categonzed accordmg to whether the usults Prototype from tne ubrauon measurement propam on the Proto-type te the Condaiona! Prototype are apphcable.
The vibration measurement program should be consistent with the guidehnes delineated m regulatory 3.3.2 Vibration Measurement Program posinon C.3.1.2 fer the measurement program for A vWration measurement propam should be on the Non-Prototype, Category IIi, implemen ted 3.4.3 inspection Program reactor internals dunng preoperationa! and nuttal startup testmg.
If an mspection program is implemented in hea of a ubratwn measurement progam, the guidelines Sufhcient and apprornate instrumentation for the inspection p.opam delmeated in regulatorv should be used to denne the ubrator) response of those position C.3.1.3 for Non-Prototype, Category 1, reactor reactor components important to safety which, because internals should be fo' lowed.
of structural or operational modiGeations relauve to the ongmal design of the Condinonal Prutotype, are expected to have response charactenstics substantially different from th ose measured for that component D. IMPLEMENTATION during the vibration measurement propam on the Prototype to the Conditional Prototype.
Tne purpose of this section is to provide guidance to apphcants and licensees regardmg the NRC staffs plans A!1 other compon:nts should be momtored for ut luing this regulatory guide.
with suf ficient and appropnate instrumentitma to con-firm that the measured response for each component is substantially smn!ar to that obtamed dunng the ubra-Except m those cases m which the applicant proposes tion measurement propam on the Prototype to the an acceptable alternative method for complying with Conditional Prototvpe-specubt portions of the Commission's regulanons, the method c senbed herein wal be used m the evaluatwn The ubrauon measurement program should of submittals for operatmg licen.,e or construetwa satisfy the gencal guidelmes for a Prototype measure-pernut appla anons Jodeted arter June 22.1970 l
ment propam as dehneated in regulatory position C.2.2.
3.3.3 Inspection Program If an apphcant wishes to use this regulatory guide ut developing submittals for apphcations docketed on or An inspectw n program that satisfies the before June 22, 1976, the pern pmnons of the guidelmes for the mspection program dehneated in appheation will be evaluated on the basis of this guide.
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