ML20059H924
| ML20059H924 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/23/1993 |
| From: | Keaten R GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20059H927 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR 5000-93-0073, 5000-93-73, C321-93-2321, GL-87-02, GL-87-2, NUDOCS 9401310236 | |
| Download: ML20059H924 (3) | |
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GPU Nuclear Corporation n.. f g
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Writers Direct Dial Number December 23, 1993 5000-93-0073 C321-93-2321 i'
U. S. Nuclear Regulatory Commission Att: Document Control Desk Wathington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Operating License No. DPR-16 Docket No. 50-219 In-structure Response Spectra Our response to Supplement 1 to Generic Letter (GL) 87-02, "SQUG Resolution of USI A-46" dated September 14, 1992 stated that new in-structere response spectra were being developed.
Enclosed for your review is a report (Attachment 1) entitled, " Der gn Criteria for Soil Structure Interaction Analysis of the Reactor / Containment Building at GPU tk@ar/0yster Creek Nuclear Generating Station" (EQE report dated June 1993).
This document describes the soil-structure interaction analysis conduc'ed by EQE to obtain design in-structure response spectra for the OCNGS Reactor Building. This analysis conforms to all applicable portions of the NRC Standard Review Fian as discussed in Appendix B and Sections 1 through 5 of tne report. The methodology and the results of the analysis have been reviewed by GPU Nuclear angineers and by our consultant, Dr. Robert P.
Kennedy.
Two site specific response spectra (SSRS) were used in the analyses /stadies t
described in this report. One is the SSRS developed from the 72 earthquake record data set, referred to as the "NRC Recommended Data Set" in our DecemMr 30, 1991 letter. The other is the SSRS developed from the 67 earthquake record data set submitted in our December 30, 1991 letter and accepted in your Safety Evaluation Report (SER) dated March 18, 1992. Due to the timing of previous commitments to the NRC, preliminary results were needed prior to the receipt of the SER on March 18, 1992. Therefore, portions of the analysis were conducted prior to March 18 with the NRC recommended data set. Analyses conducted after March 18 used the 67 earthquake data set.
The following paragraphs explain which set was used for each portion of the analysis.
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Section 2 of the report presents all the seismic input data to be used to generate the in-structure response spectra. This includes the horizontal SSRS from the 67 record data set, vertical SSRS and Power Spectra Density functions (PSDFs) for both the horizontal and vertical SSRS. The vertical SSRS are developed using the 34 vertical components from the earthquakes used to obtain the horizontal SSRS. The methodology for the vertical SSRS is the same as that used for the horizontal SSRS. The details are provided in the attached report " Site Specific Response Spectra" prepared by Weston Geophysical, dated December 20, 1991 (Attachment 2).
The details of the PSDF calculation and results are provided in the attached memos prepared by Weston Geophysical and i
transmitted to EQE Engineering on September 2, September 25 and October 14, 1992 (Attachments 3-5).
Section 5 presents the sensitivity analyses conducted to arrive at the final soil-structure interaction model. These analyses use the SSRS from the 72 record data set.
EQE has determined, and Dr. Kennedy has agreed, that the final soil-structure interaction model would not be affected if the SSRS from the 67 record set had been used.
During the development of the soil-structure interaction model, questions were raised by Dr. Kennedy, EQE Engineering and GPU Nuclear Engineering regarding the soil profile used in previous analyses conducted at OCNGS.
Therefore, a decision was made to review all available data, determine its validity and adequacy and develop a technically appropriate dynamic soil profile for use in the soil structure interaction model. GPU Nuclear contracted with Geomatrix Consultants, Inc. to perform this work. The results are contained in the attached Geomatrix report " Soil Profile and Dynamic Soil Properties for Soil-Structure Interaction Analysis of Reactor Building, Oyster Creek Nuclear Generating Station," (Attachment 6) and are summarized and used in Section 3 i
of the EQE report. The Geomatrix Report has been reviewed by GPU Nuclear engineers and Dr. Kennedy.
GPU Nuclear intends to un the methodology and criteria presented in the attached EQE report to develop in-structure response spectra for the OCNGS reactor building and for other applicable structures at the OCNGS site. This methodology is in conformance with all ;rovisions of the US NRC Standard Review Plan. Therefore, GPU Nuclear intends to use the resulting spectra to conduct evaluations in response to Generic Letter 87-02.
In addition, GPU Nuclear intends to use the spectra in conjunction with damping values specified in Regulatory Guide 1.61 and ASME code case N411 for all future designs, analyses and evaluations performed at OCNGS.
GPU Nuclear would like to proceed with the evaluations in response to Generic Letter 87-02.
Therefore, we request a review at your earliest convenience.
If you wish to discuss the information contained in the attached report, we will be pleased to meet with you at your convenience.
C321-93-2321
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If you have any questions or comments, please contact Michael W. Laggart at (201) 316-7968.
I Sincerely, i
R. W. Keaten, Director, Technical Functions Enclosure i
RWK/YN/ pip cc: Administrator, Region I NRC Oyster Creek Project Manager Senior Resident Inspector l
.