ML17319B506

Clarifies Submittal Schedule of Analyses Re Completion of All American Electric Power Svc Corp & Exxon Nuclear Co Info in Support of Cycle 4 Operation

ML17319B506
Person / Time
Site:	Cook
Issue date:	09/08/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0637D, AEP:NRC:637D, NUDOCS 8209130053
Download: ML17319B506 (6)

Text

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AOCBSSION NBR:8209130053, DOC.DATE: 82/09/08 NOTARIZED:

NO DOCKET FACIL 50 316 Donald C ~

Cook Nuclear Power Plantr Uni,t 2r Indiana 8

05000316 AUTH'AME AUTHOR AFFILIATION HUNTERrR ~

'ST Indiana 8 Michigan Electric Co,

'RBC IP ~ NAME RECIPIENT AFFILIATION DENTONrH ~ Rs Office of Nuclear Reactor Regulationr Director

SUBJECT:

Clarifies Asubmittal schedule of analyses ire completion of all American Electric Power 'Svc Corp 8

EXXON Nuclear Co info in suppor t of Cycle 4 operation, DISTRIBUTION CODE:

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INDIANA 5 MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 September 8,

1982 AEP:NRC:0637D Donald C. Cook Nuclear Plant Unit No.

2 Docket No. 50-316 License No. DPR-74 UNIT 2 CYCLE 4 EXXON NUCLEAR COMPANY (ENC)

SUBMITTAL SCHEDULING Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

On August 5, 1982, representatives of American Electric Power Service Corporation (AEPSC) and Exxon Nuclear Company (ENC) met with members of the NRC Staff to discuss the D. C.

Cook Unit 2 Cycle 4 reload application.

The meeting summary memorandum was issued on August ll, 1982 and established the target date of September 30, 1982 for completion of all AEP and ENC document submittals in support of Cycle 4 operation.

With the exception of certain ENC analyses which are currently in progress, we concur with this target date.

The purpose of this letter is to clarify the submittal schedule for these analyses.

As a result of an issue raised by another fuel supplier in

1981, an additional LOCA analysis is being performed with ENC's EXEM/PWR evaluation model to calculate peak cladding temperature with both ECCS low pressure injection pumps (RHR pumps) in operation.

The requirement to address this issue was expressed by the NRC at the August 5 meeting but no date for submittal was established.

We will submit the results of this additional analysis to the NRC Staff by November 1,

1982.

A requirement to re-evaluate the current radiological assessment of Unit 2 operation if fuel exposure and/or power are increased.was also identified at the August 5 meeting.

The additional scope of the required re-evaluation is currently under review.

No submittal date was suggested at the meeting.

However, analyses to support Cycle 4 operation involving this issue are currently expected to be submitted by October ll, 1982, 8209130053 820908 PDR ADOCK 0500031 6 P

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Mr. Harold R. Dento

NRC:0637D ENC agreed to use D. C. Cook Unit 2 for the example calculations using their automated cross-flow model at the August 5

meeting.

The additional work scope associated with this effort was identified at the meeting as requiring additional time.

The limiting transients re-evaluated with the automated cross-flow model and documentation of the automated cross-flow model will be submitted by October 8, 1982.

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,

/os S. Hunter Vice President cc:

John E. Dolan Columbus M. P. Alexich R.

W. Jurgensen W. G. Smith, Jr.

Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant - Bridgman

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