ML20080B464

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Forwards Nonproprietary Version of Independent Evaluation of Proposed Mods to Westinghouse D4,D5 & E Steam Generators. Mods Will Reduce Tube Vibration in Preheater Section & Do Not Result in Unreviewed Safety Question
ML20080B464
Person / Time
Site: Harris, Byron, Braidwood, South Texas, 05000000, Marble Hill
Issue date: 08/01/1983
From: Butterfield L
COMMONWEALTH EDISON CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20080B467 List:
References
1101R, NUDOCS 8308050512
Download: ML20080B464 (3)


Text

Commonwe:lth Edison s

) one First National Plaza, Chicago, tilinois 3

C */ Address Reply to: Post Office Box 767 j Chicago, Illinois 60690 August 1, 1983 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Counterflow Steam Generator Owners Review Group Evaluation of Westinghouse Proposed Modifications to Model 04, D5 and E Steam Generators, NRC Dockets 50-400, 50-401, 50-454, 50-455, 50-456, 50-457, 50-498, 50-499, 50-546, 50-547

Dear Mr. Eisenhut,

Enclosed are forty copies of the Counterflow Steam Generator Owners Review Group (CSG0RG) evaluation of the Westinghouse proposed modifications to the model D4, D5 and E steam generators to minimize flow induced vibration in the preheater section.

The non-proprietary report, titled " Independent Evaluation of Proposed Modifications to Westinghouse D4, D5 and E Steam Generators" CSG0RG-002, has been reviewed and approved by the members of the CSGORG.

The domestic utility members of the CSGORG, their plants and i

l NRC docket numbers are as follows:

t Utility Plant Docket No.

Carolina Power & Light Co.

Shearon Harris 1 50-400 Shearon Harris 2 50-401 i

Commonwealth Edison Co.

Byron 1 50-454 l

Byron 2 50-455 I

Braidwood 1 50-456 Braidwood 2 50-457 Utility Plant Docket No.

Houston Lighting & Power Co.

South Texas 1 50-498 South Texas 2 50-499 Public Service Company Marble Hill 1 50-546 of Indiana Marble Hill 2 50-547 Y ;/ A0 Y

9308050512 830801 (3CI PDR ADOCK 05000400 A

PDR

o This report was discussed with Mr. T. Novak and other members of your staff in Bethesda, MD on July 7, 1983 where the CSG0RG presented the following conclusions:

The modification will reduce tube vibration in the preheater section to an acceptable level for long term operation.

The modifications to the model D4, D5 and E steam generators does not result in an unreviewed safety question.

This report is intended for use by the domestic utilities to support the licensing of plants containing model D4, D5 and E steam generators and will be referenced by them.

Related plant specific modification information will be submitted as revisions to the appropriate Plant Final Safety Analysis Report.

Each utility will, on an individual basis, address other items that it determines to be appropriate, such as surveillance programs and the schedule for implementation.

The proprietary version of this report, with the same title and number CSG0RG-001, was submitted to the Nuclear Regulatory Commission by letter dated July 18, 1983.

Any questions concerning the report should be communicated to:

Dr. M.G. Zaalouk, Chairman Technical Review Committee Counterflow Steam Generator Owners Review Group Houston Lighting & Power Company P.O. Box 1700 Houston, Texas 77001 Telephone:

(713) 877-3067 Very truly yours,

[ Il b.

\\j m,,

L.D. Butterfield, Jr. Chairman Steering Committee Counterflow Steam Generator Owners Review Group LDB/ji 110lR cc:

CSG0RG Members P. McDonough, Westinghouse