ML20198H524
| ML20198H524 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/17/1997 |
| From: | Schopfer D SARGENT & LUNDY, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 9583-100, NUDOCS 9709190022 | |
| Download: ML20198H524 (2) | |
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9-j Don K. Schopfer Vice President September 17,1997 an 2cScors Project No. 9583-100 Docket No. 50-423 Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 3 Independent Corrective Action Verification Program United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 l
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As part of Unit 3 ICAVP Programmatic Review, S&L is performing a review of 1
corrective actions for design deficiencies identified by the licensee in their Configuration Management Plan (CMP). In addition, the NRC has r%uested that we also perform a review of corrective actions for previously identified (by the original architect-engineer) l design deficiencies. These deficiencies (known as E&DCRs) have been resolved by NU some time during the plant operating life (or are currently being resolved) and are not part of NU's CMP discovery effort.
In order to determine if NU has properly dispositioned this type of discrepancy without adversely affecting the plant licensing or design basis, we propose that a sample of the E&DCRs affecting the ICAVP in-scope systems be reviewed. This sample should be fccused on those E&DCRs which were not dispositioned through the plant design change process (i.e., were not given the full level of review required of a plant modification). In addition, the sample will be selected to cover a range of engineering subjects and disciplines and be biased toward those E&DCRs of a rcore significant subject matter. We propose that 10% of the non-modification related E&DCRs for the ICAVP in-scope systems be sampled (for a total of approximately 35 E&DCRs). This sample,ize is consistent with the sample sizes being reviewed for other past changes initiated by NU which are part of cur ICAVP Tier 3 review. We believe this " smart sample" will proside us with an adequate population to verify whether NU has adequately resolved the technical issues associated with the E&DCRs while maintaining configuration control.
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United States Nuclear Regulatory Commission' September 17,1997 Attention: Document Control Desk Page 2 13ased on our prior discussions, we are proceeding with obtaining copies and performing the reviews of the E&DCRs as described above.
If you have any questions or comments on the abo,a proposed review approach, please call me at 312 269-6078.
Yours very truly, l
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D. K. Schopfer ICAVP Manager DKS:TJR:pah Copies:
E. Imbro, ICAVP Oversight T. Concannon, NEAC J. Fourgere, NU B. A. Erler File (MANgsh'37.NR0917s. doc) a
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