ML20050C775

Forwards Response to NRC Seismic Qualification Review Team (Sqrt) 820329 Audit Open Items,Following Up NRC 810601 Site Review & Supplementing Util 820421 Seismic Qualification Rept & 810827 Impendance Testing Program

ML20050C775
Person / Time
Site:	Zimmer
Issue date:	04/07/1982
From:	Borgmann E CINCINNATI GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20050C776	List: ML20050C775 ML20050C778 ML20050C780 ML20050C781
References
NUDOCS 8204090346
Download: ML20050C775 (2)

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P-c1 rM THE CINCINNATI GAS & EIECTRIC COMI%NY CINCINN ATI.OHto 4SELI E A. DORGM ANN ge mon M r rat s=ot NT April 7, 1982 A

Docket No. 50-358 \E

1. R>

{ liECEIVED -

Mr. Ilarold Denton, Director = g 8 N2h-Officc. of Nuclear Reactor Regulation D U.S. Nuclear Regulatory Commission .

Washington, D.C. 20555 1, j /f RE: WM. II . ZIMMER NUCLEAR POWER STATION -

UNIT 1 - SEISMIC QUALIFICATION OF EQUIPMENT

Dear Mr. Denton:

Enclosed are eight copies of supplemental information as described in Attachment 1. This is follow-up information to the NRC SQRT Site Review conducted during the week of June 1, 1981 and the NRC December 28 letter discussing that site visit.

This supplements the seismic qualification report previously sub-l mitted on April 21, 1981 and the supplemental information on the impedance testing program submitted on August 27, 1981.

There remains only one piece of equipment within the scope of the impedance program for which a report has not been completed. That remaining piece of equipment is the RCIC steam turbine assembly. Work is currently in progress on this item.

l Requalification of the 480 volt motor control centers is expected to be completed by September 30, 1982. The requalification of l

l l

bok N 1 1 -

6H4 8204090346 820407 l PDR ADOCK 05000358 G A PDR

To: Mr. Harold Denton, Director April 7, 1982 Re: Wm. H. Zimmer Nuclear Power Station - Page #2 Unit 1 - Seismic Qualification of Equipment the RBCCW pumps is anticipated to be complete by April 30, 1982.

Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY By E. A. BORGMANN EAB: dew cc: Without Enclosures John H. Frye III M. Stanley Livingston Frank F. Hooper Troy B. Conner, Jr.

James P. F9nstermaker Steven G. Jmith William J. Moran J. Robert Newlin Samuel H. Porter James D. Flynn W. F. Christianson James H. Feldman, Jr.

John D. Woliver Deborah F. Webb David K. Martin George E. Pattison Andrew B. Dennison J. Singh - EG&G (1/1)

State of Ohio )

County of Hamilton)ss i

Sworn to and subscribed before me this TE day of April, 1982.

{l;m ?U $"k Notary Public AllCE M. LEURCK Hotary Pat $c, State of Ohi, i

Ny Ocmmission Epires Decem*ar 15.

ATTACHMENT 1 Response to NRC SQRT Audit Open Items 3-29-82 Ref: NRC Letter from B.J. Youngblood to E.A. Borgmann dated December 28, 1981.

Generic Open Items ITEM A. (c) Impedance Tests

{~ The following Sargent & Lundy Reports, for NRC review, are enclosed: '

EXHIBIT "A" SGTS Equipment Train IVG05SA & SB EXHIBIT "B" RCIC Pump lE51C001 EXHIBIT "C" RHR Heat Exchanger 1E12B001 The last remaining item is the RCIC Steam Turbine Assembly.

Work is currently in progress on this item.

ITEM A. (b) Fatigue Evaluations A summary report titled " Fatigue Evaluation of Equipment" and a report on the fatigue analysis of the RCIC Pump are enclosed as EXHIBIT "D" and EXHIBIT "E", respectively.

ITEM B. Amplification Factor of 2 Reference is made to the justification furnished to the NRC on the LaSalle Station docket. This justification is also applicable to Zimmer.

ITEM C. Limitorque Motor Operators Enclosed, is a dynamic qualification test report, EXHIBIT "F",

prepared by SDRC covering the qualification of Limitorque motor operators..

l l

ITEM D. Valve "g" Levels and Nozzle Loads The piping analysis work on Zimmer is essentially complete. Where-ever the valve allowable "g" levels and/or nozzle loads were exceeded the valve was requalified for the higher allowables, or the piping loads were reduced by redesign of the support system. Any engineering changes to existing safety related piping will involve a review of the valve "g" levels and nozzle loads to assure that allowables are not exceeded.

Specific Open Items ITEM A. (a) Spent Fuel Storage Rack 1 Ecciosed, is a copy of a Nutech Report citled " Assessment Report -

Spent Fuel Sturage Rack" EXHIBIT "G", which covers our response to the NRC concerns on this item.

ITEM A. (b) Reactor Core Cooling Bench Board Enclosed, is EXHIBIT "H" which lists the non-essential devices on 1 the Reactor Core Cooling Bench Board and the basis for their non-essential classification.

ITEM A. (c) Flow Indicator Switch The referenced Barton Model 288A flow indicator switches will be purchased and installed as replacements for the Model 288 by October 1

, 1982, on the Flammability Control Unit.

l ITEM A. (d) Bailey Alarm Enclosed, is EXHIBIT "I" which provides justification for the use of a reduction factor of 3 for the acceleration at the center of gravity.

ITEM B. Requalifica. tion of BOP Items (a) and (b)

A program for the requalification of the 480 V. Motor Control Center is currently being put into place with an expected completion date of September 30, 1982. The requalification of the RBCCW Pumps is nearly complete with a scheduled completion date of April 30, 1982.