ML17326A067

Forwards Summary of 990616 Meeting at DC Cook Nuclear Plant in Berrien County,Mi Re Core Offload for Both Units.List of Attendees & Copy of Briefing Sheets Used by Licensee Also Encl

ML17326A067
Person / Time
Site:	Cook
Issue date:	07/26/1999
From:	Stang J NRC (Affiliation Not Assigned)
To:	Powers R INDIANA MICHIGAN POWER CO.
References
NUDOCS 9907290084
Download: ML17326A067 (8)

Text

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Mr. Robert P. Powers Senior Vice President July 26, 1999 Nuclear Generation Group Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107-1 395

SUMMARY

OF THE JUNE 16, 1999, PUBLIC MEETING TO DISCUSS THE STATUS OF CORE OFFLOAD FOR THE DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2

Dear Mr. Powers:

On June 16, 1999, the U.S. Nuclear Regulatory Commission (NRC) held a public meeting at the Donald C. Cook Nuclear Plant (D.C. Cook) in Berrien County, Michigan to discuss the core oNoad for both units Enclosure 1 is a list of attendees for the meeting, and a copy of the briefing sheets used by the licensee is provided as Enclosure 2.

The licensee presented an overview of the schedule for the Unit 2 core offload. Unit 2 is the lead unit for the offload. The proposed schedule showed that the unit would transition from Mode 5 into Mode 6 in early July 1999, with the offload completed by mid-July 1999.

Unit 1 will followas soon as the Unit 2 offload is completed.

The licensee provided a detailed summary of the analysis being performed prior to fuel movement. The analysis included control room dose from a fuel handling accident, the effects of lake water temperature, and the residual heat removal pump vibration issues.

The licensee also stated that the Updated Final Safety Analysis Report would be reviewed to assure that the design basis and licensing basis for core oNoad were up-to-date and accurate.

Finally, the licensee stated that all systems required for core offload operations would be in full compliance with the Technical Specifications.

Sincerely, Original signed by:

John F. Stang, Sr. Project Manager, Section 1

Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74

Enclosures:

1. List of Attendees

2. Briefing Sheets cc w/encls: See next page DISTRIBUTION Hard Copy (w/ encls) cDock5t=FiTe PUBLIC PD3-1 R/F J. Stang (2)

OGC ACRS J. Grobe, Rill E-Mail

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Mr. Robert P. Powers Senior Vice President Nuclear Generation Group Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107-1395 July 26, 1999

SUMMARY

OF THE JUNE 16, 1999, PUBLIC MEETING TO DISCUSS THE STATUS OF CORE OFFLOAD FOR THE DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2

Dear Mr. Powers:

On June 16, 1999, the U.S. Nuclear Regulatory Commission (NRC) held a public meeting at the Donald C. Cook Nuclear Plant (D.C. Cook) in Berrien County, Michigan to discuss the core offload for both units Enclosure 1 is a list of attendees for the meeting, and a copy of the briefing sheets used by the licensee is provided as Enclosure 2.

The licensee presented an overview of the schedule for the Unit 2 core offload. Unit 2 is the lead unit for the oNoad. The proposed schedule showed that the unit would transition from Mode 5 into Mode 6 in early July 1999, with the offload completed by mid-July 1999.

Unit 1 will follow as soon as the Unit 2 oNoad is completed.

The licensee provided a detailed summary of the analysis being performed prior to fuel

, movement. The analysis included control room dose from a fuel handling accident, the effects of lake water temperature, and the residual heat removal pump vibration issues.

The licensee also stated that the Updated Final Safety Analysis Report would be reviewed to assure that the design basis and licensing basis for core offload were up-to-date and accurate.

Finally, the licensee stated that all systems required for core offload operations would be in full compliance with the Technical Specifications.

Sincerely, Original signed by:

John F. Stang, Sr. Project Manager, Section 1

Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74

Enclosures:

1. List of Attendees

2. Briefing Sheets cc w/encls: See next page DISTRIBUTION Hard Copy (wlencls)

Docket File PUBLIC PD3-1 R/F J. Stang (2)

OGC ACRS J. Grobe, Rill E-Mail JAZ EEB COT GEG NRC Participants Rill PRR CMC1 BLB1 T. Hiltz (TGH)

RPZ RIII, DRS (2)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 July 26, 1999 Mr. Robert P. Powers Senior Vice President Nuclear Generation Group Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107-1395

SUMMARY

OF THE JUNE 16, 1999, PUBLIC MEETING TO DISCUSS THE STATUS OF CORE OFFLOAD FOR THE DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2

Dear Mr. Powers:

On June 16, 1999, the U.S. Nuclear Regulatory Commission (NRC) held a public meeting at the Donald C. Cook Nuclear Plant (D. C. Cook) in Berrien County, Michigan to discuss the core offload for both units Enclosure 1 is a list of.attendees for the meeting, and a copy of the.

briefing sheets used by the licensee is provided as Enclosure 2.

The licensee presented an overview of the schedule for the Unit 2 core offload. Unit 2 is the lead unit for the offload. The proposed schedule showed'that the unit would transition from Mode 5 into Mode 6 in early July 1999, with the offload completed by mid-July 1999.

Unit 1 will follow as soon as the Unit 2 offload is completed.

The licensee provided a detailed summary of the analysis being performed prior to fuel movement. The analysis included control room dose from a fuel handling accident, the effects of lake water temperature, and the residual heat removal pump vibration issues.

The licensee also stated that the Updated Final Safety Analysis Report would be reviewed to assure that the design basis and licensing basis for core offload were up-to-date and accurate.

Finally, the licensee stated that all systems required for core offload operations would be in full compliance with the Technical Specifications.

Sincerely, d.

ohn F. Stang, Sr.

roject Manager, Section 1

Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74

Enclosures:

1. List ofAttendees

'. Briefing Sheets cc w/encls: See next page

Robert P. Powers Indiana Michigan Power Company Donald C. Cook Nuclear Plant Units 1 and 2 CC:

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Ml 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, Ml 49106 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P.O. Box 30630 CPH Mailroom Lansing, Ml 48909-8130 Gordon Arent Director, Regulatory Affairs Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Ml 49127 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 Jeremy J. Euto, Esquire Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 A. Christopher Bakken, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI.48909 Michael W. Rencheck Vice President, Nuclear Engineering Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107

PUBLIC MEETING TO DISCUSS THE D.C. COOK CORE OFFLOAD ACTIVITIES JUNE 16, 1999 ATTENDEES Name Cecil Thomas Bruce Bartlett John Stang Claudia Craig Dave Kunsemiller Scot Greenlee George Honma George Wadkins Terry Grebel Chris Bakken Rob Antonow Don Hafer Jim Raleigh Affiliation NRC, Director, Project Directorate III, NRR NRC, Senior Resident Inspector NRC NRC, Chief, Section 1, Project Directorate III, NRR AEP, Director, Nuclear Regulatory Affairs AEP, Director, Design Engirieering AEP NRAF PG&E AEP, Site Vice President AEP AEP AEP Enclosure 1

CORE OFFLOAD BRIEFlNG June 16, 1999 Donald G. Cook Nuclear Plant

1. Introduction (Kunsemiller)

2. Core Offload Schedule Overview (Antonow)

3. Re uired Anal ses/0 erabili Evaluations (Greenlee)

Control Room Dose Fuel Handling Accident Analysis

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Use of Core/Fuel Specific Source Terms

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No Credit for Ventllatlon Filtration Lake Temperature Effects Analy818

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Control Room Temperatures

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Spent Fuel Pool Cooling Capability/Dual Core ONoad Heatup Calculations

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Residual Heat Removal Mode 6 Operability/Pump Vibration

4. Potential Licensin Im acts Bein Evaluated {Kunserniller)

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Source Range Neutron Monitoring instrumentation Requirements

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UFSAR Change

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Spent Fuel Pool Systems Design

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Safety Guide 13/Regulatory Guide 1.13 Cooling and Cleanup

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lwakeup A

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Ventllatlon

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Amendment169/152 Safety Evaluation Report

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Refueling Practices Survey

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Resolution ofSpent Fuel Pool Safety issues and AEP Response

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Fuel Handling Operations Requirements

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LER 99%06, impact on Fuel Racks from Dropped LOads e

- Wlaintenance of23 Feet ofWater Over Dropped Fuel

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lIovement of lnultlple Fuel Assemblies

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Spent Fuel Pool Ventilation Operability

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LER 9B<29, Radiation Monitoring and Ventilation System Response Time Enclosure 2

AFST. JFCÃ. Tta TAFLl4.SOCCERJ IICIVCMTE'MASS ItI'NllZ OFFl OAD SCHEDUlE.

U>>ll >> LTVIL I OFFLOAD scleIOULT vtstaIc A xaaLO ccsss accaa>>ti>>ILIIY >>Asco max dULY U2 OTHER PR

-DEFUEL WORK

'IF 50 3OJUN99 ENTER MODE 58 DESCENDING IF ts>>

I 30JUN99 6JUL99 00 TO 6 I

30JUN99 9JUL99

)P RX OISA SEMBLY 10 12 5J 4JUL99

)GURGE STRENGTH EVAL FOR FULL COAE OFFLOAD F ls 5JUL99 (AKE TEMP VS SFP COOLING ANALYSIS UL99 Q

6JUL99 VERIFY MODE 6 PAEAEOUISITES COMPLETE BJUL99 U2 ENTER RODE 6 IF 11 BJUL99 g

BJUL99 START FILL U.2 REFUELING CAVITY IF 11 BJUL99 ~

$ 1JUL99 2ND XFER U.1 RITST TO U.2 RMST IF II 11JUL99 g 11JUL99 COMPLETE FILL U.2 AEFUELING CAVITY

-11 11JUL99 BEGIN CORE OFFLOAD 11JUL99 13JUL99 UNNN2 COAE OFFLOAD 13JUL99 P2 COAE OFFLOAD COMPLETE DATA OATK 15JI>>f90 OUTADE SCKKOULF. OKVELOPHENT IIATEIITAL

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