ML20237A090

Ack Receipt of Which Withdrew Violation 50-382/97-25 Re Failure to Follow Condition Reporting Procedures,Per 10CFR50,App B,Criterion V.Documentation That Supports Current Use of 0.3 Valve Factor for Valves,Encl

ML20237A090
Person / Time
Site:	Waterford
Issue date:	08/07/1998
From:	Ewing E ENTERGY OPERATIONS, INC.
To:	Dyer J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20237A093	List: ML20237A090 ML20237A098
References
50-382-97-25, W3F1-98-0144, W3F1-98-144, NUDOCS 9808130092
Download: ML20237A090 (4)

Text

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, Eniergy per tions, toc.

Kdvy:-a. LA 70066

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To L]4 739 624?

Early C. Ewing.10 I

. a ef, & Regulatory N%rs W3F1-98-0144 ,

A4.05 PR August 7,1998 Mr. J. E. Dyer Deputy Regions' Administrator, Region IV U.S. Nuclear Regulatory Commission l

i 611 Ryan P;aza Drive, Suite 400 Arlington, TX 70011 3 i

Subject:

Waterford 3 SES )

Docket No.60-382 License No. NPF-38 Response to Withdrawal of Violation 50-382/9725-04 and (

Supplementary Information for Unresolved item 50-382/9725-03

Dear Mr. Dyer:

Thank you for your letter of June 9,1998, which withdrew Violation 50-382/9725-04 related to a failure to follow condition reporting procedures as required by 10 CFR 50, Appendix B, Criterion V. The letter also described a conference call conducted I on June 4,1998, between Waterford and the NRC to discuss the use of a 0.3 valve factor to analytically predict feedwater isolation valve response to design basis accident conditions. This use of the 0.3 valve factor was addressed in inspection l Report 50.382/97-25 and identified as Unresolved item 50-382/9725-03. During the j conference call, Waterford agreed to perform an analysis for the feedwater isolation  !

valves based on the Electric Power Research Institute (EPRI) Performance Prediction Methodology (PPM) prior to our February 1999 refueling outage. l

!n addition to porforming an analysis using the EPRI PPM, Waterford agreed to provide Region IV the following information:

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(1) documentation supplied by our vendor, Anchor-Darling, that supports the current .

ese of a 0.3 valve factor for the feedwater isolation valves; and k3 I (2) any revised operability evaluations performed as a result of using the EPRI PPM.

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Response to Withdrawal of Violation 50-382/9725-04 and Supplementary information for Unresolved item 50-382/9725-03 -

W3F198-0144 Page 2 i August 7,1998 l

Enclosed is documentation supplied by our vendor. Anchor-Darling, that supports the currei.c use of a 0.3 valve factor for the feedwater isolation valves wt Wateiford. Any

. revised operability evaluations performed as a result of using the EPRI PPM will be l 9 provided by November 13,1958.

Should you have any questions, please feel free to contact me at (504) 739-6242.

Very truly yours, E.C. Ewing Director Nuclear Safety & Regulatory Affairs l

ECE/BVR/rtk

Enclosures:

1. Memo from Anchor Darliag, dated June 18,1998

2. Anchor Darling Report Number CTS-27 (w/ Enclosures) cc: E. W. Merschoff C.P. Patel, NRC-NRR L. J. Smith M. Runyon N.S. Reynolds . ,,. ..

NRC, Document Control Desk 1 NRC Resident inspectors Office l

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NQIE BW/IP W11ERNATIONAL AND DURCO INTERNATIONAL RECENTLY '

MERGED TO FORM FLOWSERVE CORPORA TION TELECOPY/ FAX PAGE 1 OF 1 i TO: KIMBERLY COOK FROM: DOUGLAP 8. O'CONNOR ENTERGY-WATERFORD 111 PRODUCT MANAGER-LJNE VALVES PHONE: (717) 327 4923 ]

FAX: (717) 327 4888 VIA FAX (504)739 4564 DATE: June 18,1998

SUBJECT:

VALVE FACTOR - FEEDWATER ISOLATION VALVES

REFERENCE:

OUR TELECON OF JUNE is,itse Kirnberty, in response to your earlier toisphone inspasty, BW4P is ploaeed to provitte the foNowlog technical infonnation regarding actuator sizing for foodweenr loolation valves:

. BW4P% standard valve factor uend in 't-

• J'-g = requined actuator thrusts for foschusser leolation service is 0,3. Shouhl no customer specilled .TJ '-- O regartling valve factor be forwanted with a request for quotation or purchase ortler, we would default to this standard 8.3 factor.

. For funherJusensapon on the use of a 9.3 valve factor, paan

• refer kn eier Report No.

CTS-27, High Enewgy Flow Tesdng of a $*400 Doulde Disc Gate Valve (aiready in your Possession).

should you nusuko any addhional infonnasion, feel ftee to give one a call.

Regenes

N gp gl{1nyrn ti:n I, Inc.

Anchor / 701 F.*st #mamspo- Teiephone Darling Street Sams, van.a 717 327 4800 Valves ' P O Sca 70'4408 Fan y, 3428 71? 327 4805 vei. -

at:o Actuator.

March 19,1998 Kimberly Cook Waterford 3 Highway 18 Killona LA 70066 a

SUBJECT:

Evaluation of 20 Inch Feedwater isolation Valve

Dear Kim:

Per our discussion this week you will find enclosed a copy of the Summary Report for the 6" 900 class, double disc valve that was tested about six years ago. Also enclosed are laboratory tests conducted on Stellite 6 for wear and friction characteristics.

I trust that this information may be helpful in evaluating your feedwater valves. I believe the kinetic energy provided by the type of actuator on these valves may be an important factor for consideration.

Should you have further questions, please do not hesitate to call.

Sincerely, h.'.Y eMC William G. Knecht Technical Director WGKjs Enclosures cc: D. S. O'Connor f

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