ML17335A467
| ML17335A467 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/07/1999 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | Powers R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| GL-97-04, GL-97-4, TAC-M99980, TAC-M99981, NUDOCS 9901120272 | |
| Download: ML17335A467 (8) | |
Text
Mr. Robert P. Powers, S r Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 january 7,
1999
SUBJECT:
DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND2-CLOSEOUT OF GENERIC LETTER 97-04, "ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVALPUMPS," DATED OCTOBER 7, 1997 (TAC NOS. M99980 AND M99981)
Dear Mr. Powers:
On October 7, 1997, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," to all holders of operatihg licenses or construction permits. The NRC issued GL 97-04 to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps under all design-basis accident scenarios.
By letter dated January 30, 1998, Indiana Michigan Power Company (the licensee) responded to GL-97-04 for Donald C. Cook Nuclear Plant, Units 1 and 2.
The NRC has reviewed the licensee's submittal. Additionally, the NRC has reviewed the current NPSH analyses of record for the safety-related pumps due to a concern raised by the Union of Concerned Scientists in a January 12, 1998, addendum to a 10 CFR 2.206 Petition request.
During the review of the NPSH analyses and the D.C. Cook FSAR, the staff could not determine whether the current NPSH analyses are accurate.
Based on this review, the NRC staff has determined that the D.C. Cook GL 97-04 response was inconsistent with the UFSAR and may not represent the actual design basis of the plant. The licensee will have to resubmit a revised GL 97-04 response once the D.C. Cook design basis NPSH analysis is found to be correct and sufficient. The review of the revised GL 97-04 submittal and the NPSH calculations at D.C.
Cook willbe completed under new TAC numbers.
Therefore, the staff considers the initial GL 97-04 response closed for D.C. Cook, Units 1 and 2. This completes our effort on TAC Nos.
M99980 and M99981.
Sincerely, Original Signed by John F. Stang, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 cc: See next page DOCUMENT NAME: G:i...tiD.C.COO To receive a copy of this document. indicate in the box N
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Mr. Robert P. Powers, S~r Vice President Indiana Michigan Power 58bpany Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 Oanoary 7,
1999
SUBJECT:
DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2 - CLOSEOUT OF GENERIC LETTER 97-04, "ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVALPUMPS," DATED OCTOBER 7, 1997 (TAC NOS. M99980 AND M99981)
Dear Mr. Powers:
On October 7, 1997, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," to all holders of operating licenses or construction permits. The NRC issued GL 97-04 to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps under all design-basis accident scenarios.
By letter dated January 30, 1998, Indiana Michigan Power Company (the licensee) responded to GL-97-04 for Donald C. Cook Nuclear Plant, Units 1 and 2.
The NRC has reviewed the licensee's submittal. Additionally, the NRC has reviewed the current NPSH analyses of record for the safety-related pumps due to a concern raised by the Union of Concerned Scientists in a January 12, 1998, addendum to a 10 CFR 2.206 Petition request.
During the review of the NPSH analyses and the D.C. Cook FSAR, the staff could not determine whether the current NPSH analyses are accurate.
Based on this review, the NRC staff has determined that the D.C. Cook GL 97-04 response was inconsistent with the UFSAR and may not represent the actual design basis of the plant. The licensee will have to resubmit a revised GL 97-04 response once the D.C. Cook design basis NPSH analysis is found to be correct and sufficient. The review of the revised GL 97-04 submittal and the NPSH calculations at D.C.
Cook willbe completed under new TAC numbers.
Therefore, the staff considers the initial GL 97-04 response closed for D.C. Cook, Units 1 and 2. This completes our effort on TAC Nos.
M99980 and M99981.
Sincerely, Original Signed by Docket Nos. 50-315 and 50-316 cc: See next page DOCUMENT NAME: G:i...iD.C.CO To receive a copy of this document, indicate ln the born
'N' No co John F. Stang, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation g197-04.wpd Copy without attachment/enclosure E
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january 7, 1999 Mr. Robert P. Powers, Senior Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107
SUBJECT:
DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2 - CLOSEOUT OF GENERIC LETTER 97-04, "ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVALPUMPS," DATED OCTOBER 7, 1997 (TAC NOS. M99980 AND M99981)
Dear Mr. Powers:
On October 7, 1997, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," to all holders of operating licenses or construction permits. The NRC issued GL 97-04 to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps under all design-basis accident scenarios.
By letter dated January 30, 1998, Indiana Michigan Power Company (the licensee) responded to GL-97-04 for Donald C. Cook Nuclear Plant, Units 1 and 2.
The NRC has reviewed the licensee's submittal. Additionally, the NRC has reviewed the current NPSH analyses of record for the safety-related pumps due to a concern raised by the Union of Concerned Scientists in a January '12, 1998, addendum to a 10 CFR 2.206 Petition request.
During the review of the NPSH analyses and the D.C. Cook FSAR, the staff could not determine whether the current NPSH analyses are accurate.
Based on this review, the NRC staff has determined that the D.C. Cook GL 97-04 response was inconsistent with the UFSAR and may not represent the actual design basis of the plant. The licensee willhave to resubmit a revised GL 97-04 response once the D.C. Cook design basis NPSH analysis is found to be correct and sufficient. The review of the revised GL 97-04 submittal and the NPSH calculations at D.C.
Cook willbe completed under new TAC numbers.
Therefore, the staff considers the initial GL 97-04 response closed for D.C. Cook, Units 1 and 2. This completes our effort on TAC Nos.
M99980 and M99981.
incerely C"
Docket Nos. 50-315 and 50-316 cc: See next page hn F. Stang, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Robert P. Powers Indiana 4lichigan Power Company CC:
Donald C. Cook Nuclear Plant Units 1 and 2 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, Ml 48909-8130 Regulatory Affairs Director Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 John R. Sampson, Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106
Distributior.. Letter to R. Powers regarding GL 97-04 4
<Docket;Facile PUBLIC PDIII-3 Reading EGA1 OGC J. Stang (2)
ACRS G. Grant, RIII CACarpenter Dated:
3anu r
7 1999
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