ML19221A843
| ML19221A843 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1974 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.012, REGGD-1.012, NUDOCS 7907100077 | |
| Download: ML19221A843 (3) | |
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s Revision 1 U.S. ATOMIC ENERGY COMMIS&lON
[(M REGU LW~O RY G U D D E h,'a rn c' DIRECTORATE OF REGULATORY STANDARDS REGUL ATORY GUIDE 1.12 INSTRUMENTATION FOR EARTHQUAKES
- A. INTRODUCTION appropriate locations to provide dau on the seismn input to containment, data on the frequency, amphtude.
Paragraph (c) of & 50.36 "Te c h nical and phase relationship of the seism:c respor.se of the 4
SpeciGc at o ns," of 10 CFR Part 50, "Licensmg of contamment structure, and data on the seismic input to Production and Utibzation Faedities," provides that the other Seismic Category I structures, syst ems, and technical speciGcations wdl include surveillance tomponents. It is desirah!e that these strong monon requirements to assure that the necessary quahty of accelerographs be located so as to facihtat e the sy stens and components is mamtained, that facility engmeering analysis of the recorded traces foHowmg an operation will be within safety hmits, and that the earthquake.
hmitmg conditions of operation will be met. Appendix A. " Seismic and Geologic Sitmg Criteria for Nuclear ne acceleration value correspondmg to zero penod Power Plams," to 10 CFR Part 100, " Reactor Site in the containment foundation design response spectra Cntenal' requires, m Paragraph VI (aX3), a suitable may be referred to as the " acceleration level" of the program for implementmg this requirement wirl.rgard to seismic instrumentation needed to determme mput design earthquake motion to the containment st ruc tu re. His acceleration levei n an important promptly the seismic response of nuclear power plant parameter because the magrutudes of the design response features important to safety to permit companson of spectra themselves are affected to a large extent M thn siich response with that used as the design basis. Such a level, and the plant shutdown requirement as specified m rompanson is needed to decide whether the plant can Appendix A to 10 CFR Part 100 is also related to thn continue to be operated safely. His guide desenbes level. It is therefore necessary to insta.ll a triaual seisma s e tsmic instrumentation acceptable to the AEC switch at an appropriate location in the basemen t R e gu la t ory staff as sattsfymg the above stated capable of providmg an immediate signal to remotely requirements of Appendix A to 10 CFR Part 100. nis indicate if the speciGed zero pened acceleration has guide does not, however, address the need for been exceeded. Dus can provide the basis for immediate mstrumentation that would automatically scram a administrative procedures if needed.
nuclear power plant or specify the methods to be used in the analysis of recorded data. He Advuory Committee on Reactor Safeguards has been consulted concerning Appendix A to 10 CFR Part 100 requires that aU this guide and has concurred in the regulatory position.
the structures, systems, or components of a nuclear power plant necessary for continued operation without undue nsk to the health and safety of the pubhc be B. DISCUSSION designed to remain functional when subject to 1he When an earthquake occurs, it may not he known Operating B asis Eartnquake (OBE). Since the immediately how severe the efTects of the earthquake zero-period scceleration of the contamment foundann are on a given nuclear power plant. It is advisable to have design response spectra representmg the OBE may om fully desenbe the seismic event,it is important to have a t r ia xial time-history accelerographs ' installed at t najual response spectrum recorder mstalled at e
- Dis guide is a revision of Safety Guide 12.
appropnate location in the basement of the plant capable of providing immediate signals for remote
' See ANSI Standard N18.5, " Earthquake Instrumentation indicatmg m the control room if any si runcant Portion 8
Critens for Nuclear Pnwer Plants, for definitbns.TNs standard of the foundation design response spectra has been is available frorn the Arnerican Nuclear Society,244 East Ogden Avenue. Hinsdde, Ilhnois 60521.
exceeded. Uus can provide additional basn for me d*oas USAEC REcuLATORY QUIDES c op se of esta.shed p. des a., tie ce. ned tiv rowsee.reens come ced to the U S. Atornac E nery, Corrw=esea. Wome8*agtoa. Of M545 Mr A ttentica Director ce Reewiseory siearnetts Commeate are suerstmas Repwastery Guedes are *esued to descree end meme eveaetre to the owtie c l *g>rovemoars en pose posee are emoouraged ead sh ed tuo esat to tae Sentary erwehos ocasetense to the AEC Regwistory sieff of impaea.aomg spectf.c perte of tDe C.
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immediate adminatrative precedures on decisions-Nuclear Pc wer Plants," is acceptable ir ihe Regulaton immediately fouowmg an earthquake.
staff for satisfying the seismh mstrumentanon requiremer.ts indicated in Paragraph VI (a) (M of he effects.o the seismic motion at a given floor Appendix A to 10 CFR Part 100 for anunng ihe safety level m a uructure an ne represented by calculated of nuclear power plants. subject to the following-Coor respon>< spntra. In many of the nuclear power plants. cakm2ied fWr respense spectra are also used to 1.
The irstrumentation called for m Seconn 4.1 of the design seis m s Crewn I systems and components Standard should be apphed to nudear power plant wiih supponed a tese esels it is therefore important to a Safe Shutdown Earthquake maumum loundanon mst a' ria na.
re'pomeapectrum recorders at the acceleration of less than 0.3 g as supplemented b) the se!ceted wppm Inmn locanons to determine if the following calculaied de repense spectra hase been exceeded.
This mfermatmo wu be needed to determine (1) the a.
Instead of the locations specified in Section consen ansm n the rrodelmg and design assumptions 4.1.2 of the Standard, one tnaxial peak accelerograph made for the snueture and des!gn input rnotion to the should be provided at one location of each of the su ppo rted sy stems and components and (2) the following-advisabihty of connnumg the operation of the plant (1) A selected location on the reactor without a safety analy sis following an earthquake.
equipment.
(2) A selected location on the reactor piping.
De matrouJe of the resp (mse of the s><tems and (3) he most pertinent location on one of the components supported on the containment structure is following outside of the containment structure required n order ta venf3 if the actual response of these (a) Seismic Category I equipment.
part s has exceeded the des:gn ba s2s. His can be (b) Seismic Category I pipmg.
2 monitored by mstallmg tnaxial peak accelerographs over selected Icutions on these parts. In addition, peak b.
One triaxial response spectrum recorder '
response of these parts w,ll be necessary to determine capable of messunng both horizontal motions and the the conservansm in the modeling and design assumptions vertical motion and capable of providing signals for made for these systems and components.
immediate control room indication should be provided at the containment foundation.
De seventy of response of a given Seismic Category I structure wili depend to a large degree on the c.
One tnarial response-spectrum recorder capable maximum a c c eleration of the Safe Shutdown of measurmg both horizontal motions and the vertical Earthquake at the foundation of the containment motion should be provided at one location of each of structure. It is therefore reasonable to relate the amount the following:
of mstrumentanon desirable to the magrutude of the it) A selected location on the reactor maximum c apected foundation acceleration. For this equipment or piping supports.
purpose. Safe Shutdown Earthquakes are divided into (2) Re most pertinent location on one of the two cat e genes ti) eart hquakes with maximum following outside of the containment structure-foundanen accelerations of less than 0.3 g, and (a) A seismic Category I equ pment (2) earthquakes wit h ma ximum foundaGon support or appropnate Door locatio-accelerstmns of 0.3 g or greater. ne earthquakes in the (b) A Seismic Category I ripmg support or first category may be termed as rangmg fror" moderate appropnate floor location.
to strong, and the earthquakes in the secono category (3) At the foundation of an independent may be called severe. T1us guide prescnbes appropriate Seismic Category I structure where '.he,esponse is mstrumentation for monitoring these categones, different from that of the reactor containment structure.
Working Group ANS-2.2 of Subcommittee ANS-2, 2.
Section 4.2 of the Standard should not be used.
Sue F valu a non. of the Ame nca n Nuclear Society S:andards Co m mit t ee.
prepared ANSI N 18.5, 3.
The instrumentation specified m Section 4.3 of the "Earthqune instrumentation Cnteria for Nuclear Power Standard should be apfied to nuclear power plants with Plants." which contams most of the criteria with respect a Safe Shutdown Earthquake maximum foundation to loca non and number of instruments, mstrument acceleration of 0.3 g or greater as supplemented by charactenstics. and instrumentation station mstallations Regulatory Positions 1 and 2 at ave, and the following specified in th;s guide.
a.
Instead of the 'ocations specified m Section C R EGULATOR Y POSITION 4.3.2 ef the Standard, one t riaxial time-history accelerograph should be provided at the most pertment F art hq a A e instrumentation spen fied in ANSI N lh A.
" Ea rt hq uak e instrumentation Cntena for
- An mstrurnent having the espatntity when actuated of permanently recording peak rerponses as a functon of
- ANSI Nik 5 for denmt ons.
freq uency.
1.12-2 125 00
J location on one o' t he independent Senmk Category I be provided at a selected io at.on on reactor equipment s
st r a a t.r e s where the response is dif ferent trom that of supports or piping supports.
ihe reactor coni.unment structure.
4 The response. spectrum returders should have the h
Irsicad of the locations spect6ed in Section following specifications
- 4. t. I of the Standard, one trianal peak accelerograph a.
Dynamic Range 50 t tern to peak (su h n should be provided at the most pertinent location on 0.02 g to 1.0 g).
Seismic Category I equipment or piping m an independent Seismic Category I structure where the response is difTerent from that of the reactor b.
Frequency Range-minimum coserage f rom I tu to 30.0 lb.
containment structure.
Damping-not less than nominal 2' nor more c.
In addition to the locations specified in c.
Regulatery Positions l.b.. l.c.(1), and I.c.(3) above. ene than nominal 5"1 of entical damping, controlled to triacal response. spectrum secorder should be provided 20.15 of nominal. The actual amount of damping is 'o at one location on both items speci6ed in Regulatory te consistent with the OBE. based design damping for Positions 1.c.(2Wa) and 1.c.(2Xb) above.
the supported structure or equ pment.
d.
Instead of the locations specified in Section Instead of the dynamic range specified in Section 4.3 4 of the Standard, one tnaxial seismic switch should 5.3.5 of the Standard, a range of 100 I should be used.
h 125 044 1.12 3