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Trip Rept of 860201 Site Visit Re Effects of 860131 Earthquake on Plant.Only Minor Damage Found.List of Meeting Attendees,Recovery Organization Chart & Seismic Recordings Encl
	ML20141N033
Person / Time
Site:	Perry
Issue date:	02/25/1986
From:	Chang T; Office of Nuclear Reactor Regulation
To:	Bosnak R; Office of Nuclear Reactor Regulation
References
	NUDOCS 8603030441
	Download: ML20141N033 (43)
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MEMORANDUM FOR:

Robert J. Bosnak, Chief Engineering Issues Branch DSRO, NRR Frank J. Congel, Chief Reliability and Risk Assessment Branch DSRO, NRR T. Y. Chang, Task Manager FROM:

Leon Reiter.Sr. Reliability and Risk Analyst DSRO, NRR

SUBJECT:

REPORT OF QUICK RESPONSE TRIP TO OBSERVE EFFECTS OF THE NORTHERN OHIO EARTHQUAKE ON THE PERRY NUCLEAR POWER PLANT.

Background

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 s

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

The Perry Plant is a General Electric BWR-6 with a Mark Ill 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 (CE!). The utility was performing pre-operational tests and according to CEI, most of the safety related systems were runnfag 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 af ternoon of Jenuary 31, 1986. The recovery organization is shown in enclosure 1.

A detailed walkdown inspection involving about 40, and at times 65, people was conductedforthewholeplant,whichcoveredbuildings, equipment,(see instrumentation, piping systems, etc. Only minor damage was found preliminary findings below). The inspection was completed at 2:00 a.m. on February 1, 1986.

An Augmented Inspection Team (AIT) from NRC Region !!! 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 DSRO). They left Perry on the evening of February 2.

The Region III group was led by Carl Paperiello (Director of the Region !!!

Reactor Safety Division). The NRC team held several meetings with the CEI engineering and licensing staff, the Architect / Engineer (Gilbert Associates).

CEIconsultants(WestonGeophysical)andsuppliersoftheseismicmonitoring instrumentation (Kinemetrics, and Engdahl Enterprises). A list of meeting

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p. enbodf s(tEf%

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2 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 seismie monitoring instrumentation on the site when the earthquake occurred. All but one were operating and recorded the earthquake. The triaxial time-history accelerographs (y are of three different types:made by Kinemetrics), triaxial peak respon 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 teak 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 Ifghts marked with the corresponding 12 tuned reed frequencies. These amber lights and red Ifghts 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 abut a year, and spurious annunications have occurred previously whe". there were no earthquakes. Paul Engdahl, President of Engdahl Enterprises, was present at Perry during the visit and helped interpret the 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 21 damping spectra curves should be used for comparison since the reeds have a built-in 2% damping.

There were some concerns cbout 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'.

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

3-anchored at 0.0759 Preliminary data indicated a Zero Period Acceleration (ZPA) value of 0.18g at the reactor base mat. These recorded data are being further studied by the NRC and CEI consultants and instrument suppTiers.

2.

Rasults of Preliminary Plant Inspection Damage to the Perry Plant was assessed by CE! 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 tne 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. $1nce 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 othar 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 af ter the earthquake. CEI is still locking 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 af ter 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 enalosure 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 Wssibilit) Nt the OBE and $$E 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 well at 682 habout 107' above base mat) still shows exceefance 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 yleid new information on this matter. It should be kept in mind that response spectra do not present all the information

4 about an earthquake. The energy content as a function of frequency is better represented by the Power Spectral Density (PSD), which 'is an important indicator of damage potential. Another damage potential j

Indicator is the duration of the earthquake. On both accounts, the effects of the earthquake on the Perry plant were ob:erved to be minimal. Normally responses in the high frequency range do not have 4,

much energy content. Furthermore, the peak time history reading at the base met lasted for only about one half second.

NRC AND SOUG FOLLOW-UP ACTIONS 1.

The location, af tershocks and travel mechanisr of the earthquake sequence will have to be examined and compared with previous seismicity so as to determine if there is any impact upon the adequacy of assumptions made in the Safety Evaluation Report.

2.

OSR0/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 EWR Licensing Divsion should take the lead. DSR0 will perform an oversight function and provide technical assistance if needed.

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

l 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 /8WR Licensing Division /NRR) and J. Singh (INEL contractor), and will perfom an independent review of safety related equipment.

4.

Seismic Qualification Utility Group (SQUG) will send a team to Perry on E/10/86 to collect seismic experience data. This information could be useful for the on going Unresolved Safety Issue (USI) A-4G, " Seismic

?;sH'Wint of FWe**nt in Operating Plants."

5.

As the analysis and review of the earthquake, and recorded data proceed, additional recomendations 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 $$E exceedance and their implications, b=W

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

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H. Denton S. Brocoum D. Eisenhut L. Heller R. Bernero N. Chokshi W. Butler L. Shao. RES G. Lafnas G. Bagchi J. Stefano G. Giese Koch S. Stern p, y, gua T. Spets R. Rothman

6. Sheron A, t,,

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 t

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enc t.o. vog-z MEETING ATTENDANCE TEC

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February 1, 1986 r

NAME COMPANY ROSITION N. J. Lehman CEI Staff Analyst '

J. J. Waldron CEI Manager Technical Dept.

K. A. Connaughton NRC Resident Inspector J. W. Huffett NRC, Region III Plant System Section Section Chief 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 CCI Lead Structural Engineer E. H. Buzzelli CEI Sr. Licensing Engineer K. R. Pech CEI Gen. Sup. Eng., Nuci Constr.

M. N. Gmyrek CEI Sr. Operations Coordinator R. A. Stratman CEI Gen. Supervisor, Operations H.'L. Williams fEI Executive Vice President A. Kaplan CEI V.P. Nuclear Operations Div.

M. D. Lyster CEI Manager, PPOD F. R. Stead CEI Manager, NED B. A. Stiles CEI Community Relations Asst.

John J. Stefano NRC/NRR Perry Project Manager Leon Reiter NRC/NRR Sr. Reliability & Pipe Analyst T. Y. Chang NRC/NRR Task Manager W. E. Colema.

CEI GSE, Community Relations G. R. LeiJich CEI GSE, Outage Management D. J. Ta<acs CEI Gen. Sup., Maintenance J. A. Grobe NRC Sr. Resident Inspector M. J. Hayner CEI Licensing Engineer

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NAME-COMPANY

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M.'H. Minns CEI Licensing Engineer

~. G. Schuerger CEI

. Chairman, NSRC R

E. N. Levine Weston Geophysical Seismologist, Consul-tant to CEI Gabriel Letlanc' 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.

r 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, GA Ronald L. Farrell CEI Manager, PPSD Murray R. Edelman CEI V.P., Nuclear Group

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StiSMIC MON!TORING INSTRUMENTATION

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