ML20210T587

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Advises of Transfer of Region III Lead Responsibility for Resolution of 860131 Earthquake/Seismic Event at Plant to NRR Per 860204 Telcon W/G Lainas.Util 860211 Seismic Event Evaluation Technical Presentation Agenda & Viewgraphs Encl
ML20210T587
Person / Time
Site: Perry, 05000000
Issue date: 02/06/1986
From: Paperiello C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Bernero R
Office of Nuclear Reactor Regulation
Shared Package
ML20195C722 List:
References
FOIA-86-91 NUDOCS 8605300696
Download: ML20210T587 (47)
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Text

{{#Wiki_filter:._ gno sed u,etTED STATES f*, 4 NUCLEAR REGULAf03Y COMMisslON i h. S nEcios m 5 799 ROO$EvtLT NO AD g GLEN ELLYN. 4LLAPeOl5 64137 FEB 6 1986 MEMORANDUM FOR: Robert M. Bernero, Director, Division of Boiling Water Reactor Licensing, NRR FROM: Carl J. Paperiello, Director, Division of Reactor Safety, RIII

SUBJECT:

TRANSFER OF LEAD RESPONSIBILITY FOR RESOLUTION OF THE EARTHQUAKE / SEISMIC EVENT AT THE PERRY NUCLEAR POWER PLANT As you are aware, an earthquake occurred in the vicinity of the Perry Nuclear Power Plant on January 31, 1986. The recorded seisr:ic forces to which the plant was subjected, based on instrumentation data, need tc be reviewed and evaluated by your staff for cortparison with design criteria. The licensee is currently in the process of analyzing this data. Per my conversation with Gus Lainas on February 4,1986, the Region is hereby transferring the lead responsibility for seismic review and resolution to NRR. 7 o Carl J. Pa eriello, Director Division of Reactor Safety cc: C. E. Norelius, RIII E. L. Jordan, IE J. J. Stefano, NRR R. A. Hennann, NRR 8605300696 860321 PDR FOIA HIATT86-91 PDR M

= o l THE CLEVELAND ELECTRIC ILLUMINATING COMPANY SEISMIC EVENT EVALUATION TECHNICAL PRESENTATION ] AGENDA FEBRUARY 11, 1985 a INTRODUCTION & OVERVIEW M. R. EDELMAN PLANT STATUS AND RESPONSE R. A STRATMAN EARTHQUAKE ANALYSIS R. HOLT AND SEISMICITY WESTON GEOPHYSICAL 1 PLANT SEISMIC DESIGN EVALUATION DR. C. CHEN GILBERT Com0NWEALTH

SUMMARY

AND CONCLUSIONS M. R. EDELMAN e t t

PLANT STATUS PatoR To SEISMIC EVENT ONG0 LNG IESTING, CALIBRATION, WORK ACTIVITIES o PREPARATION FOR DIVISION 11 DIESEL GENERATOR IESTING o 0 STARTUP SOURCES NOT YET MOVED SYSTEMS ENERGlZED (IN OPERATION AND STANDBY MODE) ~ O SAFETY SYSTEMS NON-SAFETY SYSTEMS ( w 1 e r- ,-,.3-, -.u, w-,_my_-- 9 e-w w .9 p--e--

PLANT STATUS SYSTEM G33 REACTOR WATER CLEANUP A & B PUMPS WITH FLOW TO THE MAIN COND. AT 55 GPM NO FILTER /DEMINERALIZERS IN SERVICE G41 FUEL POOL COOLING AND CLEANUP A PUMP RUNNING B FILTER /DEMINERALIZER TRAIN IN SERVICE M35 TURBINE BUILDING COOLING B FAN RUNNING AND VENTILATION M41 HEATER BAv VENTILATION B FAN RUNNING M45 CIRCWATER PUMP HOUSE A AND B FANS RUNNING VENTILATION N21 CONDENSATE A HOTWELL PUMP IN SHORTCYCI.E CLEANUP A, B, C CONDENSATE BOOSTER PUMP LUBE 0!L PUMPS N23 CONDENSATE FILTRATION f!LTERS B, C, E N24 CONDENSATE DEMINERALIZERS DEMINERALIZERS A, B N32 TURBINE CONTROL (EHC) RECIRCULATION PUMP RUNNING N71 CIRCULATING WATER A & B PUMPS RUNNING B, C, D LOOPS IN OPERATION COOLING TOWER IN BYPASS P11 CONDENSATE TRANSFER NORMAL PUMP RUNNING B PUMP IN STANDBY P20 WATER IREATMENT A AND B COAGULATORS IN SERVICE P21/22 Two BED / MIXED-BED B STREAM IN SERVICE DEMINERALIZERS B SULFITE PUMP RUNNING B AND C CLEARWELL PUMPS RUNNING P41 SERVICE WATER B AND C PUMPS RUNNING l 4 P43 NUCLEAR CLOSED COOLING B AND C PUMPS RUNNING A HEAT EXCHANGER IN SERVICE P44 TURBINE BUILDING CLOSED B AND C PUMPS RUNNING COOLING A HEAT EXCHANGER IN SERVICE i

, - ~, - SYSTEM PLANT STATUS. P52 INSTRUMENT AIR UNIT 1 COMPRESSOR RUNNING PSS BUILDING HEATING A PUMP RUNNING P61 AUXILIARY STEM B BOILER C BOILER FEED PUMP P62 AUXILIARY BOILER FUEL Dit B FUEL OIL PUMP P72 PLANT UNDERDRAIN PUMPS IN AUTOMATIC C11 CONTROL ROD DRIVE A PUMP A FLOW CONTROL VALVE C41 STANDBY LIQUID CONTROL IANK HEATERS ENERGlZED C71 REACTOR PROTECTION SYSTEM ENERGlZED 017 PLANT RADIATION MONITORS ENERGIZED E12 RESIDUAL HEAT REMOVAL XEEP Fitt PUMP FOR LOOPS B & C E21 low PRESSURE CORE SPRAY KEEP FILL PUMP FOR LPCS AND RHR LOOP A E22 HIGH PRESSURE CORE SPRAY KEEP FILL PUMP FOR HPCS F42 FUEL TRANSFER EQUIPMENT ENERGlZED Mll CONTAINMENT VESSEL COOLING B, C, E, F FANS RUNNING M13 DRYWELL COOLING 1A, 2A, 3B FANS RUNNING B LOOLING Coll M15 ANNULUS EXHAUST GAS IREATMENT A TRAIN RUNNING B TRAIN IN STANDBY M21 CONTROLLED ACCESS VENTILATION A TRAIN RUNNING B TRAIN STANDBY M23/24 MCC SWITCHGEAR & MISC. A IRAIN RUNNING AREA VENTILATION / BATTERY ROOM B TRAIN STANDBY EXHAUST M25/26 CONTROL ROOM VENTILATION / A TRAIN RUNNING IN NORMAL MODE EFidRGENCY RECIRCULATION MODE 'B IRAIN STANDBY M27 COMPUTER ROOM VENTILATION A FAN RUNNING

1 PLANT SYSTEM SYSTEM M32 ESW PUMPHOUSE VENTILATION A AND B FANS RUNNING 1 M40 FUEL HANDLING BUILDING 8 AND C EXHAUST FANS 1 VENTILATION 23 IAN RUNNING M43 DIESEL 6ENERATOR BUILDING VENTILATION P45 EMERGENCY SERVICE WATER A AND B PUMPS RUNNING WITH ALL LOADS VALVED IN P47 CONTROL COMPLEX CHILLED A CHILLER RUNNING WITH NORMAL LOADS A CIRCWATER PUMP RUNNING WATER P49 EMERGENCY SERVICE WATER BOTH SCREENS OPERATING j SCREEN WASH i RECIRC PUMP (CONSTRUCTION) RUNNING P54 FIRE PROTECTION NO INTITIATION OF C0, HALON, OR 9 SPRINKLER SUPPRESSION SYSTEMS O e O W ( 5 e p ~ e.

m _ I e I IN3PECTt0NS 313 C"lDitl33 FoLLowtNs Setssic Event l 0 OPERATOR SURVEY (No SrRuCTURAL DAMAGE) 0 WALKD06fMS BY PLANT MAINTENANCE PERSONNEL (N0 STRUCTURAL DAMAGE) 4 o SYSTEMATIC PLANT WALKDOWNS BY 65 ENGINEERS AND IECHNICIANS (No STRUCTURAL / EQUIPMENT PAMAGE) IDENTIFY AND D0cVMENT ALL DISCREPANT CONDITIONS ,N' "E d L180 DaSERvATIONS DOCUMENTED (MINOR ITEMS)

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/ b7 A Tey- - ($dJ*h O ADDITIONAL INSPECTIONS / SURVEYS SITE SURVEY PLANT SETTLEMENT SURVEY C00t!Ne TOWER WALKDOWN-O SE:SMIC CLEARANCE l 4SPECTION j O ENERGIZE 0 ELECT aC L EQu!PMENT STUDY 4 _ O ONGOING SURVE!LLANCE (SVI'S) 0 NE.v PROCEDURE ASSURES CE!/NRC REVIEV 0F ALL POTENTI AL EARTHQUAKE-RELATEJ ITEMS REvtsv AL_ WORK REaueSTS FOR RELATIONSHIP TO EARTHQUAKE NO WORK c:4 EARTHQUAKE-RELATED OR INDETERMINATE CONDITIONS WITHCUT CEl/NRC REvtEW 4 -l .._,..J. _m..

l l MAIN SHOCK January 31,1986 origin time : 16 hr 46m 42.3 8 U.T. latitude : 41.649 N longitude : 81.105 W focal depth : 10 Km i based on : 64 stations (worldwide) M=49 b M big = 4.96 location : Geauga County Near intersection of i Highway 86 and 166 i est. distance to plant : 11 miles 17.7 km based on : NElS solution l i ...-_.-__----..-_...._j

EARTHQUAKE MAGNITUDE & INTENSITY 4.96 M BLG - USGS (EQUIVALENT RICHTER SCALE) MODIFIED MERCALLI INTENSITY VI - PRELIMINARY - WESTON GEOPHYSICAL e QUESTIONNAIRE e REPORTED EFFECTS FEW DAMAGED CHIMNEYS CRACKS IN WALLS CRACKED / FALLEN PLASTER BROKEN WINDOWS WELL-WATER EFFECTS /

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SAFE SHUTDOWN EARTHQUAKE MODIFIED MERCALLIINTENSITY = Vll l PEAK GROUND ACCELERATION - 0.15 g REGULATORY GUIDE 1.60 SPECTRA l SITE SPECIFIC SPECTRA e 5.3 M8LG .5 5.5 M BLc i.3 l l i l l l

I i FIFTY-MILE SEISMICITY i RELATIVELY LOW SEISMICITY I I NO CAPABLE FAULTS t l i HIGHEST INTENSITY - MODIFIED i MERCALLI Vi HIGHEST MAGNITUDE -4.96 M sts E l k i i

j CONCLUSIONS I TECTONIC PROVINCE APPROACH STILL VAllD e NO CAPABLE FAULT e NO TECTONIC STRUCTURE SAFE SHUTDOWN EARTHQUAKE INTENSITY e MODIFIED MERCALLI Vil vs. VI SITE SPECIFIC e 5.5 t.3 vs. 4.96 e 5.3 i.5 vs. 4.96 EXCEEDANCE OF SAFE SHUDOWN EARTHQUAKE e SHORT DURATION (< 0.5 sec.) e HIGH FREQUENCY (20 Hz) e EXCEEDANCE ABOVE 84% EXPECTED i ..__.r-.-, ___a _n

CHARACTERISTICS OF THE 1986 OHIO EARTHQUAKE o HIGH FREQUENCIES e SHORT DURATION e LOW ENERGY e LOW VELOCITY e SMALL DISPLACEMENT CH ARACTERISTICS OF THE PERRY DESIGN BASIS EARTHQUAKE (SSE) e BROAD BAND FREQUENCIES e LONG DURATION e HIGH VELOCITY e LARGE DISPLACEMENT e HIGH ENERGY i

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= :

9 G I s< I d.m

s..,rr. =

i (. ..= .. = in. = . i.. a.= 33.5 !=,,p e=os. rwn-.,,is.m r= ranwr-, ~.... - -. Ii;.1.u,':lllh.w..;.;l.l.'G.. dTT,*it:.h-"".""" I:.'"i.,.,.,JT I'W= ii ; Nm.. I '==. 's =' =a-1 i, 1R - 3 a ic a i. I* 3 4 a g. E ,s l .g. E $. >.Yh{dWNl., \\1ls*U.ek,HfiN=^==:-;- - - : 1 ^^^ i -,; -:

^^

- ~ - -- - - = l y e L ...E s .:s a i. ,s s

1 Jr!

( ( x: s

i. u v.m i i.u is.u i i. m s i.

is.u v r..m.s =, w. u, r.si..o r.. tant := sie nins es.u .s s n

1 SEISMIC DESIGN BASIS e BROAD BAND FREQUENCY DESIGN RESPONSE SPECTRA e SMOOTHED,84 PERCENTILE SPECTRA l i e COMPOSITE TIME HISTORIES WITH LONG DURATIONS AND HIGH ENERGY 1

\\ \\ / 23 / \\ M \\ \\ 10 / l g)g%% ~ K%"iM2 ~ j V,#x 6 %N ~ ~ ~

  1. <g l

^2$hM6 6M6< 5 ^ p.,A w^ J A v v -[Ob Ob[NI [b 0.1 0.2 0.5 1 2 5 10 20 50 100 FREQUENCY, eps FIGURE 1. HORIZONTAL DESIGN RESPONSE SPECTRA - SCALED TO Ig HORIZONTAL GROUND ACCELERATION l e __m.. m

l D j.5_- u; k. h b k ,c vu=g

7 m_,,

_= b gNbG-s. .! Q ['~~ 5- ,h ik O P! E es

q Mij _'

g- _S m-' - @ J~@ 49 t h E.::-

572,~

is I ,......, / _',yI T__@.__ o' ! "_E7' T "

  • , p*

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i =O ='::- ' E ~ -' M " a g,p

r. -= P a:===n
=

a

p -

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il.

j ,i +w e i N kI g" hv M M gE"""3R

7mlrt 4

g 4 p, w 7 _ l... e = n n , m ._G

  • g,

-=.] g h gi.. fd '*I O.- 4 iH'S n.. =Q G' o.oapar.

  • r ---

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?;ggy O EI hO g g r.~..Z h.~--d, I '.m_: gen _,' g ( =w=- d - - - ~ T. .,.., ~ ' g, s iF-~ p 5 pm = _..... rM. "3 7 u m-m. -. g.., i g: --A:.-9m==,

  • "~_...A*

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- y Z" ", m 'g; M

k :.~D7.' [ ? hh_gany.8 g[pNMF4h hOSIh Cl E}.0 90 G') o ;g l ,n ;.YI U*a / h is~ / #[8 ** ,9)b'i 5 7 o v C"- w i .N==ta.#11..' [Lj J%9 g w.e /4, ky? A: .a $ _gt a,r, o-9,cii SJ rpa 9 = Ql.'.}@ .R.g 6 -Z1 dh6anaxM b= Tdem i, a -m....- M I .gy h {, 5 a n e es.- 2 [ 1 t is u 3 J u s j,l j u f F_D 6 k @ Instrument #D51-N101 7 3 g @ Instrument #D51-N111 l @ Instrument #D51-R120 @ Instrument #D51-R140 @ Instrument #D51-R160 @ Instrument #D51-R170 @ Instrument #D51-R180 @ Instrument #D51-R190. --..------ ~

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  • EiS ld bikI u df- ~ 'di{i

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  1. D51-N101 R/B Foundation Mat, El. 575', Az.175' 2.
  2. D51 N111 R/B Containment Vessel, El. 686', Az.174 3.
  3. D51-R120 Reactor Recirc Pump, El. 605', Az.145' 4.
  4. D51 R140 A/B Foundation Mat, El. 568' 5.
  5. D51 R160 R/B Foundation Mat, El. 574' Az. 225' 6.
  6. D51 R170 R/B Platform, El. 630' Az. 238' 7.
  7. DL1-R180 A/B Foundation Mat, El. 568' 8.
  8. D51-R190 A/B Foundation Mat, El. E68'

Page 1 cf 2 PERRY NUCLEAR POWER PLANT UNIT NO.1 l SEISMIC Mt'rflTORING INSTRUMENTATION TABLE IV I i Type Manufacturer / Model Number Location References Reactor Building F D51-N101 (1) Kinemetrics / 5MA-3 Figures A and 8 E io 10 Azimuth 175' Reactor BuildingPage f,onta nme Figures A and C e5 D51-N111 (1) Kinemetrics / SMA-3 ,, g ,0 Azimuth 174* Reactor RetirculationPump D51-R120 (2) Engdahl/ PAR-400 (Inside Drywell, Reactor Building) Figures A and D j Elevation 605 -0, ( Approximately) i Azimuth 145' l I l D51-R130 (2) Engdahl / PAR-400 0UT O F 5 E R VIC E 't 1 1 Auxiliary Building D51-R140 (2) Engdahl / PAR-400 f*H Figures A and E nda o Ma p { Elevation 568'-4" l 4 1 Trianial Time-History Accelerograph 4 2. Trianial Peak Accelerograph 3. Triaxial Response Spectrum Recorder

Page 2 of 2 i l i PERRY NUCLEAR POWER PLANT UNIT NO.1 } SEISMIC MONITORING INSTRUMENTATION f TABLE IV i i in r nt Type Manufacturer / Model Number Location References i Reactor Building F " D51-R160 (3) Engdahl / PSR-1200-H / V-12A gures A a f I i E ai 57 ' 10 j Azimuth 225* j Reactor Builtiing 630' Platform I d O' Figures A and G D51-R170 (3) Engdahl / PSR-1200-H / V O 1 Azimuth 238* j i P/4 l I Auxiliary Building i I" i Mt D51-R180 (3) Engdahl / PSR-1200-H / V Figures A and H S ug R l Elevation 568*-4" l } Auxiliary Building at Ma D51-R190 (3) Engdahl / PSR-1200-H / V Figures A and j p p ] Elevation 568*-4" i 1 i 4 j 1. Trianial Time-History Accelerograph j 2. Trianial Peak Accelerograph j 3. Triarial Response Spectrum Recorder

ZPA COMPARISON e ZERO PERIOD ACCELERATION e RECORDED ZPA'S VARY FROM BELOW OBE VALUES TO 74% OF i SSE VALUES i e EXCEPT AT CONTAINMENT VESSEL ELEVATION 686' e BUT RELATIVE DISPLACEMENTS AND STRESSES HERE (AS WELL AS i ALL OTHER LOCATIONS) ARE LOW REASON: ~ e HIGH FREQUENCY AND LOW ENERGY OF THE 1986 EARTHQUAKE I i ., ~. - - - -.. - v--., v...

e~--

e --r s,y-,.. - --,-w .w.-.,w.. v-~w,

TABLE 11 Comparison of Design ZPA's' VS Recorded ZPA's ( Expressed in g values) l Auxiliary Building Reactor Building Reactor Building Reactor Building Reactor Building

l Foundation Mat Foundation Mat Recirculation Pump Platform Containment Vessel j

Elevation 568* Elevation 574'-10" Elevation 605' Elevation 630' Elevation 686' PAR 400(Engdahl) SMA-3 (Kinemetrics) PAR 400(Engdahl) Inside Drywell SMA-3 (Kinemetrics) D51-R140 D51-N 101 D51-R120 PSR 1200(Engdahl) D51-N111 D51-R170 Recorded .17 .18 .32 .09 .55 NS SSE 17 .18 1.06 .48 40 OBE .10 .10 .86 .40 .24 Recorded .06 .10 11 .16 .18 EW SSE .20 .18 1.06 48 .40 OBE .10 .10 .86 .40 .24 i Recorded .03 .11 .05 Note 2 .30 VERT. SSE .20 .18 .47 .28 .24 j OBE .10 .10 .38 .16 .15 i Recorded .18 .23 .34 Note 2 .65 5A55' .55E* .33 .31 1.57 .73 .62 OBE .17 .17 1.27 .59 .37 I 1 Zero period acceleration 2 ZPA indeterminable from available data 3 Square-root-of-the-sum of the squares l 4 Licensing basis is SSE

1 TABLE I Comparison of Design Displacements' V5 Recorded Displacements' ( Expressed in centimeters /one inch = 2 54 cm) COLUMN 1 COLUMN 2 CO L U M N 2 minus C O L U M N 1 Reactor Building Reactor Building Relative Displacements Foundation Mat Containment Vessel for the ,l Elevation 574*-10" Elevation 686* Containment Vessel SMA-3 ( Kinemetrics) SMA-3 ( kinemetrics) D51-N 101 D51-N111 Recorded 0 09 0.17 0.08 NS 55E 0 044 0 28 0 24 OBE 0.023 0.17 0 15 i Recorded 0 16 0 21 0 05 EW SSE 0.044 0.28 0 24 OBE O 023 0.17 0.15 Recorded 0 05 0.07 0 02 VERT. SSE 0 02 0.37 0.017 OBE O013 0.022 0.009 1 4 Recorded 0.1 8 SRSS SSE 0.34 i Ott 0.21 t l l 1 i 1. Displacements based on same time-step to determine relative displacements 2 Square-root-of-the-sum of the squares .l

RESPONSE SPECTRA COMPARISON PERRY DESIGN RESPONSE SPECTRA ARE FAR ABOVE THE RECORDED SPECTRA IN THE FREQUENCY REGION BELOW 14 Hz. 2 1 e CERTAIN RECORDED RESPONSE SPECTRA EXCEED DESIGN SPECTRA VALUES IN THE REGION AROUND 20 Hz. e CORRESPONDING SMALL DISPLACEMENTS (EXAMPLE: 3/100 INCHES OR BELOW AT FOUNDATION MAT) e NO ENGINEERING SIGNIFICANCE e RECORDED VELOCITY SPECTRA SHOW MUCH LESS ENERGY THAN THE DESIGN RESPONSE SPECTRA i l

11A8002 PERRY NUCLEAR PDi'ER PL ANT COM? U? SMA35/N 165-2 (( DAMP;NG VALUES ARE 2 PERCENT OF CRITICAL FREQUENCY - HZ 10 1 -1 10 g... a.... .....-1: 1 .d F PSA - G SD - IN 10' s ( L2 1 ! 0 16 I i \\ )[ ~ ,S - CM 6 t s ' l . $10 .s a ,g. \\ _, z l)n si ~ o N -2

1. 1 0

RECORD b _i ic I 1 ~ , -2 -3 0 s;g2 i , -s .q- -1' f 10 -i i 10 1 to PERIOD - SEC // (/

11AE002 PERRY NUCLEAR POWER PLANT COM? WEST SMA35/N 165-21 ( DAMP 1NG VALUES ARE 2 PERCEN! OF CRITICAL g ~REDUENCY - HZ 10 1 10 g... g... s ...-10 l g 1 i .PSA - G SD - IN DES N l ' *2 CK Ed, l' ~ O f* 1 2 s3g -10, I SD - C.M 1 i (M ~ s10 \\. 1 D'I ,e z s 10,' p s1 m en 1 -2 l, ~ 1 30 REcoRb N'c _s '10 1 ~ -2 3 l si O'I 1 ~ 1. . -3 I i ~ 10 7 10 1 10 L PERIOD - SEC --y _e., ,___,_.m ,_..,--y.., 3

. -...,... s v r. r s t ub i v e. K Y 31. i 956 llAE002 PERRY NUCLEAR POUER PL ANT CO.MP SOUTH SMA35/N ; 6 5-Zi ( DAMPING VALUES ARE 2 PERCENT OF CRITICAL ( .REQUENCY - HZ ) 10 1 1 10 d 3... a.. . s. t i.... -j 0 ; ~ l y i t PSA - G '. l 'o r DES N SD - IN ~ G T4 .8' i \\ ,o SSE N02 je* 2)L i ~ 1, I ,id i.o' I SD - CM ,~ 4 1 i sia U i, 1 0, 3 I =

s m

m 1 to a 1 i. -i 1 RECORDED -2 0 . ~10 ' f O -2 1 1 -3 .0 -2 '10 -3 ~, 1 L i ,,,,,e b -1 ,....,i 10 1 10 L r .._._,,.,y v--

h1 Ascot PERflY NUCLEAR POWER PLANT COM? UP SMA3E/N 165-IV ( DAMP 1NC VALUES ARE 2 PERCENT OF CRITICAL FRED'ENCY - HZ J ( 10 1 10 ,s s.... s.... g... .0 cf .PsA - G so - IN ,e .0 1 s . ',1.,2 10' ESlGM so - CM n.e.yar 5.. m.s, s.s4.

  • m es,a. C i y 1

s -( sl o .,T D ('*.*. I.

  • 0 i

s E 10 N Q1 s1 = m ~ C3 -1 -2 1 .0

  • REC.OR b

I -1 ,,9 I 1 f f -2 -3 i 0 10 T 1 p

  • )

.]' = 10 -i 10 1 10 PERIOD - SEC l' / .s s d \\ i

Mu 5.0 EARTH 0 JAKE JANUARY 31. 1956 11AE001 PERRY NUCLEAR POWER PLANT COM? WEST SMA35/N 165-1T k( DAMPlNG VALUES ARE 2 PERCENT OF CRITICAL FREQUENCY - HZ 10 1 10 s i....-10 ii..... i......, r-1 j .d

f..

I PSA - G SD - IN I ID l 0 1 g st sif 9 0 ...e8th.r so _ cn SJ.E. N*All p %'1% 1 l- '10 C.'.2 vb -t 1 .0 .g t 10 h3 'I .-g. -z ,o TcCORDE .i ) '10 1 i O j m t -3 3 ' ( ( l ~ ~ 10 i 10 1 10 -n ~ \\ l

s. U E. A Rl H 0 d A.K t.

JAhuhhY Oi, 1966 IIA 8001 PERRY NUCLEAR POWER PLANT COM? SOUTH SNA35/N 165-1L ( DAM.* LNG VALUES ARE 2 PERCENT OF CRiflCAL ( FREQUENCY - HZ 10 1 10 3 .....;10 i.... :-.. s..... 1 PSA - C ED - I N ' ,0= ~ .0 18 2 ESIG sig 7 10 T.B. Mar ft.M4 ~ SD - CM A ;l l'$.$.f.M848M he* L f, p ~ 1 10 0 9 1 . 0' ' 1: s, 10 1 v m es 1 -2 O , -f?EC6RDE 3 l '10 -2 s l. f 1 0'

  • I

-3 -) 1

  • (

~1 ' 0 -1 10 1 10 PERIOD - SEC l/ Y jN, .\\.

l VERIFICATION OF THE LACK OF ENGINEERING SIGNIFICANCE OF THE 1986 OHIO EARTHQUAKE e PROOF TEST-PLANT STRUCTURES UNAFFECTED 1 - PLANT EQUIPMENT UNAFFECTED i e OTHER INDUSTRIAL CRITERIA CONFIRM THE CONCLUSIONS PILE DRIVING OR BLASTING OPERATIONS - USE 1 INCH /SEC. PARTICLE VELOCITY AS THE NON DAMAGE THRESHOLD FOR NON-ENGINEERED STRUCTURES THE RECORDED MAXIMUM ACCELERATION ATTHE PERRY FOUNDATION M AT IS ONLY 0.87 INCH /SEC. e IEEE 344 PROHIBITS QUALIFICATION SY SHOCK-TYPE TESTING (LOW ENERGY, HIGH I FREQUENCY, SHORT DURATION) f

BUILT IN CONSERVATISMS OF PLANT DESIGN l e BROADENING AND ENVELOPING PROCESS OF FLOOR RESPONSE SPECTRA. 1 e EQUIPMENT QUALIFICATION BY GENERIC TESTS. j I e STRAIN HARDENING NOT ACCOUNTED FOR AND STATIC ALLOWABLES USED FOR DYNAMIC LOADS. e LOADING COMBINATIONS. i e PRIMARY STRESSES VS. SECONDARY STRESSES. DAMPING VALUES. f I e RESPONSES OF EL CENTRO STEAM PLANT. l r

CONCLUSION THE 1986 OHIO EARTHQUAKE: e HIGH FREQUENCIES e SHORT DURATION e LOW ENERGY e LOW VLOCITY e SMALL DISPLACEMENT n-,

.,.e,,.,,,-.,,,

me,- n-, -w n-.---,m,,. , - --awn,,v ,w..,

,,n---,

w,-

SUTARY ANLCONCLUSIGNS ^ o PROOF TEST OF SEISMIC DESIGN JANUARY 31,.1986 EARTHQUAl(E - INTENSITY VI, 4.% RICHTER PLANT STRUCTURES AND SYSTEMS UNAFFECTEDBYEARTHQUAKE NO CHANGE TO CONCLUSIONS ON GEOLOGY AND SEISMOL%Y o DESIGN EARTHQUAKE BOUNDS JANUARY 1986 EVENT (MAGNITUDE, ENERGY ETC.) INCLUSION OF RECENT EVENT WOULD NOT CHANGE DESIGNSPECTRUM o PLANT SEISMIC Ct? ABILITY ABLE TO.ACCOMODATE JANUARY EARTHQUAKE i SHORT DURATION, HIGH FREQUENCY, LOW ENERGY l LOW VELOCITY, SMLL DISPLACEMENT MEASURED RESPONSE EXCEEDANCES OF NO ENGINEERING SIGNIFICANCE ? o FOLLOW ON ACTIVITIES CONFIRMTORY PROGRAMS SUPPORT OF GENERIC, INDUSTRY STUDIES -SOG,SQUG,EPRI .}}

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