ML19347B638
| ML19347B638 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/08/1980 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Bournia A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19295B962 | List: |
| References | |
| NUDOCS 8010150474 | |
| Download: ML19347B638 (2) | |
Text
._
/^N Commonwealth Edison
/
) orn First National Plaza (
3, Illinois
(
O j Addr:ss R; ply tr Post Ont.e Box 767
\\
,/ Chicago, Illinois 60690 October 8, 1980 Mr. A.
Sournia Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission W1shington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Seismic Qualification Review Program NRC Occket Nos. 50-373, 50-374 FOR ADDRESSEE'S EYES ONLY
Dear Mr. Bournia:
This report augments and updates Edison's last transmittal of August 4, 1980 by inclusion of tne Open Items List for BOP and NSSS equipment for which requalification testing is currer:tly underway, reanalyses are not yet completed, or the last test reports are not yet in the file.
Additionally, this report provides the latest spectra for the reactor building and for the auxiliary building.
These combined response spectra are supplied for various elevations and they include the governing load cases in which NRC interest has centered from the Mark II Containment program.
Adequate spectra are provided to enable a comparison for the reactor building, for instance, of the combined seismic and SRV spectra against the combined seismic and T-quencher spectra.
Such comparisons provide a general framework for an understanding of the present loads associated with floor-and wall-mountec equipment.
Specific comoined spectra are also included for those load combinations requested by the NRC.
These six specific combined spectra include the latest chugging loads, condensation oscillation loads, and SRV-enveloping loads.
These spectra are important for comparative purposes also.
It is important to remember that the original LSCS design basis used bounding spectra from ramshead hydrodynamic loads in combination with normal and seismic loads.
With change-over to the T-quencher design, the pertinent response spectra includes T-quencher hydrodynamic loads in combination with seismic and normal loads.
The comparison of tnese original combineo response spectra (ORSC) with the newer combined response spe;*.ra (NRSC) provides justification for accepting equipment qualir acations based on the original design loaos because the newer T-quenc%e_
combined lads are enveloped by the former.
Tnese spectra are h 31 submited to justify tnat approach.
s
- p 8010150 N '
g
Mr. A. Bournia October 8, 1980 Page 2 The introduction to this report provides a historical background to assist the reviewers in roadmapping this and prior SQRT submittals.
for LSCS equipment both NSSS and BOP;It outlines the SQRT assessment it defines the acceptance criteria; and it elaborates on the requalification efforts for mechanical equipment, valves, electric equipment, and instrument.
For completeness, the roadmap also mentions verification test ef forts such as the in-site impedance test, the future SRV in-plant SRV test, and the characteristic fatigue evaluation, etc.
These verification efforts not only provide confirmation on methodology and models, which is their primary objective but also yield some experimental verification of natural resource,s and unique and equipment damping values.
They also confirm the extent of structure cross-coupling.
Such verification tests are not equipment qualification tests, per se, but are significant, in total, establishing credibility for the LSCS SQRT equipment qualification process.
If you have any questions in this regard, please' direct them to this office.
We will expect you to provide your equipment selection for our SfjRT audit (scheduled for the week of October 27, 1980) by October 15, 1980 as was committed in our meeting of September 24, 1980.
Very truly yours, L. O. DelGeorge Nuclear Licensing Administrator Attachments cc:
Mr. R. Rahl (w/Att.)
NRC Resident Inspector - LSCS (w/o Att.)
7269A
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