ML17321B009

Confirms 860114 Project Meeting W/Nrc & Exxon Nuclear Co to Discuss Status of Cycle 6 Licensing.Previously Submitted Documents Which Provide Overview of Licensing Activity to Date Re Cycle 6 Reload Listed

ML17321B009
Person / Time
Site:	Cook
Issue date:	12/26/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0916K, AEP:NRC:916K, NUDOCS 8512310303
Download: ML17321B009 (6)

Text

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ZndIana kr" OB000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH.M. P.

Indiana Zc Michigan Electric Co.

RECIP. NAME RECIPIENT AFFILIATION DENTON, H. R.

Office of Nuclear Reactor Regulation.

Director (post 851125

SUBJECT:

Confirms 860114 prospect meeting e/NRC h Exxon Nuclear Co to discuss status of Cycle 6 licensing. Previouslg submitted documents which provide overview of licensing activity to date re Cjclg 6 reload listed.

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/ND]ANA 8 NICHIGAN ELECTR/C CONPANY P.O, BOX 16631 COLUMBUS, OHIO 43216 December 26, 1985 AEP:NRC:0916K Donald C. Cook Nuclear Plant Unit No.

2 Docket No. 50-316 License No. DPR-74 UNIT 2, CYCLE 6 ANALYSES REVIEW Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Denton:

This letter confirms the project meeting which has been scheduled for January 14, 1986 between representatives of Indiana 6 Michigan Electric Company (I6'MECo), Exxon Nuclear Company (ENC), and the U.S. Nuclear Regulatory Commission (USNRC) to discuss the status of Unit 2, Cycle 6

licensing.

The following previously submitted documents provide an overview of the licensing activity to date regarding the Unit 2, Cycle 6

reload.

Exxon Re orts 1.

XN-NF-85-28, "D. C. Cook Unit 2 Cycle 6 Safety Analysis Report,"

July 1985.

2.

XN-NF-85-68(P), "Donald C. Cook Unit 2 Limiting Break LOCA/ECCS

Analyses, 10% Steam Generator Tube Plugging, and K(Z) Curve,"

September 1985.

3.

XN-NF-85-28(P), Supplement 1, "D. C. Cook, Unit 2 Cycle 6 Safety Analysis Report:

Disposition of Standard Review Plan Chapter 15 Events," October 1985.

4 ~

XN-NF-85-64(P), "Plant Transient Analysis for D. C. Cook Unit 2 with 10% Steam Generator Tube Plugging," November 1985.

IGMECo Corres ondence AEP:NRC:0916A, dated May 21, 1985, "Unit 2 Cycle 6 Safety Analyses."

2.

AEP:NRC:0916E, dated May 31, 1985, "Correction to AEPINRCI0916A."

8512310303 85122b PDR ADOCY, 0500031b PDR ADD:

PWR - A/BC's TECH SUPPORTI AD - J.

KNIGHT (Itr only),

EB (BALLARD)

EICSB (ROSA)

PSB (CANNILL)

RSB (BERLINCER)

POB (BENAROYA)

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Mr. Harold R.

Den AEP:NRC:0916K 3.

.AEP:NRC:0916B, dated September 18,

1985, "Exxon Nuclear Methodology for Pressurized Water Reactors:

An'alyses of Chapter 15 Events, XN-NF-84-73(P)."

4.

AEP:NRC:0916H, dated October 8, 1985, "D. C. Cook Unit 2 Limiting Break LOCA/ECCS Analyses, 10% Steam Generator Tube Plugging, and K(Z) Curve, XN-NF-85-68(P)."

5.

AEP:NRC:0916G, dated October 18,

1985, "D. C.

Cook Unit 2, Cycle 6, Safety Analyses Report."

6.

AEP:NRC:0916J, dated October 29, 1985, "Extension for Submittal of Transient Analysis and Technical Specifications."

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, t

cm N.

P. Al ich Vice Pre ident V'yPl 0

cc:

John E. Dolan W. G. Smith, Jr.

Bridgman R. C. Callen G. Bruchmann G. Charnoff R. Copeland, Exxon Nuclear Company - Richland, WA NRC Resident Inspector Bridgman

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