ML20239A672
| ML20239A672 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/11/1987 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8709180084 | |
| Download: ML20239A672 (59) | |
Text
__
September 11, 1987 Docket No. 50-219 LICENSEE:
GPU Nuclear Corporation Jersey Central Power and i.ight Company i
FACILITY:
Oyster Creek Nuclear Generating Station
SUBJECT:
SEPTEMBER 3, 1987 MEETING WITH GPU NUCLEAR CORPORATION (GPUN) TO DISCUSS MATTERS RELATED TO NEW SEISMIC FLOOR 1
RESPONSE SPECTRA FOR OYSTER CREEK NUCLEAR GENERATING STATION i
On Thursday, September 3, 1987, a meeting was held at NRC, Bethesda, Maryland with GPUN (the licensee) to discuss the licensee's proposed methodology to develop new seismic floor response spectra for the Oyster Creek Nuclear Generating Station. Enclosure 1 is the list of individuals participating in the dis. ision.
Enclosure P is the licensee's agenda. The following is a sumary of the significant items discussed.
The licensee indicated that several different floor response spectras have been used in the design of the Oyster Creek Nuclear Generating Station.
Based on this, they indicated that there was a strong need for unification of Oyster Creek re3ponse flcer spectra and they proposed a methodology to develop. new seismic floor response spectra for Oyster Creek including soil-structure interaction. They also stated that in developing the new floor response spectra, GPUN shall be using the.165g ground spectra developed during the systematic evaluation program. GPUN intends to use these newly developed i
floor response spectra for all future work. The staff indicated that the use of a.16% ground spectra may not he appropriate for all future work. The staff indicated that we will advise GPUN of its acceptability.
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We further indicated that GPUN provide the following additional information:
1.
A comparison between the design basis floor response spectra and the i
newly developed floor response spectra for key major components in the l
plant.
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P.
Effect of saturated soil on the soil structure interaction re:sults using the Super Flush Code.
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Due to the effect of the soil structure interaction analysis, the i
frequencies of the newly developed floor response spectra at the peak
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responses will be different than those using the design basis floor i
response spectra. Provide the effect of this frequency shift on the
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component responses.
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.We also advised ~GPUN that we intend to audit the' analysis methodology including l
sample calculations of~the analysis results.
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Alexander Dromerick, Project Manager.
i Project Directorate I-4 Division of Reactor Projects I/II
Enclosures:
As stated cc w/ enclosures:
- See next page l
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e Mr. P. B Fiedler Oyster Creek Nuclear Oyster Creek Nuclear Generating Scr 'on
. Generating Station'
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Ernest L. Blake, Jr.
Resident Inspector
'Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC i
2300 N Street, NW-
- Post Office Box 445 Washington, D.C.
20037 Forked River, New Jersey 08731 a
J.B. Liberman, Esquire Commissioner l
Bishop, Liberman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New. York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineering l
U.S. Nuclear Regulatory Commission Department of Environmental Protection
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631 Park Avenue CN 411 King.of Prussia, Pennsylvania '19406-Trenton, New Jersey '08625 BWR Licensing Manager
.GPU Nuclear. Corporation
~1 Upper Pond Road Parsippany, New Jersey 07054 4
Deputy Attorney General State of.New Jersey Department of Law and Public Safety 36 West State Street - CN :112 Trenton, New Jersey 08625-l Mayor.
Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 l
Licensing Manager
.0yster Creek Nuclear Generating Station
-Mail Stop: Site Emergency Bldg.
P. O. Box 388 1
Forked River, New Jersey 08731 I
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OYSTER CREEK DOCKET NO. 50-219 MEETING - SEPTEMBER 3, 1987 j.
LIST OF ATTENDEES
'Name Organization l
A. Dromerick NRR, DRP I/II J. Rogers.
GPUN,-OC Licensing John Lysmer' U. C. Berkeley Marty Czarnecki URS/Blume Lincoln Malik URS/Blume Ahmad Kabir-URS/Blume Ron Zak GPUN, Engr Mechanics Leon Garibian GPUN, Engr Mechanics A. P. Rochino GPUN, Engr Mechanics Hans Ashar NRR David C. Jeng NRR Goutam Bagchi NRR/ DEST /ESGB R. F. Wilson GPUN E. F. O'Connor GPUN Y. Nagai GPUN G. Capodanno GPUN LA. J. Phillipacopoucos Brookhaven National Lab I
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I SEISMIC ANALYSIS METHODOLOGY AND CRITERIA TO DEVELOP FLOOR RESPONSE SPECTRA FOR THE OYSTER CREEK NUCLEAR GENERATING STATION i
presented to I
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GPU Nuclear and URS/ John A. Blume & Associates, Engineers t
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AND SITE CONDITIONS 4
l-1 REACTOR BUILDING 1
- BWR Mark l Plant
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- 53 ft. Embedment in Soll
- 10 ft. Mat Foundation ll SITE SOIL CONDITIONS
- Deep Alluvial Deposits - about 1800 ft. deep
- Ground Water Table 23 ft. below Ground Surface 1
- Bedrock at Elevation = -1800 ft.
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Beam Elements used to model superstructure. 2 D,4 Node element with two transnational and one rotational DOF prescribed at each end.
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r DESCRIPTION OF ELEMENTS (continued)
. Viscous Dashpots simulate effects of 3-D soll on the 2-D soll element nodes. This element is based on the analogy between the dynamic response of a uniformly loaded elastic half space and a viscous dashpot.
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Rigid and Flexible Floor Slabs e
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