ML20093G906

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Forwards Interim Closure Rept Re Compliance W/Proposed Upgrades to Reactor Vessel Water Level Measurement Sys Design.Rept Forms Basis for Resolving TMI Action Plan Item II.F.2.Final Rept Will Be Submitted by Late Oct 1984
ML20093G906
Person / Time
Site: Clinton Constellation icon.png
Issue date: 10/10/1984
From: Spangenberg F
ILLINOIS POWER CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML20093G909 List:
References
TASK-2.F.2, TASK-TM U-0749, U-749, NUDOCS 8410160089
Download: ML20093G906 (2)


Text

y U4749 L30-84(10-10 )L 1A.120 ILLIN0/8 POWER COMPANY

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CLINTCN PCWER STATICN. P.o. BCX 670. CLINTON.. ILLINOl$ 61727 October 10, 1984 Docket No. 50-461 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief 3 Licensing Branch No. 2 Division of Licensing

. U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station Unit #1 NUREG-0737, TMI Action Plan Item II.F.2 Instrumentation for Detection of Inadequite Core Coolina

Dear Mr. Schwencer:

Attached is an Interim Closure Report regarding Illinois Power's compliance with proposed upgrades to the Reactor Vessel Water Level Measurement System (WLMS) design. These WLMS design enhancements were ,

originally addressed in submittals to the Nuclear Regulatory Commission (NRC) staff from the Boiling Water Reactors Owner's Group (BWROG) for TMI activities, of which Illinos Power Company is a participating member. Specifically, two reports, SLI-8211 entitled " Review of BWR Raactor Vessel Water Level Measurement Systems" and SLI-8218 entitled

" Inadequate Core Cooling Detection in Boiling Water Reactors", were prepared by Sol Levy Inc. for the BWROC and provided to the Staff for review. The attached Interim Closura Report addresses the concerns identified within these BWROC reports as they relate to the Clinton Power Station (CPS).

. As a result of the plant-specific evaluations performed for CPS, Illinois Power is incorporating design modifications to the.WLMS which

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enhance the reliability and accuracy of this system during postulated plant accident conditions. These modifications include instrument sensing line re-routing within the drywell to limit the overall vertical drop to within approximately 30 inches and relocation of the instrument line flow limiting orifice plates to near the corresponding drywell penetration. The design for these modifications to the C?S WLMS is complete and construction implementation is underway.

A final comprehensive evaluation report of the CPS WLMS will be submitted to the NRC Staff in late October, 1984. The attached Interim '

Closure Report provides the highlights from this final report and forms t

9410160089 041010 PDR ADOCK 05000461 A PDR

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U 0749 L30-84(10-10 )L 1A.120 the basis for resolving TMI Action Plan Item II.F.2 (Inadequate Core Cooling Detection) for CPS.

Please contact us if you have any questions on the information prcvided in this submittal.

Sincerely yours, q '. .

F. A. S nge erg [

Director - Nuclear U censing Nuclear Station Engideering FAS/DW/im Attachment cc B. L. Siegel, NRC Clinton Licensing Project Manager

. NRC Resident Office Ill!sois Department of Nuclear Safety Regional Administrator Region III USNRC s

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