ML17326B183
| ML17326B183 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/20/1985 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8507030287 | |
| Download: ML17326B183 (8) | |
Text
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June 20, 1985 Docket No. 50-316 LICENSEE:
INDIANA AND MICHIGAN ELECTRIC COMPANY FACILITY:
DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2
SUMMARY
OF MEETING HELD ON MAY 30, 1985 WITH INDIANA AND MICHIGAN ELECTRIC COMPANY TO DISCUSS CYCLE 6 RELOAD ANALYSIS FOR UNIT 2 The staff met with the licensee and Exxon Nuclear Corporation, their fuel supplier, to discuss the reload submittals and schedule for the Cycle 6
submittals and schedule for the Cycle 6 analysis.
The list of attendees is attached as Enclosure l.
The licensee presentation included the attached viewgraphs and schedule for submission of the Cycle 6 reload analysis.
The main steam line break analysis will not be available with the reload submittal but will be submitted in July 1986 and without the boron injection tank (BIT).
The technical specifications are to be modified at that time to remove the BIT requirements.
The Exxon presentation was made from viewgraphs proprietary to Exxon.
In a subsequent letter dated June 10,
- 1985, Exxon submitted the viewgraphs to be withheld from public disclosure pursuant to 10 CFR 2.790(b).
These viewgraphs will not be included here.
The Exxon presentation was on the LOCA/ECCS analysis and on disposition of events for the transient analysis.
The status of each event and the limiting events were discussed to define those events to be addressed by the reload submittal.
/s/DLWigginton David L. Wigginton, Project Manager Operating Reactors Branch ¹1 Division of Licensing ORB¹l:DL CParrish 06lgO/85 ORB¹l:DL DWig inton/ts 06 85 8507036287 8>O+>O PDR ADQCK 050003th PDR
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Docket No. 50-316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 20, 1985 LICENSEE:
INDIANA AND MICHIGAN ELECTRIC COMPANY FACILITY:
DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2
SUMMARY
OF MEETING HELD ON MAY 30, 1985 WITH INDIANA AND MICHIGAN ELECTRIC COMPANY TO DISCUSS CYCLE 6 RELOAD ANALYSIS FOR UNIT 2 The staff met with the licensee and Exxon Nuclear Corporation, their fuel supplier, to discuss the reload submittals and schedule for the Cycle 6
submittals and schedule for the Cycle 6 analysis.
The list of attendees is attached as Enclosure l.
The licensee presentation included the attached viewgraphs and schedule for submission of the Cycle 6 reload analysis.
The main steam line break analysis will not be available with the reload submittal but will be submitted in July 1986 and without the boron injection tank (BIT).
The technical specifications are to be modified at that time to remove the BIT requirements.
The Exxon presentation was made from viewgraphs proprietary to Exxon.
In a subsequent letter dated June 10,
- 1985, Exxon submitted the viewgraphs to be withheld from public disclosure pursuant to 10 CFR 2.790(b).
These viewgraphs will not be included here.
The Exxon presentation was on the LOCA/ECCS analysis and on disposition of events for the transient analysis.
The status of each event and the limiting events were discussed to define those events to be addressed by the reload submittal.
r David L. Wig i on, Project Manager Operating Reactors Branch ¹1 Division of Licensing
Enclosure 1
FUEL RELOAD MEETING DONALD C.
COOK UNIT NO.
2 MAY 30, 1985 Or anization D. Wigginton R. Jones J.
Guttman M. Cleveland G. Owsley J.
Holm R. Heiks B. Copeland M. Kennedy F.
Adams V. Vanderburg H. Fouad G. John N. Lauben NRR-ORBgl NRR-RSB NRR-RSB AEP ENC ENC ENC ENC ENSA ENC AEPSC AEPSC AEPSC NRR-RSB
INTRODUCTION Meeting:
May 30, 1985
Participants:
NRC Staff American Electric Power Service Corp.
Exxon Nuclear'ompany, Inc.
Plant:
Donald.C.. Cook Unit 2 Sub5ects:
- 1) Cycle 6 Transient Analysis
- 2) Cycle 6 LOCA Analysis
- 3) Schedule
COOK UNIT 2, CORE MAP 205-60 Axial Offset CBD Peak F~, unpenalized Location, Peak F Limit F, unpenalized Location, Limit F Map Date Map Burnup Pro)ected EOC
-0.03 220 steps 1.32 1.525 3.2 ft.
1.319 10.2 ft.
May 20, 1985 11,454 ~
MWD Oct. 29, 1985 Limit F H
1.49 Margin, Peak F
~ llX Margin, Limit F
~ 4.7X Q
Target Burnup 17,790 MWD Availability 90X
SCHEDULE D.C.
COOK UNIT 2 REFLOOD HEAT TRANSFER CORRELATIONS AND K(Z) VERIFICATION APRIL 1985 FCTF CORRELATION SUBMITTAL AEPSC/NRC STATUS MEETING REVISED COMBINED CORRELATION TO NRC CYCLE 6 SAR.
LOCA ANALYSIS AND PARTIAL PLANT TRANSIENT ANALYSIS SUBMITTAL NAY 3, 1985 NAY 30, 1985 AUGUST 1.
1985 AUGUST 1985 COMPLETE DOCUMENTATION PACKAGE TO NRC DC COOK 1 K(Z) VERIFICATION CYCLE 6 STARTUP STEAM LINE BREAK ANALYSIS SEPTEMBER 1985 OCTOBER 1.
1985 JANUARY 1986 JULY 1986
MEETING
SUMMARY
DISTRIBUTION
/Docket oy Central file NRC PDR Local PDR ORB¹1 RDG J. Partlow (Emergency Preparedness only)
Steve Varga Project Manager OELD E. Jordan P.
McKee ACRS (10)
NS IC Gray file Plant Service List C. Parrish J. Partlow NRC Partici ants R. Jones J.
Guttman N. Lauben