ML17326A055
| ML17326A055 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/15/1999 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | Powers R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| NUDOCS 9907220194 | |
| Download: ML17326A055 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 July 15, 1999 Mr. Robert P. Powers Senior Vice President Nuclear Generation Group Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107-1395
SUBJECT:
SUMMARY
OF THE MARCH 24, 1999, TECHNICALMEETING REGARDING TECHNICALISSUES RELATED TO RESTART OF THE DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2
Dear Mr. Powers:
On March 24, 1999, staff of the Donald C. Cook Nuclear Plant, Units 1 and 2 (D. C. Cook),
conducted a technical meeting to brief U. S. Nuclear Regulatory Commission (NRC) staff on issues associated with the restart of D. C. Cook. A copy of the slides used by the licensee is provided as Enclosure 1.'A list of attendees is provided as Enclosure 2.
Mr. Dave Kunsemiller, Director of Regulatory Affairs, discussed problems associated with the
'icensee's 10 CFR 50.59 Safety Evaluation Program.
The licensing department willhave clear ownership of the safety evaluation program.
New 10 CFR 50.59 procedures were written and approved on February 24, 1999. The Nuclear Safety Assessment Team (NSAT), an in-line engineering review group comprised of experienced industry personnel, is responsible for review of safety evaluations and safety significant screens.
As a result of the licensee's initiatives in this area, training of personnel is more effective and safety significant issues are being identified.
Next, Mr. Mark Marano, Director of Business Services, discussed changes to the licensee's corrective action program (CAP) to address inadequacies with the existing program. The licensee's goals with respect to the CAP are to implement a program that readily identifies problems, aggressively corrects problems, and effectively uses trending tools to ensure that significant problems are not repetitive. Progress has been made in providing oversight of the CAP and in lowering the threshold for reporting. As a result, the number of condition reports generated monthly has generally been increasing.
The electronic tool, eCAP, willbe used to Pg track restart mode restraints at the corrective action level. Performance indicators willbe used to assess the program's performance.
Mr. Paul Schoepf, technical lead on ice condenser issues, discussed the status of D. C. Cook' progress on ice condenser maintenance.
Failures with inlet door seals are being addressed to ensure that the temperature in the ice condenser remains within design limits to prevent sublimation.
Missing ice basket coupling screws were attributed to a failure to install screws on baskets adjacent to crane and containment walls. A sampling of ice baskets is being inspected to assess the extent of the problem. A failure analysis is currently being performed to determine the ability of the screws to carry the required load and sampling inspections of the ice baskets are being performed to determine the number of screws with missing heads.
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R.P. Powers July 15, 1999 Finally, Mr. Jeff Bass discussed the status of containment sump issues.
Post-accident containment water inventory must be sufficient to meet net positive suction head (NPSH) requirements and prevent vortex formation in the containment sump. A new limiting case was identified that could prevent sufficient water inventory in the sump based on a revised ice condenser lower inlet door model. Two plant modifications have been identified to ensure that all water would be directed to the, active sump:
- 1) plugging the spray nozzles that spray into the annulus region, and 2) rerouting the floor drains that transfer water from upper containment directly to the active sump.
The licensee willcontinue with design work on the containment sump and meet with NRC officials to discuss submittals necessary for restart.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures willbe placed in the NRC's Public Document Room.
Sincerely, Original signed by:
John F. Stang, Senior Project Manager, Section 1
Project Directorate III Division of Licensing Project Manag3ment Office of Nuclear Reactor Regulation Docket Nos. 50-315, 50-316 License Nos. DPR-58, DPR-74
Enclosures:
As stated cc: See next page
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R.P. Powers Finally, Mr. Jeff Bass discussed the status of containment sump issues.
Post-accident containment water inventory must be sufficient to meet net positive suction head (NPSH) requirements and prevent vortex formation in the containment sump. A new limiting case was identified that could prevent sufficient water inventory in the sump based on a revised ice condenser lower inlet door model. Two plant modifications are being considered to ensure that all water would be directed to the active sump:
- 1) plugging the spray nozzles that spray into the annulus region, and 2) rerouting the floor drains that transfer'water from upper containment directly to the active sump.
The licensee willcontinue with design work on the containment sump and meet with NRC officials to discuss submittals necessary for restart.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.
Sincerely, I
Ch John F. Stang, Senior Project Manager, Section 1
Project Directorate Ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315, 50-316 License Nos. DPR-58, DPR-74
Enclosures:
As stated cc: See next page
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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 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Ml 49127 Jeremy J.
Euto, Esquire Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 Mayor, City of Bridgman P.O. Box 366 Bridgman, Ml 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Ml 48909 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, MI 48909-8130 Gordon Arent Director, Regulatory Affairs Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 A. Christopher Bakken, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 Michael W. Rencheck Vice President, Nuclear Engineering Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107
7/15/99
SUMMARY
OF 3/24/99 RESTART PANEL MEETING ON.. COOK RESTART ACTIVITIES DISTRIBUTION Hard Copy (w/encls)
Docket File PUBLIC PD31 Reading OGC C. Sochor J. Stang ACRS J. Caldwell E-Mail (w/Encl 1)
S. Collins (SJC1)
R. Zimmerman (RPZ)
J. Zwolinski (JAZ)
S. Black (SCB)
J. Stang (JFS2)
T. Hiltz (TGH)
C. Craig (CMC1)
E. Barnhill (EEB)
G. Dick (GFD)
C. Thomas (COT)
G. Grant (GEG)
M. Holmberg B. Bartlett J. Grobe A. Vegel J. Jacobson J. Maynen B. Fuller