ML17335A148

Responds to RAI Per 10CFR50.54 Re 2.206 Petition Filed by Union of Concerned Scientists.Info Included in Response Represents Status of Licensee Actions to Date

ML17335A148
Person / Time
Site:	Cook
Issue date:	07/31/1998
From:	Sampson J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17335A147	List: ML17335A146 ML17335A148 ML17335A149 ML17335A150 ML17335A152 ML17335A153 ML17335A154 ML17335A155 ML17335A156 ML17335A157 ML17335A185
References
2.206, AEP:NRC:1260G7, NUDOCS 9808100089
Download: ML17335A148 (4)

Text

Indiana Michigan Power Company

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500 Circle Drive Buchanan, Ml 491071395 INOIAliM MICHIGAN POEM July 31, 1998 AEP:NRC:1260G7 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-P1-17 Washington, D.C. 20555-0001 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 RESPONSE TO REQUEST FOR INFORMATION PURSUANT TO 10 CFR 50.54(f) REGARDING THE 2.206 PETITION FILED BY THE UNION OF CONCERNED SCIENTISTS On June 8, 1998, the NRC requested that we provide information, pursuant to 10 CFR 50.54(f) regarding concerns raised in the above referenced petition filed October 9, 1997, and supplemented on January 12, 1998, respectively. This letter and the attachment are being submitted in response to your request. In accordance with our letter of July 21, 1998, the due date for this information was revised to July 31, 1998.

Our response includes information that addresses questions related to: 1) the details of programs that will be used to evaluate safety-related systems; 2) expected status of safety-related systems with respect to conformance with the that will be licensing'nd design basis; 3) programmatic changes implemented at Cook Nuclear Plant before restart; and 4) responses to each of the specific issues 1 thru 5 as set forth in enclosure 1 of the NRC's letter dated June 8, 1998. The specific issues identified in the NRC's letter are based on the supplement to the 2.206 petition, dated January 12, 1998,,and include: ice condenser action plans; assessment of safety evaluations performed under the old 10 CFR 50.59 process; results of the engineering calculation assessments performed to date; the net positive suction head (NPSH) calculations for safety-related pumps, which are being submitted as proprietary information; and actions taken to address the February 6, 1997, AEP response to the NRC 50.54(f) request for information.

The information included in this response represents the status of our actions to date. We are performing additional activities associated with the Cook Nuclear Plant restart plan. Issues identified as a result of these ongoing activities will be dispositioned in accordance with our restart plan and the ongoing 0350 process. NRC permission for restart will not be requested until the restart plan is complete and reasonable assurance of restart readiness is achieved.

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U. S. Nuclear Regulatory Commission AEP:NRC:1260G7 Page 2 This letter is submitted pursuant to 10 CFR 50.54(f)

Sincerely, J. R. Sampson Site Vice President SWORN TO AND SUBSC ED BEFORE ME THIS ~AY OF 1998 No a Public My Commission Expires +/ 4KB~

/jen Attachment c J ~ A. Abramson J. L. Caldwell D. A. Lochbaum, UCS MDEQ - DW 6c RPD NRC Resident Inspector C. J ~ Paperiello

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