ML17320A685

Requests Extension Until 840330 to Respond to Generic Ltr 83-28, Required Action Based on Generic Implications of Salem ATWS Events. List of Extended Action Items Encl

ML17320A685
Person / Time
Site:	Cook
Issue date:	09/09/1983
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
AEP:NRC:0838, AEP:NRC:838, GL-83-28, NUDOCS 8309150254
Download: ML17320A685 (8)

Text

DOCKET 05000315 05000316 DISTRIBUTION CODE:

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OR Submittal:

General Distribution NOTES:

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ACCESSION NBR:8309150254 DOC.DATE: 83/09/09 NOTARIZED'O FACIL:SO 315 Donald C.

Cook Nuc I ear Power Pl anti Unit ir Indiana tt 50 316 Donald C ~

Cook Nuclear P'ower Pl antg Unit 2i Indiana tt AUTH NAtlE AUTHOR AFFILIATION ALEXICH.M.P.

Indiana 8 Michigan Electric Co.

REC IP. NAtiE REC IP IENT AFFILIATION EISENHUT.O.G.

Division of Licensing

SUBJECT:

Reauests extension until.840330 to respond to Generic Ltr 83-28'Reguired Action Based on Generic. Implications of Salem ATNS Events'

" List of extended action items encl'XTERNALS ACRS NRC PDR NTIS 09 02 RECIPIENT ID CODE/NAME NRR ORBi BC 01 INTERNAL: ELD/HDS3 NRR/OL DIR TB REG F

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INDIANA8 N ICHIG AN ELECTRIC COiMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 September 9,

1983 AEP:NRC:0838 Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos. 50-315 and 50-316 License Nos.

DPR-58 and DPR-74 GENERIC LETTER 83-28 REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS Mr. Darrell G. Eisenhut, Director Division of Licensing, NRR U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Eisenhut:

We have carefully reviewed the contents of your Generic Letter 83-28 dated July 8, 1983.

For many of the action items, we will be responding within the 120 days specified in your letter.

There are several action items, however/

where the scope of information is wide and the response requires us to integrate the output from the Westinghouse Owner's Group, the Institute of Nuclear Power Operations and our ma)or suppliers.

For these

items, for which we estimate a 2 man-year effort, we request that you grant us an extension to March 30, 1984 to respond.

The Attachment to this letter lists these extended action items.

At the time of our March 30, 1984 submittal we will provide you with a status report and an implementation schedule for each item.

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 yours, 8309150254 830909 PDR ADOCK 05000315 P

PDR

. P. AlexichI Vice President MPA/cam Attachment cc:

John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector Bridgman

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Attachment to Letter AEP:NRC:0838 of Se tember 9,'983 The following actions items listed in Generic Letter 83-28 dated July 8, 1983 are extensive and it is requested that we be given until March 30, 1984 to prepare a response:

2.1 Equi ment Classification and Vendor Interface (Reactor Tri S stem Components)

The vendor interface program is to be part of the overall effort in action item 2.2.

We expect to submit our statement on equipment classification of trip components by November 5, 1983.

2.2 Equipment Classification and Vendor Interface (Programs for all Safet -Related Components)

This activity is very large in scope.

It requires that all our vendors agree to a formal and auditable document control system for the life of the plant. It further necessitates a matching internal document control structure from design through operations and maintenance.

This is an industry-wide undertaking.

The Institute of Nuclear Power Operations has formed a Nuclear Utility Task Action Committee to help formulate an acceptable vendor interface program.

A report containing their recommendations is scheduled for February 1984.

3.2 Post-Maintenance Testing (All Other Safety-Related Com onents)

This requires an extensive review of all vendor recommendations and verification of our plant procedures for testing and maintenance.

4.1 Reactor Trip S stem Reliabilit (Vendor-Related Modifications)

We will respond on the Westinghouse supplied equipment by November 5, 1983.

For other vendors, we need from them a verified comprehensive list of all modifications which can be checked off.

For the other vendors we need until March 30, 1984 to respond.

4.2 Reactor Trip S stem Reliability (Automatic Actuation of Shunt Tri Attachments)

We intend to incorporate the Westinghouse recommended design for automatic actuation of the shunt trip attachment.

So far, the Westinghouse Owner's Group has received a generic design package.

Detailed design, life cycle testing and evaluation will take about nine months.

We need until March 30, 1984 to be able to forecast the implementation of this feature.

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4.5.3 Reactor Trip Reliabilit (System Functional Testing)

Test Intervals This will be responded to as part of the activities of the Westinghouse Owner's Group which has already taken the following initiatives:

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Life Cycle testing of the undervoltage trip attachment for the reactor trip breakers is nearing completion.

Authorization is being given to begin life cycle test of the shunt, trip attachments.

Every effort is being made to qualify the shunt trip attachment to appropriate standards and criteria.

A generic conceptual design package, for incorporation of an automatic shunt trip feature into Westinghouse reactor protection systems, was prepared and comments received via'our letter to Mr. J.

Sheppard of the Westinghouse Owner's Group dated August 10, 1983.

The Westinghouse Owner's Group program is expected to last about nine months.

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