ML20141N309

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Notification of Significant Licensee Meeting on 860211 W/Util in Perry,Oh to Discuss Licensee Review of 860131 Earthquake & Operational Readiness to Load Fuel at Unit 1. Agenda & Viewgraphs Encl
ML20141N309
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 02/25/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20141N307 List:
References
NUDOCS 8603060125
Download: ML20141N309 (44)
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{{#Wiki_filter:. _ _ UBIITE) STATES NUCLEAR REIULATURY COMMiss10N [ nEason m 5 m noosevett nono stem sLLvn. ILunois eesar NOTICE OF SIGNIFICANT LICENSEE MEETING Name of Licensee: The Cleveland Electric Illuminating Company (CEI) Name of Facility: Perry Unit 1 r Docket No.: 50-440 Date and Time of Meeting: I2bruary 11, 1986, at 10:00 a.m. and 1:00 p.m. i Location of Meeting: TrLining Center Building Perry Site Perry, Ohio Purpose of first meeting: Meet with CEI management to discuss the licensee's review of the January 31, 1986 earthquake. Purpose of second meeting: Meet with licensee's management to discuss the operational readiness to load fuel at j the Perry Unit 1 plant. Region III Attendees: J. G. Keppler, Regional Administrator i C. J. Paperiello, Director, Division of Reactor Safety R. C. Knop, Chief, Projects Section 1 C, Division of Reactor Projects J. A. Grobe, Senior Resident Inspector, Perry l, Others as assigned NRR Attendees: l J.M.Bernero, Director,DivisionofBWRLicensing,NRR vJ. Stefanoi 1.icensing Project Manager, NRR Others as assighed Licensee Attendeeh:' M. R. Edelman, Vice President, Nuclear Group Others as assigned NOTE: Attendance at this meeting by NRC personnel should be made known i by COB February 7, 1986, by telephone call to R. C. Knop L l ., Region III (FTS 388-5547) 1 i Distribution: J. M. Taylor, Diector Office of Inspection and Enforcement E. L. Jordan, Director, Division of Emergency Preparedness and Engineering 1 Response, IE J. G. Partlow, Director Division of Inspection Programs B. Kr Grimes Director Division of Quality Assurance, Vendor and Technical Training Center Programs R. Bernero, Director, Division of Boiling Water Reactor Licensing W. Brach, Executive Coordinator for Regional Operations, DEDROGR l J. Stefano, Licensing Project Manager, NRR B603060125 840225 PDR ADOCK 05000440 A PDR

9 - 3 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY SEISMIC EVENT EVALUATION TECHNICAL PRESENTATION AGENDA FEBRUARY 11,1986 INTRODUCTION & OVERVI W M. R. EDELMAN PLANT STATUS AND RESPONSE R. A STRATMAN EARTHQUAKE ANALYSIS R. HOLT AND SEISMICITY WESTON GEOPHYSICAL PLANT SEISMIC DESIGN EVALUATION DR. C. CHEN GILBERT C0rtiONWEALTH SUttiARY AND CONCLUS10llS M. R. EDELMAN i b y l / J

e PLANT STATUS PRIOR To SEISMIC Evggt DNGDING IESTING, CALIBRATION, WORK ACTIVITIES 0 PREPARATION FOR DIVISION 11 DIESEL 6ENERATOR IESTING O O STARTUP SOURCES NOT YET MovEn SYSTEMS ENERGlZED (IN OPERATION AND STANDBY MODE) 0 9 SAFETY SYSTEMS ^ -

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4 SYSTEM PLANT STATUS G33 REACTOR WATER CLEANUP A & B PUMPS WITH FLOW TO THE MAIN COND. ~ AI 55 GPM NO PILTER/DEMINERALIZERS IN SERVICE G41 FUEL POOL COOLING AND CLEANUP A PUMP RUNNING B FILTER /DEMINERALIZER TRAIN IN SERVICE l M35 TURBINE BUILDING COOLING B FAN RUNNING AND VENTILATION M41 HEATER BAY VENTILATION B FAN RUNNING M45 CIRCWATER PUMP HOUSE A AND B FANS RUNNING t VENTILATION N21 CONDENSATE A HOTwELL PUMP IN SHORTCYCUE CLEANUP B C CONDENSATE BOOSTER MP LUBE OIL A n,S PUMP ] I N23 CONDENSATE FILTRATION FILTERS B, C, E DEMINERALIZERS A, B. N24 CONDENSATE DEMINERALIZERS 1 . N32 TURBINE CONTROL (EHC) RECIRCULATION PUMP RUNNING N71 CIRCULATING WATER A & B PUMPS RUNNING l-B,C,D(OOPSINOPERATION COOLING 10WER IN BYPASS 1 PilCONDENSATEIRANSFER NORMAL PUMP RUNNING B PUMP IN STANDBY ,Y i P20 WATER IREATMENT A AND B COAGULATORS IN SERVICE P21/22 TWO SED / mixed-BED B STREAM IN SERVICE .DEMINERALIZERS B SULFITE PUMP RUNNING B AND C CLEARWELL PUMPS RUNNING h l P41 SERVICE WATER B AND C PUMPS RUNNING r i P43 NUCLEAR CLOSED COOLING B AND C PUMPS RUNNING j A HEAT EXCHANGER IN SERVICE P44 TURBINE BUILDING CLOSED B AND C PUMPS RUNNING COOLING A HEAT EXCHANGER IN SERVICE l l 4 i l

5 SYSTEM PLANT STATUS PS2 INSTRUMENT AIR-UNIT 1 COMPRESSOR RUNNING P55 BUILDING HEATING A PUMP RUNNING P61 AUXILIARY STEAM B BOILER C BOILER FEED PUMP P62 AUXILIARY BOILER FUEL OIL, 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 i C71 REACTOR PROTECTION SYSTEM ENERGIZED I D17 PLANT RADIATION MONITORS ENERGIZED f E12 RESIDUAL HEAT REMOVAL KEEP FILL PUMP FOR LOOPS B $ C i E21 LOW PRES 0CRE CORE SPRAY KEEP FILL PUMP FOR LPCS AND RHR LOOP A E22 HIGN PRESSURE CORE SPRAY KEEP FILL PUMP FOR HPCS F42 FUEL TRANSFER EQUIPMENT ENERGIZED Mll CONTAINMENT VESSEL COOLING B, C, E, F FANS RUNNING f M13 DRYWELL COOLING 1A 2A, 3B FANS RUNNING BdOOLINGC0ll i M15 ANNULUS EXHAUST GAS IREATMENT A TRAIN RUNNING B IRAIN IN STANDBY M21 CONTROLLED ACCESS VENTILATION A TRAIN RUNNING B TRAIN STANDBY .es M23/24 MCC SwlTcHGEAR & MISC.. A TRAIN RUNNING 4

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SYSTEM PLANT SYSTEM M32 ESW PUMPHOUSE VENTILATION A AND B FANS RUNNING' M40 FUEL HANDLING BUILDING B AND C EXHAUST FANS VENTILATION 2B FAN RUNNING M43~ DIESEL GENERATOR BUILDING VENTILATION A AND B PUMPS RUNNING WITH ALL P45 EMERGENCY SERVICE WATER LOADS VALVED IN IH7 CONTROL COMPLEX CHILLED A CHILLER RUNNING WITH NORMAL LOADS A CIRCWATER PUMP RUNNING WATER P49 EMERGENCY SERVICE WATER BOTH SCREENS OPERATING SCREEN WASH P54 FIRE PROTECTION RECIRC PUMP (CONSTRUCTION) RUNNING NO INTITIATION OF C0, HALON, OR 7 SPRINKLER SUPPRESS 10R SYSTEMS a l D i

l INSPECTIONS AND FINDINGS FOLLOWING SEISMIC EVENT l i 0 OPERATOR SURVEY (NO STRUCTURAL DAMAGE) I O WALKDOWNS BY PLANT MAINTENANCE PERSONNEL (NO STRUCTURAL DAMAGE) l O SYSTEMATIC PLANT WALKDOWNS BY 65 ENGINEERS AND IECHNICIANS (NO STRUCTURAL /EOUIPMENT DAMAGE) IDENTIFY AND DOCUMENT ALL DISCREPAN.T_ CONDITIONS 480 OBSERVATIONS DOCUMENTED (MINOR ITEMS) REvrEW FOR RELATIONSHIP TO EARTHQUdKE REVIEW OF OBSERVATIONS BY CEI AND NRC - 0 ADDITIONAL INSPECTIONS / SURVEYS SITE SURVEY ~ PLANT SETTLEMENT SURVEY COOLING IOWER WALKDOWN 0 SE!SMIC CLEARANCE INSPECTION 0 ENERGrzED ELECT!RCAL EQU!PMENT STUDY 0 ONGOING SURVE!LLANCE (SVI'S) 0 NEW PROCEDURE ASSURES CE!/NRC REVIEW OF ALL POTENTIAL EARTHQUAKE-RELATED ITEMS REVIEW ALL WORK REQUESTS FOR RELATIONSHIP TO EARTHQUAKE NO WORK ON EARTHQUAKE-RELATED OR INDETERMINATE CONDITIONS WITHOUT CE!/NRC REVIEW 1

t MAIN SHOCK January 31,1986 ll l 47 n origin time : 16 hr 46m 42.3 8 U.T. i latitude : 41.649* N longitude : 81.105* W . focal depth : 10 Km based on : 64 stations (worldwide) M=49 b Mbig = 4.96 e j location : Geauga County Near intersection of l Highway 86 and 166 est. distance I to plant : 11 miles 17.7 km j based on : NElS solution l

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a h h ,/ - ( 1 d r. n-t t KEY: 6 Inst.rument #D51-N101 k 7 3 @ 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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g.,.

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7 1 ,,u. g . s.: ~.. r '.w.M-r.i.u;j.1 !(..5l ----@, 3_. T .L idl '. 'l " E? ,kS-N, _ _ G.5 Ill1 ll . Id lu!3 lh E..h. -:

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  • -w w

s+ 1.

  1. D51-N101 R/B Foundation Mat, El. 575', Az.175*

2.

  1. D51-N111 R/B Containment Vessel, El. 686', Az.174*

3.

  1. D51-R120 Reactor Recirc Purnp, El. 605', Az.145*

4.

  1. D51-R140 A/B Foundation Mat, El. 568' 5.
  2. D51-R160 R/B Foundation Mat, El. 574' Az. 225*

6.

  1. D51-R170 R/B Platform, El. 630' Az. 238*

7.

  1. D51-R180 A/B Foundation Mat, El. 568' 8.
  2. D51-R190 A/B Foundation Mat, El. 568'

Page 1 cf 2 . PERRY NUCLEAR P3WER PLANT UNIT ND.1 ~ SEISMIC MONITORING INSTRUMENTATION TABLE IV l ~ Type Manufacturer / Model Number Location References I"' '" Reactor Building I u at on D51-N101 (1) Kinemetrics/SMA-3 Figures A and B g 7 10 j Azimuth 175* l j Reactor BuildirW f,ontainme 1 V'5I Figures A and C l D51-N111 (1) Kinemetrics/SMA 3 ,,, 9 6' 0 1 Azimuth 174* Reactor RecircutationPump I '" d d } D51-R120 (2) Engdahl/ PAR-400 Figures A and D Ele a on 5 ou at ) Azimuth 145' l i D51-R130 (2) Engdahl / PAR-400 OUT O F S E R VIC E l Auxiliary Building Fo Engdahl/ PAR-400 Figures A snd E D51-R140 (2) i gH 5 pR i Elevation 568'-4" i 1. Trianial Time-History Accelerograph j

2. Triaxial Peak Accelerograph.
3. Triarial Response Spectrum Recorder.

1 i I

l Page 2 cf 2 l PERRY NUCLEAR PO'WER PLANT UNIT NO.1 SEISMIC MONITORING INSTRUMENTATION l TABLE IV ~ Type Manufacturer /Model Number Location References Nu r i Reactor Building D51-R160 (3) Engdahl/ PSR-1200-H / V-12A Figures A and F ya i 7 10 j Azimuth 225* i Reactor Building 630' Platform D51-R170 (3) Engdahl/PSR 1200-H/V I E at on O' 1 Figures A and G Azimuth 238' 3 Auxiliary Building D51-R180 (3) Engdahl / PSR-1200-H / V Funda e mp R ) Figures A and H Elevation 568'-4" 4 l Auxiliary Building at Mat D51-R190 (3) Engdahl/PSR-1200-H/V { p pp ) Figures A and j Elevation 568*-4" l i 4 4 I l { 1. Triaxial Time-History Accelerograph j

2. Trianial Peak Accelerograph j
3. Trianial Response Spectrum Recorder l

d

ZPA COMPARISON t ~ e ZERO PERIOD ACCELERATION e RECORDED ZPA'S VARY FROM BELOW OBE VALUES TO 74% OF SSE VALUES e EXCEPT AT CONTAINMENTVESSEL ELEVATION 686' e BUT RELATIVE DISPLACEMENTS g ggy AND STRESSES HERE (AS WELL AS 0%L A'#* ALL OTHER LOCATIONS) ARE LOW UM' i REASON: e HIGH FREQUENCY AND LOW ENERGY OF THE 1986 EARTHQUAKE 4

l TABLE II Comparison of Design ZPh's V5 Recorded ZPA's ] (Expressed in'g values) i Auxiliary Building Reactor Building Reactor Building Reactor Building Reactor Building Foundation Mat Foundation Mat Recirculation Pump Platform Containment Vessel 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.N101 D51.R120 PSR 1200(Engdahl) D51-N111 D51-R170 6 .l i-Recorded .17 .18 .32 .09 .55 l NS SSE .17 .18 1.06 .48 .40 'l OBE .10 .10 .86 .40 .24 i Recorded .06 .10 .11 .16 18 I EW SSE .20 .18 1.06 .48 .40 OBE .10 .10 .86 .40 .24 1 Recorded .03 .11 .05 Note 2 .30 VERT. SSE .20 .18 .47 .28 .24 OBE .10 .10 .38 .16 .15 ) <p ' Note'2 j ~ ".45 e. s s

  • ?.34I 2'

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39,
ogE i 2.

O ^ r ^ . 37

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j 1. Zero period acceleration i 2. 2PA indeterminable from available data 3. Square-root-of-the-sum of the squares ) 4. Licensing basis is SSE i r

TABLE I Comparison of Design Displacements' V5 Recorded Displacements (Expressed in centimeters /one inch = 2.54 cm) i l l COLUMN 1 COLUMN 2 C O L U M N 2 minus C O L U M N 1 Reactor Building Reactor Building Relative Displacements i Foundation Mat Containment Vessel for the { Elevation 574*-10* Elevation 686* Containment Vessel j SMA-3 ( Kinemetrics) SMA-3 ( kinemetrics) ] D51-N101 D51-N111 J l. Recorded 0.09 0.17 0.08 l NS SSE 0.044 0.28 0 24 OBE 0.023 0.17 0.15 i Recorded 0.16 0.21 0.05 1 i EW SSE 0.044 0.28 0.24 i OBE 0.023 0.17 0.15 l Recorded 0.05 0.07 0.02 i VERT. SSE 0.02 0.37 0.017 i j OBE 0.013 0.022 0.009 1 i f.t j. s -n l m. ^ - w.g.q s 3. =_ s + s 0.1 s . ~.., w-u.e, ;c.3 -w i SR$5 t.. 155El ^' ' " " l -? " i. /0.34 a.c ~ \\ ' y,< ~ . j 'y x > \\ i JOSE; <J W 5~ ;- 0.21' i + L; c., ,u 3 i 1. Displacements based on same time-step to determine relative displacements l 2. Square-root-of-the-sum of the squares l l v l

M RESPONSE SPECTRA COMPARISON j ~ e e PERRY DESIGN RESPONSE SPECTRA ARE FAR ABOVE THE RECORDED SPECTRA IN THE FREQUENCY REGION BELOW 14 Hz. 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 1 i e RECORDED VELOCITY SPECTRA SHOW ~ MUCH LESS ENERGY THAN THE DESIGN ~ RESPONSE SPECTRA e f -n. .--.m---- ---mgan--- ,-,..--.,,._.n.. ,--_,-w.,..n,, m,,._,,,__, .e-,,_,_-....,,,, ,,.mwmowmasw--w...e,

-~ -m u o v o.me rne e a. 6M 11A8002 PERRY NUCLEAR POL'ER PL ANI COM? UP SMA35/N 165-8 L(( DAMPING VALUES ARE 2 PERCENT OF CRITICAL FREoVENCY - HZ -1 10 1 to i..... g... g....-11 f i 6 r-i PsA - c SD - IN 10, 8 L,.,! g ig g y $\\ }g [ p g ,s - ces .a ' . st o C.* 3 o: _.z \\s,, ig s1 n a 2 1 .o. 2 Recont> b I 'i o > -2. -3 o -2 s; o i . -s

(

-1' 10 g 10' ~ i to PERIOD - SEC

" 11AE302 PERRY NUCLEAR POWER PLANT COM? WEST EMA35/N 165-2' ( DAMP 1NG VALUES ARE 2 PERCENT OF CRITICAL 4 ~REDUENCY - HZ 10 1 10 ) -1 g... .s s....s s... - 1 Lo g. t i . PSA - G SD - IN ' 'g DES N 4 cK rt, s' 0 f* 1 j ~ i s3[ lU i S D - C F. ~ 1 i '10 p (r. 1 6 v' a: s

  • a 10 s1 m

en l~ ' -1 't -t o. t ^ REcoRb s10' 1 ~ . -2 s -s 0 i I ~ $16* T I 3 i i. ~' 10 l l 'l' -n j 10 1 10 L .M.0 00 -

an -c enouvnn u @) : 11A8002 PERRY NUCLEAR F0WER PL ANT COMP 500TH EMA3S/N.65-8 ' ( DAMPING VALUES ARE 2 PERCENT OF CRITICAL TREQUENCY - HZ 10 t 1 ~ 3_._ _ g... 10 i g... .s g... . - i (4 6 .d i t PSA - G .l 'g DES N ED - IN Cif r4 .8' ,o .SSE#o , ge-2)E ! ;l h<, ~ 3, 1 ,sd so - en <t 1 r 1 (N N e, io e 1 i r, 1 ,D, . =s , se 1 -i o e . [ _i

i..

1 RECORDEb .o_,. l -i 10 1 s -a t 1 s -3 'O 2 sid 1 -s 1 ) 4 -1 ,,....i 10 1 10 .r ? ____,__p..y owr"=W-

IIA 8001 PERRY NUCLEAR POWER PLANT COM? UP SMA3E/N 165-tv (. DA!1 PING VALUES ARE 2 PERCENT OF CRITICAL FREQUENCY - NZ 3 ( 10 1 10 3' i ...-10 s..... i..... ~ e I 3 g l ~ a PSA - G SD - IN i if ~ s 0 1 4 1. j 10 !

s. g.

1 ESIGM SD - CM , y K 0. Math. 9N S, l s.5 4.tfr m c4&,f4= 2 % 1 t s 2 ~ l i ..[ r10 ~ M. ~ eo r *a, f*: ,0; 8 at 10 N c: g1 m l o .i -2 1 0-lt' ,; o ' ' RECOR b 1 1 4 r -2 -3 ~ .0 i i l! si O =

i p

3 i 1 L ~1' ' 'i 10 -1 10 1 10 PERIOD - SEC / ~

l'i t. O.U

t. A r\\ ! t.J V A rs t JhNdhkY 3),

)966 l 11'A805i PERRY NUCLEAR POWER PLANT COMP WEST SMA35/N 165-1T i ( DAMPING OALUES ARE 2 PERCENT OF CRITICAL FREDUENCY - HZ 10 1 10 ~ s i...... s.... i....;iD s~ \\ j .d .r- \\. PSA - G SD - IN i io" } 0 1 g 2 0 .$ A EY.574 t' '~ S - cn 5.t.E. M* rih pf,' A 2 1 i. 'l 0 (W U T -t t. 1

D g

L_ = "N 10 Qg g. a .._g. ,o-a 3 ecoRDE st D ' 1 ~* 1 ~3 .t. ,0 9 2 '1D I I i. -3 = ( i 10 ' t 10 i 10 I PERIOD - SEC /

v.& swrnrnemrnm ts, e n h u n n T V i~.~ ~ 1 b b F ~~~ ~ ~ ~ 11'A8001 PERRY NUCLEAR F0WER PLANT COM? SOUTH SNA3s/N 165-1L .( DAM.'ING VALUES ARE 2 PERCENT OF CRITICAL - ( FREQUENCY - HZ 10 1 10 3 s.... s..... .....;10 -l s 1 i g i ~ PSA - G ED - IN " i 1d j .0 18 ~ i ESI sig 10 W.S. Mar L.H4 ,s.s.t.Metsu heL gn _ gn s 1 y 10 ,0 o l l 0: 1, z s, 10 : 1 u JTl c3 -t -a ,0 AECORDE 3 '10 Y l, 3 I 1 s10'* I 3 -3 1 { T I ~8 10 '- ~ 10 1 10 ///[#/ PERIOD - SEC . /g .N.d...\\. \\NN

VERIFICATION OF THE LACK OF ENGINEERING SIGNIFICANCE OF THE 1986 OHIO EARTHQUAKE ~ ~ ~ ~ ~ ~ ' ~ ' ~ ' ~ e PROOF TEST-PLANT STRUCTURES UNAFFECTED -PLANT EQUIPMENT UNAFFECTED 4 e OTHER INDUSTRIAL CRITERIA CONFIRM THE CONCLUSIONS j e PILE DRIVING OR BLASTING OPERATIONS - USE 1 INCH /SEC. PARTICLE VELOCITY AS THE ) NON-DAMAGE THRESHOLD FOR NON-l ENGINEERED STRUCTURES 1 e THE RECORDED MAXIMUM ACCELERATION ATTHE PERRY FOUNDATION MATIS ONLY i 0.87 INCH /SEC. i e IEEE 344 PROHIBITS QUALIFICATION BY SHOCK-TYPE TESTING (LOW ENERGY, HIGH [ g. FREQUENCY,SHORTDURATION) 1 ,g s- [

4 BUILT IN CONSERVATISMS OF PLANT DESIGN l e BROADENING AND ENVELOPING PROCESS OF FLOOR RESPONSE SPECTRA. I e EQUIPMENT QUAllFICATION BY GENERIC TESTS. i e STRAIN HARDENING NOT ACCOUNTED FOR AND. STATIC ALLOWABLES USED FOR DYNAMIC LOADS. 't e LOADING COMBINATIONS. e PRIMARY STRESSES VS. SECONDARY STRESSES. I e DAMPING VALUES. e RESPONSES OF EL CENTRO STEAM PLANT. l ,.e-, e.+---,,------------m~wm~--rr-w-, ne---w- ,,w w-~-www--o-r -w ~ m mw w w-w'*'M'*

-.on_ CONCLUSION THE 1986 OHIO EARTHQUAKE: e HIGH FREQUENCIES e SHORT DURATION e LOW ENERGY e LOW VELOCITY e SMALL DISPLACEMENT I . Q/ > */ / Wf f h$ gspng/a,a y pk 6.g,. @y

Su m ARY AND CONCLUSIONS PROOFTESTOFSEISMidDESIGN o JANUARY 31; 1986 EARTHQUAKE - INTENSITY VI,14.% RICHTER PLANT STRUCTURES AND SYSTEMS UNAFFECTED BY EARTHQUAKE 1 NO CHANGE TO CONCLUSIONS ON GE0 LOGY AND SEISM 0 LOGY o DESIGN EARTHQUAKE BOUNDS JANUARY 1986 EVENT (MAGNITUDE, ENERGY ETC.) INCLUSION OF RECENT EVENT WOULD NOT CHANGE DESIGN SPECTRUM PLANT SEISMIC CAPABILITY ABLE TO ACCOMODATE JANUARY o EARTHQUAKE SHORT DURATION, HIGH FREQUENCY, LOW ENERGY LOW VELOCITY, SMALL DISPLACEMENT l MEASURED RESPONSE EXCEEDANCES OF NO ENGINEERING SIGNIFICANCE o FOLLOW ON ACTIVITIES CONFIRMATORY PROGRAMS SUPPORT OF GENERIC, INDUSTRY STUDIES -S0G,SQUG,EPRI O}}

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