Text

Discusses 860131 Earthquake Near Plant.Facility Will Be Inspected for Structural Damage & Equipment Failure or Malfunction & Seismic Instrumentation Recordings & Util Findings Evaluated
	ML20210C096
Person / Time
Site:	Perry, 05000000
Issue date:	02/19/1986
From:	Sobel P; Office of Nuclear Reactor Regulation
To:	Liaw B; Office of Nuclear Reactor Regulation
Shared Package
ML20195C722	List: ML20195C718; ML20195C739; ML20195C752; ML20195C756; ML20195C760; ML20195C768; ML20195C779; ML20195C852; ML20195C860; ML20195C867; ML20195C873; ML20195C894; ML20210C096; ML20210C105; ML20210T527; ML20210T540; ML20210T548; ML20210T556; ML20210T561; ML20210T567; ML20210T572; ML20210T580; ML20210T587; ML20210T593; ML20210T601; ML20210T607; ML20210T614; ML20210T621; PNO-III-86-009, on 860131,earthquake Felt at Plant.No Significant Damage Reported.Some Site Personnel Evacuated. Site Area Emergency Declared.Supporting Documentation Encl; PNO-III-86-009A, on 860131,earthquake Experienced at Plant. Site Response Activities Accomplished by Implementing Emergency Plan,Although Action Not Required Prior to Licensing.No Significant Damage Noted;
References
	FOIA-86-91 NUDOCS 8602280464
	Download: ML20210C096 (3)
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UNITED STATES e

NUCLEAR REGULATORY COMMISSION a

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WASHINGTON, D. C. 20555

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50-440/441 MEMORANDUM FOR:

B. D. Liaw, Chief Engineering Branch Division of BWR Licensing bobert LaGrange, Section Leader THROUGH:

Engineering Branch Division of BWR Licensing FROM:

Phyllis Sobel, Geophysicist Engineering Branch t,

Division of BWR Licensing

SUBJECT:

JANUARY 31, 1986 EARTHQUAKE NEAR PERRY NUCLEAR POWER PLANT At 16:46:41.7 GMT (11:46 EDT) on January 31, 1986 a magnitude 4.9 to 5.0 (m )

earthquake occurred about 10 miles south of the Perry plant in northeasternb Ohio.

The USGS-NEIS report the epicenter was at 41.65'N and 81.10*W.

The earthquake was felt as far away as Washington, D.C., about 300 miles from the epicenter and there were reports of damage such as cracked walls, falling roof tiles and shattered windows near the epicenter.

There have been five small aftershocks; the largest was about a magnitude 2 to 2.3 on February 7.

The aftershocks were 2 to 9 km deep and some were felt, although not at the Perry site.

A site area emergency was declared at the Perry site and plant personnel surveyed for any damage. The NRC project manager, John Stefano, a DSRO seismologist, Leon Reiter and a DSR0 mechanical engineer, Tsung-Yung Chang inspected the plant on February 1, 1986. The initial reports indicated no significant damage. Another NRC team (including Arnold Lee of NRR and Jag Singh from EG&G) inspected the plant on February 6 and 7 and found no damage. The utility is continuing the survey for damage.

The January 31 earthquake triggered the in-plant seismic monitoring instru-Preliminary acceleration data indicate that some of the recorded ground ments.

motions exceeded the Operating Basis and Safe Shutdown Earthquake design spectra at high frequencies (above 15 hertz).

The earthquake motion recorded at the reactor building foundation was of short duration (about one second) and pre-dominantly high frequencies.

submitted their report on the earthquake data on February 12.The utility m

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l The size and proximity of the January 31 earthouake are consistent with l

observations of historical seismicity in the Central Stable Region.

In the i

SER the staff compared the Perry SSE design spectrum to a larger event (magnitude 5.3) at this distance. The location of the earthquake, its after-shocks and focal mechanisms.will have to be examined with respect to known geological features and statements in the SER to determine if significant j

new findings can be made. The significance of the high frequency peak j

accelerations observed in the plant is being assessed by the utility and the staff with respect to plant structures and co.1ponents. The staff has contracted with Jim Johnson of NTS/ Structural Mechanics Associates to inspect the Perry facility for structural damage and equipment failure or malfunction and to evaluate the seismic instrumentation recordings and the utility's findings.

I will notify you of any additional information we receive.

i I

lM Phyllis Sobel, Geophysicist Engineering Branch Division of BWR Licensing cc:

R. Bernero i

G. Lainas W. Butler F. Congel L. Beratan l

A. Murphy R. LaGrange R. Hermann N. Anderson J. Stefano S. Stern L. Reiter S. Brocoum A. Lee P. Sobel DISTRIBUTION:

DMB. Docket Files BWR. Reading Files BWR. Perry Unit Files i

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UNITED STATES g

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8 wAsmNGTON, D. C. 20666 FEB 2 51986 1

Docket No.: 50-440 50-441 i

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MEMORANDUM FOR: Walter R. Butler, Director Project Directorate No. 4 i

Division of BWR Licensing i

FROM:

John J. Stefano, Project Manager i

Project Directorate No. 4 Division of BWR Licensing

SUBJECT:

SUMARY REPORT OF THE EARTHQUAKE MEETING AT THE PERRY PLANT SITE ON FEBRUARY 11, 1986 The meeting was held to discuss CEI's preliminary findings from its i

assessment of the impact of the January 31, 1986 earthquake on the as-built Perry plant design, and to discuss the operational readiness of Perry Uni,t 1 for licensing. This report briefly summarizes discussions held in the morning of February 11, 1986, which were limited solely to the earthquake event and its aftermath. The NRC regional staff will report separately on discussions held in the afternoon of Februarj

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Unit I readiness for licensing.

' 11, 1986, relative to the Perry Enclosure (1) lists the NRC, USGS and principal CEI rep'resentatives who par-g ticipated in the meeting. Other CEI personnel and members from the press U.S.

Congressional staff, the intervenors and other interested parties were also in attendance, but are not listed in Enclosure (1). Enclosure (2)contains i

the meeting notice (issued by the NRC Region III Office) and the slide presentation handout prepared by CEI and distributed to the meeting attendees.

i In sunnary, CEI presented its independent investigative findings of plant i

status prior to, during, and after the earthquake event, including a listing l

of the safety and non-safety systems that were undergoing operational readiness tests when the event occurred; characterized the earthquake event and its geographical location relative to the plant site; described the geologic 4

i structure upon which the plant was built; and discussed the analytical results i

obtained from the seismic data recorded by instruments positioned at various i

locations within the Perry plant buildings. On the basis of CEI's analysis j

of the data recorded, CEI and its consultants have concluded that:

(1) the tectonic province considered in defining soil-structure interactions for the I

Perry site.-specific safe shutdown earthquake (SSE) intensity remains valid

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as described in the FSAR and as evaluated by the NRC staff in the Perry SER; and (2) that the exceedance of SSE limits recorded at the higher frequencies (greater than 16 Hz) was of such a short duration (less than 1 second), low velocity and small displacement as to not have imparted any significant energy j

to the plant structure and the components, systems, and equipment installed j

therein; although a more detailed assessment of the impact, if any, on the qualification of safety-related equipment in the plant has not yet been fully i

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. completed.

In view of these conclusions, CEI maintained that the SSE design basis for the Perry plant remains valid. These conclusions appear to be borne I

out by the fact that little or no damage had been observed during an intense walkdown of the plant' conducted by the CEI staff.

The NRC staff advised CEI that it still needed to conduct its own independent evaluation of the earthquake and that this effort would consider CEI's findings (a detailed report was filed by CEI with the Comission on February 12,1986).

i The NRC staff also informed CEI that the issue would be discussed with the i

ACRS, and that meetings with the ACRS Subcomittee and the ACRS Full Committee were scheduled for February 12 and 13,1986, respectively.

(NRC and CEI briefed the ACRS on those dates). Lastly, the NRC staff advised CEI that its independent evaluation would not be completed before March 1,1986, and that conpletion of its evaluation by that date assumed receipt of all outstanding data promised by CEI before February 17, 1986.

The morning session of the February 11, 1986 meeting was completed at 11:30 am after which time the NRC staff answered questions posed by the press and public representatives in attendance. The NRC staff also met with its respective CEI technical counterparts to go over in more detail the information presented by CEI during the formal meeting.

O r.

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u n J.$ ano, S r

ect Manager

.WR ProJtc1 Director ate N.

4 Division 'o' nsing

Enclosure:

As stated cc w/ enclosure: See next page l

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Mr. Murray R. Edelman Perry Nuclear Power Plant 2

The Cleveland Electric Units 1 and 2 Illuminating Company cc:

Jay Silberg, Esq.

Mr. Larry 0. Beck Shaw, Pittman, & Trowbridge The Cleveland Electric 1800 M Street, N. W.

Illuminating Company Washington, D..C.

20006 P. O. Box 97 E-210 Perry, Ohio 44081 Donald H. Hauser, Esq.

The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 Resident Inspector's Office U. S. Nuclear Regulatory Commission Parmly at Center Road Perry, Ohio 44081 Regional Adh.inistrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois.60137 Donald T. Ezzone, Esq.-

Assistant Prosecuting Attorney 105 Main Street Lake County Administration Center Painesville, Ohio 44077 Ms. Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, Ohio 44060 Terry J. Lodge, Esq.

618 N. Michigan Street Suite 105 Toledo, Ohio 43624 John G. Cardinal, Esq.

Prosecuting Attorney Ashtabula County Courthouse Jefferson, Ohio 44047 I

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I CEI/NRC MEETING AT PERRY SITE FEBRUARY 11, 1986 (MORNING SESSION ONLY)

EARTHQUAKE EVENT CEI NRC M. R. Edelman R. M. Bernero, NRR/ DBL A. Kaplan J. G. Keppler, RIII E. Buzzelli C. J. Paperiello, RIII F. Stead R. C. Knop, RIII M. Lister J. A. Grobe, RIII R. Stratman J. J. Stefano, NRR/ DBL Others W. R. Butler, NRR/ DBL R. Hernon, NRR/ DBL H. Polk, NRR/ DBL J. Johnson,Consulant(SMA)

J. Singh, Consultant (EG&G)

D. Guzy, RES G. Cuming, Consultant Gilbert Associates C. Chen R. Ailey CEI Consultants USGS R. Holt L. Langer F

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UMTED STATES NUCLEAR CEGUI.ATORY COMMisslCN 7

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5 tesno6savskynoap eten su,vn. itumois win 1

90T E OF SIGNIFICANT LICENSEE ftEETING Name of Licensee: The Cleveland Electric Illuminating Company (CEI)

Name of Facility:

Perry Unit 1 Docket No.: 50-440 I

Date and Time of Meeting:

February 11, 1986, at 10:00 a.m. and 1:00 p.m.

Location of Meeting: Training Center Building Perry Site Perry, Chio Purpose of first meeting: Meet with CEI management to discuss the licensee's review of the January 31, I?SC earthquake.

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Purpose of second meeting: Meet with licensee's management to discuss l

the operational readiness to load fuel at the Perry Unit 1 plant.

Region III Attendees:

J G. Keppler, Regional Administrator 4

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 i

Others as assigned NRR Attendees:

J. M. Bernero, Director, Division of BWR Licensing, NRR v"J. Stefano, ticensing Project Manager, NRR Others as assighed Licensee Attendees:

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M. R. Edelman, Vice President, Nuclear Group Others as assigned NOTE: Attendance at this meeting by NRC personnel should be made known by COB February 7, 1986, by telephone call to R. C. Knop

., Region III (FTS 388-5547)

Distribution:

J. M. Taylor Diector, Office of Inspection and Enforcement E. L. Jordan, Director, Division of Emergency Preparedness and Engineering Response. IE J. G. Partlow, Director, Division of Inspectior. Programs B. K 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 J. Stefano, Licensing Project Manager, NRR P

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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY SEISMIC EVENT EVALUATION TECHNICAL PRESENTATION AGENDA FEBRUARY IL 1986 INTRODUCTION & OVERVIEW 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 C0m 0NWEALTH

SUMMARY

AND CONCLUSIONS M. R. EDELMAN 1

l

1.

PLANT STATUS PRIOR To SEISMIC EVENT 0

ONGOING IESTING, CALIBRATION, WORK ACTIVITIES PREPARATION FOR DIVISION II DIESEL 6ENERATOR IESTING O

O STARTUP SOURCES NOT YET MOVED SYSTEMS ENERGIZED (IN OPERATION AND STANDBY MODE) 0 SAFETY SYSTEMS NON-SAFETY SYSTEMS D

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SYSTEM PLANT STATUS 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 IRAIN IN SERVICE 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 VENTILATION N21 CONDENSATE A HOTWELL PUMP IN SHORTCYCLE CLEANUP A B, C CONDENSATE BOOSTER PUMP LUBE OIL t

PUMPS N23 CONDENSATE FILTRATION FILTERS 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 IOWER IN BYPASS P11 CONDENSATE TRANSFER NORMAL PUMP RUNNING B PUMP IN STANDBY A AND B COAGULATORS IN SERVICE P20 WATER IREATMENT P21/22 TWO aED/ 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 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

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

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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 ENERGIZED C71 REACTOR PROTECTION SYSTEM ENERGIZED D17 PLANT RADIATION MONITORS ENERGIZED E12 RESIDUAL HEAT REMOVAL KEEP FILL PUMP FOR LOOPS B & C i

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 ENERGIZED Mll CONTAINMENT VESSEL COOLING B, C, E, F FANS RUNNING l

M13 DRYWELL CCOLING 1A 2A, 3B FANS RUNNING 2

B LOOLING COIL M15 ANNULUS EXHAUST GAS IREATMENT A TRAIN RUNNING B TRAIN IN STANDBY M21 CONTROLLED ACCESS VENTILATION A TRAIN RUNNING B TRAIN STANDBY

_ew M23/24 MCC SwITCHGEAR & MISC.

A TRAIN RUNNING AREA VENTILATION / BATTERY ROOM B TRAIN STANDBY

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EXHAUST i ?

\\M25/26CONTROLROOMVENTILATION/

A TRAIN RUNNING IN NORMAL MODE f

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SYSTEM PLANT SYSTEM M32 ESW PuMPN0uSE VENTILATION A AND B FANS RUNNING' M40 FUEL HANDLING BUILDING B AND C EXHAUST FANS VENTILATION M43 DIESEL GENERATOR BUILDING 2B FAN RUNNING VENTILATION A AND B PUMPS RUNNING WITH ALL P45 EMERGENCY SERVICE WATER 4

LOADS VALVED IN P47 CONTROL COMPLEX CHILLED A CHILLER RUNNING WITH NORMAL LOADS WATER A CIRCWATER PUMP RUNNING P49 EMERGENCY SERVICE WATER BOTH SCREENS OPERATING SCREEN WASH P54 FIRE PROTECTION RECIRC PUMP (CONSTRUCTION) RUNNING NO INTITIATION OF C0, HALON, OR 9

SPRINKLER SUPPRESSIOR SYSTEMS O

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INSPECTIONS AND FINDINGS F0tt0wtNG SerSMIC event 0

OPERATOR SURVEY (NO STRUCTURAL DAMAGE)

O WALKDOWNS BY PLANT MAINTENANCE PERSONNEL (NO STRUCTURAL DAMAGE)

O SYSTEMATIC PLANT WALKDOWNS BY 65 ENGINEERS AND IECHNICIANS (NO STRUCTURAL / EQUIPMENT DAMAGE)

IDENTIFY AND DOCUMENT ALL DISCREPAN.T_ CONDITIONS 1480 OBSERVATIONS DOCUMENTED (MINOR ITEMS)

REVIEW FOR RELATIONSHIP TO EARTHQUAKE REVIEW OF OBSERVATIONS BY CEI AND NRC- -

0 ADDITIONAL INSPECTIONS / SURVEYS SITE SURVEY PLANT SETTLEMENT SURVEY COOLING IOWER WALKDOWN O

SEISMIC CLEARANCE INSPECTION O

ENERGIZED ELECTIRCAL Ecu!PMENT STUDY 0

ONGOING SURVEILLANCE (SVI'S) 0 NEW PROCEDURE ASSURES CEl/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 CEl/NRC REVIEW i

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MAIN SHOCK January 31,1986 II l 4 7 o +

origin time :

16 hr 46m 42.3 8 U.T.

latitude :

41.649 N

longitude :

81.105 W

-focal depth :

10 Km based on :

64 stations (worldwide)

M=49 b

Mbig = 4.96 e location :

Geauga County Near intersection of Highway 86 and 166 est. distance

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11 miles 17.7 km based on :

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EARTHQUAKE MAGNITUDE & INTENSITY 4.96 M sts - 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 -

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Instrument #D51-N101

@ 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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1.

D51-N101 R/B Foundation Mat, El. 575', Az.175' 2.

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

3.

D51-R120 Reactor Recirc Pump, El. 605', Az.145' 4.

D51-R140 A/B Foundation Mat, El. 568' 5.

D51-R160 R/B Foundation Mat, El. 574' Az. 225*

6.

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

7.

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

D51-R190 A/B Foundation Mat, El. 568' i

I i

Page 1 cf 2 PERRY NUCLEAR POWER PLANT UNIT NO.1 SEISMIC MONITORING INSTRUMENTATION T A B 1. E IV a

Instrument Type Manufacturer / Model Number Location References 9

l Reactor Building u a D51-N101 (1)

Kinemetrics/ SMA-3 Figures A and B

,v io 57 10 I

Azimuth 175*

1 I

Reactor BuildingW fg,ntai"' 6*-0.'

Figures A and C o

'5 D51-N111 (1)

Kinemetrics/ SMA-3

,tio Azimuth 174*

Reactor RecirculationPump D51-R120 (2)

Engdahl/ PAR-400 (Inside Drywell, Reactor Building)

Elevation 605 -0, ( Approximately)

Figures A and D j

Azimuth 145' l

i D51-R130 (2)

Engdahl / PAR-400 0UT OF5ERVICE I

i Auxiliary Building f

Founda on D51-R140 (2)

Engdahl/ PAR-400 Figures A and E mp R m)

Elevation 568'-4" i

l 1.

Trianial Time-History Accelerograph 2.

Triaxial Peak Accelerograph j

3.

Triarial Response Spectrum Recorder m

I t

Pag 22 cf 2 J

PERRY NUCLEAR. POWER PLANT UNIT NO.1 i'

I SEISMIC MONITORING INSTRUMENTATION l'

TABLE IV 1

Instr nt Type Manufacturer /Model Number Location References

]

S Reactor Building F

D51-R160 (3)

Engdahl / PSR-1200-H / V-12A Figures A and F E

i 7

10 Azimuth 225' I

l l

Reactor Building 630' Platform j

D51-R170 (3)

Engdahl / PSR-1200-H / V I'

d

}

El 0

Figures A and G l

Azimuth 238*

I i

i Auxiliary Building D51-R180 (3)

Engdahl / PSR-1200-H / V a

Ma g

pp Figures A and H Elevation 568*-4*

1 Auxiliary Building l

D51 R190 (3)

Engdahl/ PSR 1200-H/V at Ma p

p p Figures A and J Elevation 568*-4*

4 l

1 e

t j

1.

Triarial Time-History Accelerograph j

2.

Trianial Peak Accelerograph 3.

Triarial Response Spectrum Recorder l

1

ZPA COMPARISON

.I

~

e ZERO PERIOD ACCELERATION e

RECORDED ZPA'S VARY FROM BELOW OBE VALUES TO 74% OF SSE VALUES

EXCEPT AT CONTAINMENT VESSEL ELEVATION 686' e BUT RELATIVE DISPLACEMENTS g ggy _

AND STRESSES HERE (AS WELL AS A

0%

ALL OTHER LOCATIONS) ARE LOW VM' REASON:

e HIGH FREQUENCY AND LOW ENERGY OF THE 1986 EARTHQUAKE i

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, -,,. - -.., +, - -,.. -,,, - - -,,, _,.,,

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g TABLE II I

i I

Comparison of Design ZPA's' V5 Recorded ZPA's t

(Expressed in g values) t 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 l

l Recorded

.17

.18

.32

.09

.55 NS SSE

.17

.18 1.06

.48

.40 OBE

.10

.86

.40

.24

~

i Recorded

.06

.10

.11

.16 18 EW SSE

.20

.18 1.06

.48

.40 OBE

. 10

.10

.86

.40

.24 h

1 l

Recorded

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.11

.05 Note 2

.30 l

VERT.

SSE

.20

.18

.47

.28

.24 i

OBE

.10

.38

.16

.15 f

I

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l i-

"^ "^ / gecoided; D H.13^,

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T.34 (

u Note 2 >

.65

)

w...

i 52558 J

. [> $33; g

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.62

~ { 55EN,

s i

i-OBE O.17 I,.*. ' s-

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' '.59 1 1

1 i

1.

Zero period acceleration ~

2.

ZPA indeterminable from available data j

3.

Square-root-of-the-sum of the squares i

4.

Licensing basis is SSE i

4 l

/,

i 1

1 l

TABLE I i

~

Comparison of Design Displacements VS Recorded Displacements l,

8 5

(Expressed in centimeters /one inch = 2.54 cm)

{

i I

COLUMN 1 COLUMN 2 CO L U M N 2 minus CO L U M N 1 Reactor Building Reactor Building Relative Displacements Foundation Mat Containment Vessel for the Elevation 574*-10" Elevation 686*

Containment Vessel SMA-3 (Kinemetrics)

SMA-3 (kinemetrics) i D51-N101

- D51 N111 i

Recorded 0.09 0.17 0.08 MS SSE 0.044 0.28 0.24 OBE 0.023 0.17 0:15 f

Recorded 0.16 0.21 0.05 i

j EW SSE 0.044 0.28 0.24 OBE 0.023 0.17 0.15 I

i Recorded

~

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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

-.- ern,

n7. tc'o 11A8002 PERRY NUCLEAR POWER PLANT COM? UP SMA35/N 165!

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VERIFICATION OF THE LACK OF ENGINEERING SIGNIFICANCE OF THE 1986 OHIO EARTHQUAKE o

PROOF TEST-PLANT STRUCTURES UNAFFECTED

-PLANT EQUIPMENT UNAFFECTED l

e OTHER INDUSTRIAL CRITERIA CONFIRM THE CONCLUSIONS 1

e PILE DRIVING OR BLASTING OPERATIONS -

i USE 1 INCH /SEC. PARTICLE VELOCITY AS THE NON-DAMAGE THRESHOLD FOR NON-ENGINEERED STRUCTURES 1

THE RECORDED MAXIMUM ACCELERATION ATTHE PERRY FOUNDATION MATIS ONLY 0.87 INCH /SEC.

.. g, e

IEEE 344 PROHIBITS QUALIFICATION BY SHOCK-TYPE TESTING (LOW ENERGY, HIGH FREQUENCY, SHORT DURATION) l 89 n <f-O (f

~

f l _ __ _

BUILT IN CONSERVATISMS OF PLANT DESIGN i

e BROADENING AND ENVELOPING PROCESS OF i

i FLOOR RESPONSE SPECTRA.

1 i

i e

EQUIPMENT QUALIFICATION BY GENERIC TESTS.

l e

STRAIN HARDENING NOT ACCOUNTED FOR AND STATIC ALLOWABLES USED FOR DYNAMIC i

j LOADS.

e LOADING COMBINATIONS.

e PRIMARY STRESSES VS. SECONDARY STRESSES.

l l

e DAMPING VALUES.

i e

RESPONSES OF EL CENTRO STEAM PLANT.

i I

l.

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-w-w--r-rv.-w,

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e CONCLUSION THE 1986 OHIO EARTHQUAKE:

o HIGH FREQUENCIES e SHORT DURATION e LOW ENERGY e LOW VELOCITY i

e SMALL DISPLACEMENT

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SUMMARY

AND CONCLUSIONS o

PROOF TEST OF SEISMIC DESIGN JANUARY 31; 1986 EARTHQUAKE -

1 INTENSITY VI, 4 % RICHTER PLANT STRUCTURES AND SYSTEMS UNAFFECTED BY EARTHQUAKE NO CHANGE TO CONCLUSIONS ON GEOLOGY AND SEISM 0 LOGY o

l DESIGN EARTHQUAKE BOUNDS JANUARY 1986 EVENT (MAGNITUDE, ENERGY ETC.)

1 i

INCLUSION OF RECENT EVENT WOULD NOT CHANGE DESIGN SPECTRlM l

PLANT SEISMIC CAPABILITY ABLE TO ACCOMODATE JANUARY o

EARTHQUAKE I

SHORT DURATION, HIGH FREQUENCY, LOW ENERGY LOW VELOCITY, SMALL DISPLACEMENT j

b MEASURED RESPONSE EXCEEDANCES OF NO l

ENGINEERING SIGNIFICANCE j

o FOLLOW ON ACTIVITIES CONFIRMATORY PROGRAMS SUPPORT OF GENERIC, INDUSTRY STUDIES

-S0G,SQuG,EPRI i

j

t I I cc:

H. Denton S. Brocoum D. Eisenhut L. Heller l

R. Bernero N. Chokshi i

W. Butler L. Shao, RES i

G G. Bagchi i-I.Lainas Stefano G. Giese Koch j

S. Stern P. T. Kuo T. Speis R. Rothman B. Sheron A. Lee N. Anderson P. Sobel I

Lic. Div. Directors R. Hermann Lic. Div. A/Ds C. P. Tan G. Arlotto, RES J. Richardson, RES C. Paperiello, Reg. III t

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NUCLEAR REGULATORY COMMISSION y

W ASeGTON, D. C, 20$55 O 2 5 MI6 MEMORANDUM FOR:

Robert J. Bosnak, Chief Engineering Issues Branch DSRO, NRR Frank J. Congel, Chief Reliability and Risk Assessment Branch DSR0, NRR FROM:

T. Y. Chang, Task Manager Leon Reiter, Sr. Reliability and Risk Analyst DSRO, NRR

SUBJECT:

REPORT OF QUICK RESPONSE TRIP TO OBSERVE EFFECTS OF THE NORTHERN CHIO EARTHQUAKE ON THE PERRY NUCLEAR POWER PLANT Backg round i

An earthquake occurred at 11:48 a.m. on January 31, 1986 near the Perry Nuclear Power Plant in Northern Ohio. Preliminary information from USGS indicated that the earthquake had a body-wave magnitude (m ) of 5.0, and the h

epicenter is located approximately 12 miles south of the Perry site.

The Perry Plant is a General Electric BWR-6 with a Mark III containment. It is not yet licensed. Nuclear fuel is on site but has not been loaded into the reactor core, The owner of the plant is Cleveland Electric and Illuminating Company (CEI). The utility was performing pre-operational tests and according to CEI, most of the safety related systems were running when the earthquake occurred. Although Perry is not an operating plant and is not required to do so, CEI immediately activated the emergency plan in order to assess facility damage and personnel injuries. No injuries occurred. In addition, NRC and other relevant federal and local agencies were notified of this event. The plant was switched to the recovery mode in the afternoon of January 31, 1986. The recovery organization is shown in enclosure 1.

A detailed walkdown inspection involving about 40, and at times 65, people was t

conducted for the whole plant, which covered buildings, equipment, fostrumentation, piping systems, etc. Only minor damage was found (see preliminary findings below). The inspection was completed at 2:00 a.m. on February 1,1986.

An Austented Inspection Team (AIT) from NRC Region III and staff from NRR were sent to the Perry site on the morning of February 1.

The team from NRR consisted of John Stefano (Perry Project Manager), Leon Reiter and T. Y.

Chang (both from DSR01. They left Perry on the evening of February 2.

The f.'egion III group was led by Carl Paperiello (Director of the Region III Reactor Safety Division). The NRC team held several meetings with the CEI engineering and licensing staff, the Architect / Engineer (Gilbert Associates),

CEI consultants (Weston Geophysical) and suppliers of the seismic monitoring fr.strumentation (Kinemetrics, and Engdahl Enterprises), A list of meeting i

I

, - d ud I "CMW W'T RP 1

$W-4/6 h

% attendees is attached as enclosure 2.

The NRC team members reviewed preliminary seismic recordings and conducted a walk-through inspection of buildings and equipment.

PRELIMINARY FINDINGS 1.

Seismic Records:

The plant had nine sets of seismic monitoring instrumentation on the site when the earthquake occurred. All but one were operating and recorded the earthquake. They are of three different types: triaxial time-history accelerographs (made by Kinemetrics), triaxial peak response spectra recorders, and triaxial peak accelerographs (both made by Engdahl Enterprises). A list of these instruments and their locations is attached as enclosure 3.

There were some difficulties in interpreting data obtained from the Engdahl peak response recorder. Each of these instruments has 12 tuned reeds, each tipped with a diamond stylus which makes scratches on a recording plate.

Some of these instruments are wired to annunciators in the control room.

Each annunciator has one set of 12 amber lights and one set of 12 red lights, with each set of lights marked with the corresponding 12 tuned reed.

frequencies. These amber lights and red lights are pre-set to be activated at FSAR values of 2/3 OBE spectral accelerations and full OBE spectral accelerations respectively for the corresponding tuned reeds. The recording plates have been in these instruments for about a year, and spurious

)

annunications have occurred previously when there were no earthquakes. Paul Engdahl, President Of Engdahl Enterprises, was present at Perry during the visit and helped interpret che data obtained from the scratched plates. shows the preliminary data from the Engdahl instruments in the reactor building and the auxiliary building as plotted on the FSAR spectra.

The 2% damping spectra curves should be used for comparison since the reeds have a built-in 2% damping.

There were some concerns about the way the Kinemetrics instruments were installed at the reactor base mat level. The instruments are not located on the mat, rather they are positioned on brackets bolted on the containment wall 9" above the mat. A " ring" test done by Kinemetrics proved that the brackets are rigid enough to render the data valid.

Partial preliminary time history data obtained from the Kinemetrics instruments located at the reactor building foundation (575') and on the containment vessel annulus (682') and the associated response spectra generated by Kinemetrics are shown in enclosure 5.

Note that the grade level of the plant is at 620'.

1 Enclosures 4 and 5 indicate that there is a strong possibility that both OBE 4

and SSE design response spectra may have been exceeded in the frequency range of approximately 16 Hz and above. The design basis for SSE is a Regulatory Guide 1.60 design response spectra anchored at 0.159, with the OBE spectra l.-- -

s anchored at 0.075g. Preliminary data indicated a Zero Period Acceleration (ZPA) value of 0.189 at the reactcr base mat. These recorded data are being further studied.by the NRC and CEI consultants and instrument suppliers.

2.

Results of Preliminary Plant Inspection Damage to the Perry Plant was assessed by CEI and found to be limited to hair line cracks in rad waste and auxiliary building walls and a pipe flange leak in a hot water heater in the rad waste building. In most cases CEI was not able to determine whether or not these cracks were there before the earthquake. The hot water heater supplies clean non-radioactive steam to an evaporator, and the leakage rate was estimated to be about 20 drops per minute. In addition, a rotating disc type protective relay for the turbine generators tripped, which in turn caused an auxiliary boiler to trip. Since the turbine generators were not in operation at the time of the earthquake, there was no voltage across the relay and, therefore, the rotating disc was hanging loose there. It tripped due to the earthquake motion which would be expected. An instrument air compressor tripped; however, one of the three other instrument / service air compressors in the plant automatically started.

There was also an indication that suppression pool water level indicators might have malfunctioned during and after the earthquake. CEI is still looking into this matter. Seepage of ground water through the junction of wall and floor and through cracks in the wall was also observed in the rad waste building after the earthquake. The seepage was not considered severe.

The NRC staff participated in a walk-down of the plant to inspect for damage and anomalies. The NRC staff walk-down observations are recorded in enclosure 6.

CONCLUSIONS 1.

No damage of any significance was observed at the Perry plant by the NRC staff during the trip.

2.

Based on the preliminary records of seismic monitoring instruments at the plant, the staff concluded that there is a strong possibility that the OBE and SSE design response spectra (FSAR values) may have been exceeded in the frequency range above approximately 16 Hz. It has been pointed out that the high frequency range of Regulatory Guide 1.60 spectra is not as conservative as the lower frequency range. However, the records obtained at Perry are still puzzling since the seismic instrumentation on the containment wall at 682 (about 107' above base mat) still shows exceedance of FSAR floor spectra in the frequency range higher than approximately 16 Hz. One would normally expect that the responses in the frequency ranges higher than the building fundamental frequency would be filtered out by the building.

Further analyses and study of the seismic data by CEI staff engineers and consultants may yield new information on this matter.

It should be kept in mind that response spectra do not present all the information

s f about an earthquake. The energy content as a function of frequency is bette'r represented by the Power Spectral Density (PSD), which is an important indicator of damage potential. Another damage potential indicator is the duration of the earthquake. On both accounts, the effects of the earthquake on the Perry plant were observed to be j

minimal. Normally responses in the high frequency range do not have much energy content. Furthermore, the peak time history reading at the base mat lasted for only about one half second.

NRC AND SQUG FOLLOW-UP ACTIONS j

i 1.

The location, aftershocks and travel mechanism of the earthquake sequence will have to be examined and compared with previous seismicity i

so as to determine if there is any impact upon the adequacy of assumptions made in the. Safety Evaluation Repott.

2.

DSR0/NRR had a meeting with representatives of the Division of BWR Licensing on 2/3/86 to brief them of the findings at Perry. It was decided that since the investigation of the effects of this earthquake on Perry is plant-specific, the BWR Licensing Divsion should take the lead. DSR0 will perform an oversight function and provide technical I

assistance if needed.

R. Hermann and L. Reiter were appointed as team leaders in the structural / mechanical and geoscience areas respectively.

A permanent review team is being formed to review the effects of this earthquake on the structural, equipment and geoscience aspects of the Perry plant.

3.

A BWR site investigation team was sent to Perry on 2/6/86. This team consists of A. Lee (Engineering Branch /BWR Licensing Division /NRR) and J. Singh (INEL contractor), and will perform an independent review of safety related equipment.

4.

Seismic Qualification Utility Group (SQUG) will send a team to Perry on 2/10/86 to collect seismic experience data. This information could be useful for the on-going Unresolved Safety Issue (USI) A-46, " Seismic Qualification of Equipment in Operating Plants."

5.

As the analysis and review of the earthquake, and recorded data proceed, additional recommendations to specific generic issues may be forthcoming. among these presently being considered include increased use of parameters other than peak accelerations and response spectra to better reflect the damage potential of earthquake ground motion and a clearer definition of OBE and/or SSE exceedance and their implications.

lL ~ =ys::p*

A

~

T. Y. Chang Leon Reiter Task Manager Sr. Reliability and Risk Analyst cc: See Page 5.

k cc:

H. Denton S. Broccum D. Eisenhut L. Heller R. Bernero N. Chokshi W. Sutler L. Shao, RES G. Lainas G. Bagchi J. Stefano G. Giese Koch S. Stern P. T. Kuo T. Speis R. Rothman B. Sheron A. Lee N. Anderson P. Sobel Lic. Div. Directors R. Hermann Lic. Div. A/Ds C. P. Tan G. Arlotto, RES J. Richardson, RES C. Paperiello, Reg. III

C N C L O.T w f /

RECOVERYORGANIZATIM E 0VERY 15NER N. R. EDELMN s

N. D. LYSTER :

A. KAPLAN

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AND PEDIA

S. F. KEhSIO(I : : R. A. STRATMN : : D. J. TAMCS :

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ENct.oJune 2.

s MEETING ATTENDANCE February 1, 1986 TEC NAME COMPANY POSITION N. J. Lehman CEI Staff Analyst i

J. J. Waldron CEI Manager, Technical Dept.

l K. A. Connaughton NRC Resident Inspector J. W. Muffett NRC, Region III Plant System Section Section Chier l

J. J. Harrison NRC, Region III Chief, Eng. Branch, DRS C. J. Paperiello (Team leader)

NRC, Region III Director, Div. Reactor Safet C. R. Angstadt CEI L ead Structural Engineer E. M. Buzzelli CEI Sr. Licensing Engineer K. R. Pech CEI Gen. Su'p. Eng., Nuc1 Constr.

1 M. N. Geyrek CEI Sr. Operations Coordinator R. A. Stratnan CEI Gen. Supervisor, Operations H. L. Williams CEI Executive Vice President A. Kaplan CEI V.P. Nuclear Operations Div.

M. D. Lyster CEI Manager, PPOD l

.F. R. Stead CEI Manager, NED B. A. Stiles CEI Community Relations Asst.

John J. Stefano NRC/NRR Perry Project Manager i

Leon Reiter NRC/NRR Sr. Reliability & Pipe Analyst T. Y. Chang NRC/NRR Task Manager W. E. Coleman CEI GSE, Community Relations G. R. Leidich CEI GSE, Outage Management D. J. Takacs CEI Gen. Sup., Maintenance J. A. Grobe NRC Sr. Resident Inspector M. J. Hayner CEI Licensing Engineer e

m

~

b 2

Attendance - February 1, 1986 - TEC NAME COMPANY POSITION M. H. Minns CEI Licensing Engineer R. G. Schuerger CEI Chairman, NSRC E. N. Levine Weston Geophysical Seismologist, Consul-tant to CEI Gabriel Leblanc Weston Geophysical Seismologist, Consul-tant to CEI Steve Kensicki CEI Technical Superintendent Bill Kanda CEI GSE, Technical Dan Hulbert CEI Emergency Planning Sup.

George Siegel Kinnemetrics Field Operations Sup.

Vince Concel CEI PPTD System Engr. Lead Paul Engdahl Engdahl Enterprises -

President Roger Alley Gilbert, Inc.

Project Structural Eng.

Frank Kocsis CEI Independent Safety Eng.

Cyril Shuster CEI Manager, CA Ronald L. Farrell CEI Manager, PP9D 4

Murray R. Edelman CEI V.P., Nuclear Group

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SEISNIC MONITORING INSTRUMENTATION

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