ML20003G603

Forwards Info to Be Added to Chapter 1 of Design Assessment Rept in May 1981,including Safety Relief Valve Basis Frequency range,4TCO Data Assessment,Functional Capbaility Criteria & Fatigue Evaluation.W/O Encl

ML20003G603
Person / Time
Site:	Zimmer
Issue date:	04/28/1981
From:	Flynn J CINCINNATI GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8104300242
Download: ML20003G603 (1)

Text

{{#Wiki_filter:-{7':TT~ r W L THE CINCINNATI GAS & ELECTRIC COMPANY cr1. _ h G $ D CINCINNATI. OHIO 45201 Docket No.50-358 April 28,1981 Mr. Harold Denton, Director Office on fluclear Reactor Regulation M ~. U.S. Nuclear Regulatory Commission g?' .,y. g Washington, D.C. 20555 1 y 'f b u' 'l i [ y RE: WM. H.Zimmer Nuclear Power Station - Unit 1 - Mark II Closure , fi gigfj98P 1 f .NQ1Ws _[l \\s.

Dear Mr. Denton:

\\{' ..s,S x ' 'v Enclosure A includes: (1) SRV Design Basis Frequency Range (2) 4TC0 Data Assessment Enclosure B includes: Functional Capability Criteria as Compared to NED0 21985 Enclosure C includes: Fatigue Evaluation of SRV and Downcomer Piping. This information will be added to chapter 1 of the Design Assessment Report (DAR) in May,1981. Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY By [ James D. Flynn cc: Service List 810.43noj # Ag_ -}}