U-600281, Forwards Equipment Seismic Assessment Program for Safety- Related Mechanical & Electrical Equipment, Per Proposed Program in .Sufficient Assurance Exists That Emergency Power & DHR Sys Can Withstand SSE
| ML20133G871 | |
| Person / Time | |
|---|---|
| Site: | Clinton |
| Issue date: | 10/14/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20133G872 | List: |
| References | |
| U-600281, NUDOCS 8510160165 | |
| Download: ML20133G871 (2) | |
Text
e en U-600281 L30- 85 (10- 14 )-L 1A.120 ILLINOIS POWER OOMPANY IP CLINTON POWER STATION. P.o. BOX 678. rLINTON. ILLINOIS 61727 October 14, 1985 Docket No. 50-461 Director of Nuclear Reactor Regulation Attention:
Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Equipment Seismic Assessment Program Report
Dear Mr. Butler:
Attached is the report entitled "Clinton Power Station Equipment Seismic Assessment Program for Safety-Related Mechanical & Electrical Equipment". This report describes the results of the Equipment Seismic Assessment Program originally proposed in the Illinois Power Company letter U-0484, dated May 19, 1982. The program was developed in response to a cotment made by the Advisory Committee on Reactor Safeguards (ACRS) in their March 9, 1982, letter to Nunzio J. Palladino, Chairman NRC, concerning the Clinton Power Station. The ACRS recommended that " specific attention be given to the scismic capability of the emergency AC power supplieu, the DC power supplies, and small components such as actuators and instrument lines that are part of the decay heat removal system".
The Clinton Power Station Equipment Seismic Assessment Program was implemented in three phases. Phase 1 examined the adequacy of the design methods used for small bore piping. Phase II examined the as-built equipment configurations of the decay heat removal and emergency power supply systems for seismic concerns. Phase III evaluated the ability of equipment in these systems to withstand an earthquake of the form predicted by the revised response spectra, developed using the clastic half space approach for soil-structure interaction.
The report concludes that there is sufficient assurance that the emergency power and decay heat removal systems can withstand the safe shutdown earthquake.
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Following your review of this material, if you should have any questions on this issue, please contact me.
Sincerely yours, I
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%p F.A.jpangf1 berg Managet - Li,:ensing and Safety AJH/kaf Attachment cc:
B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety