ML17334A957

Responds to Request for Further Info Re Generic Ltr 83-28, Items 4.2.3 & 4.2.4.Replacement of Shunt Trip Attachment Will Be Implemented in Appropriate Plant Procedures

ML17334A957
Person / Time
Site:	Cook
Issue date:	04/22/1986
From:	Alexich, Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0838Q, AEP:NRC:8380, AEP:NRC:838Q, GL-83-28, NUDOCS 8604250050
Download: ML17334A957 (4)

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REGULATOR'II' XNFGRHATI GN-D I BTR I BUT I GNHYBTEH-<.R-IDB)

ACCESSIONS NBR: Bb04250050 DOC. DATE: Bb/04/22 NOTARIZED: NO FACXL:50-315 Donald C. Cook Nuclear Power Planti Unit I. Indiana 5 50-3kb Donald C. Cook Nuclear Power Planti Unit 2i Indiana AUTH. NAME AUTHOR AFFILIATION ALEXICH i i Xn d an a Zc Ni c h g an El e c tr i c Co.

RECIP. NANE RECIPIENT AFFILIATION DENTONp H. R. Office of Nuclear Reactor Regulationi Director (post 851125

SUBJECT:

Responds to request For further info re Qeheric Ltr 83 28>

Items 4. 2. 3 5 4. 2. 4. Replacement of shunt trip attachment will be implemented in appropriate plant procedures.

DISTRIBUTION CODE: A055D COP IES RECEIVED: LTR ENCL SI ZE:

TITLE: OR/Licensing Submittal: Salem *TMS Events QL-83-28 NOTES RECXPIENT COPIES REC IP I ENT COP XES ID CODE/NAl'1E LTTR ENCL ID CODE/MANE LTTR ENCL PWR-A ADTS PWR-A EB PWR-A EICSB PWR-A FOB PWR-A PD4 PD Oi WIdQINQTON> D PWR-A PBB PWR-A RBB INTERNAL: ADN/LFNB ELD/HDS3 IE/DI IE/DGAVT NRR BWR ADTB NRR LASHER' NRR PWR-A ADTS NRR PWR-B ADTS

/RBIB NRR/TANB REQ I 04 RQN3 EXTERNAL: 24X i LPDR 03 NRC PDR 02 I NBIC 05 TOTAL NUNBER OF COPIES REQUIRED: LTTR 28 ENCL

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INDIANA g iNICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 April 22, 1986 AEP:NRC:0838Q Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 ATWS ITEMS 4.2.3 AND 4.2.4 CLARIFICATION Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This letter is in response to a request from your staff for further information with regard to Generic Letter 83-28, Items 4.2.3 and 4.2.4. These items concern the Reactor Trip Breakers (RTBs) and their attachments.

Specifically, these items require life-cycle testing of the RTBs and their attachments and periodic replacement of the breakers, or their components and attachments, consistent with demonstrated life cycles.

Life-cycle testing of the shunt trip attachment (STA) and the undervoltage trip attachment (UVTA) has been conducted by Westinghouse Electric Corporation, the Donald C. Cook Plant breaker manufacturer, for the Westinghouse Owners Group. This testing specified an identical qualified life of 1250 operations for both the STA and the UVTA. Currently, plant procedures require replacement of the UVTAs after 1250 operations. Although not contained in plant procedures at present, replacement of the STA, based on the life-cycle testing performed by Westinghouse, will be implemented in the appropriate plant procedures. There has been no life-cycle testing performed on the RTB itself. There is no Westinghouse-recommended periodic replacement interval.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly ours, 8504250050 850+88 PDR *DOCK 050003l5 PDR l P M. P. Ale zchQ$ L Vice President i])w MPA/rjn cc: John E. Dolan W. G. Smith, Jr. - Bridgman o<>

R. C. Callen l

G. Bruchmann )

G. Charnoff NRC Resident Inspector - Bridgman