IR 05000027/2002009
| ML021540294 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Washington State University  |
| Issue date: | 05/31/2002 |
| From: | Lanning W Division of Reactor Safety I |
| To: | Skolds J Exelon Generation Co |
| References | |
| IR-02-009 | |
| Download: ML021540294 (36) | |
Text
May 31, 2002
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION - NRC INSPECTION REPORT 50-277/02-09, 50-278/02-09
Dear Mr. Skolds:
On April 23, 2002, the NRC completed an inspection regarding your application for renewal of the operating licenses for the Peach Bottom Atomic Power Station, Units 2 and 3. The results of the inspection were discussed with members of your staff on April 24, 2002, at an exit meeting held at your office in Kennett Square, Pennsylvania. The enclosed inspection report presents the results of that inspection.
The inspection was conducted in accordance with NRC Manual Chapter 2516, Policy and Guidance for the License Renewal Inspection Program, using NRC Inspection Procedure 71002, License Renewal Inspections. The inspection was the first of two scheduled NRC team inspections activities that support your application for a renewed license for the PBAPS facilities. The inspection consisted of a selected examination of procedures and representative records, and interviews with personnel regarding the scoping and screening of systems, structures and components, in accordance with 10 CFR 54, in the license renewal application.
The scoping and screening portion of your license renewal activities were being implemented as described in your license renewal application. The documentation supporting your application is in an auditable and retrievable form. The team identified three items that require further actions by you to ensure correctness and completeness of the license renewal scoping and screening effort: (1) scoping of nonsafety-related components of the residual heat removal, core spray and reactor building closed cooling water systems to conform with the criterion of 10 CFR 54.4(a)(2); (2) reclassification of certain fuse clips identified as active components in your application; and (3) identification of offsite station blackout equipment included in the application. Except for these open items, your scoping and screening processes were successful in identifying those structures and components required to be considered for aging management.
Mr. John In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
If you have any questions, please contact David Lew of my staff at (610) 337-5120.
Sincerely,
/RA/
Wayne D. Lanning, Director Division of Reactor Safety Docket Nos:
50-277, 50-278 License Nos: DPR-44, DPR-56 Enclosure:
Inspection Report Nos. 50-277/02-09 and 50-278/02-09 Attachments: (1) Supplemental Information (2) Structures/Systems Selected for Inspection
Mr. John