IR 05000272/2010006
| ML102871030 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 10/14/2010 |
| From: | Conte R NRC Region 1 |
| To: | Joyce T Public Service Enterprise Group |
| Shared Package | |
| ML102871064 | List: |
| References | |
| IR-10-006 | |
| Download: ML102871030 (6) | |
Text
October 1, 2010
SUBJECT:
SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2, AND HOPE CREEK GENERATING STATION - NRC LICENSE RENEWAL INSPECTION REPORT NOS. 05000272/2010006,05000311/2010006,05000354/2010006 ERRATA
Dear Mr. Joyce:
On October 1,2010, the NRC issued Inspection Report 0500027212010010, 05000311/2010010,05000354/2010010, documenting the results of our inspection of your application for a renewed license. An error occurred when recording the report number of the inspection.
The inspection report was issued indicating the report number was 0500027212010010, 05000311/2010010,05000354/2010010, in a sequence of report numbers for the Salem and Hope Creek facilities when, in fact, the report number is 05000272/2010006, 05000311/2010006,05000354/2010006. A revised report cover and summary page is enclosed.
In accordance with 10 CFR 2.390 of the NRC's "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 NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading rm/adams.html (the Public Electronic Reading Room).
Sincerely, IRA!
Richard J. Conte, Chief Engineering Branch 1 Division of Reactor Safety S.UNSI Review Complete:....:Mi!!.:C~Mr!!.!/RJ~C____ (Reviewer's Initials)
DOCUMENT NAME: Y:\\Division\\DRS\\Engineering Branch 1\\- MModes\\Errata Letter Correcting Salem Hope Creek License Renewallnpsection Report Number.doc ADAMS ACC #ML102871030 After declaring this document "An Official Agency Record" it will be released to the Public.
To receive a copy of this document, indicate In the box: 'C n
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nE COpy with attac ment/enciosure "N" =No copy
=Copy without attachmen enclosure
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NAME MModesfMCM ABurrittfALB RContefRJC DATE 10/14/10 10114/10 10/14/10 I
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T.Joyce
Distribution w/encl: (VIA E-MAIL)
W. Dean, RA (R10RAMAIL Resource)
M. Dapas, DRA (R10RAMAIL Resource)
J. Clifford, DRP (R1DRPMAIL Resource)
D. Collins, DRP (R1DRPMAIL Resource)
D. Roberts, DRS (R1DRSMaii Resource)
P. Wilson, DRS (R1DRSMaii Resource)
D. Lew, DRP A. Burritt, DRP L. Cline, DRP A. Turilin, DRP C. Douglas, DRP D. Schroeder, DRP, SRI-Salem P. McKenna, DRP, RI-Salem B. Welling, DRP, SRI-Hope Creek A. Patel, DRP, RI-Hope Creek L. Trocine, RI OEDO J. Andersen, RI, OEDO M. Benson, ACRS D. Bearde, DRS RidsNrrPMSalem Resource RidsNrrPMHopeCreek Resource RidsNrrDorlLpl1-2 Resource ROPreportsResource@nrc.gov
Docket No:
License No:
Report No:
Licensee:
Facility:
Location:
Dates:
Inspectors:
Approved By:
U. S. NUCLEAR REGULATORY COMMISSION
REGION I
50-272, 50-311, 50-354 DPR-70, DPR-75, NPF-57 05000272/2010006,05000311/2010006,05000354/2010006 PSEG Nuclear LLC Salem Nuclear Generating Station Units 1 and 2, and Hope Creek Generating Station Hancock's Bridge, NJ June 7 -10,21 - 24, August 9 -12,2010 M. Modes, Team Leader, Division of Reactor Safety (DRS)
G. Meyer, Sr. Reactor Inspector, DRS S. Chaudhary, Reactor Inspector, DRS T. O'Hara, Reactor Inspector, DRS J. Tifft, Reactor Inspector, DRS Richard J. Conte, Chief Engineering Branch 1 Division of Reactor Safety
- SUMMARY OF FINDINGS IR 05000272,05000311,05000354/2010006; June 7 -10,21 - 24, August 9 -12,26,2010; Salem Nuclear Generating Station, Units 1 and 2. and Hope Creek Generating Station; Inspection of the Scoping of Non-Safety Systems and the Proposed Aging Management Programs for the PSEG Nuclear LLC Application for Renewed License for Salem Nuclear Generating Station Units 1 and 2, Hope Creek Generating Station.
This inspection of license renewal activities was performed by five regional office engineering inspectors. The inspection was conducted in accordance with NRC Manual Chapter 2516 and NRC Inspection Procedure 71002. This inspection did not identify any "findings" as defined in NRC Manual Chapter 0612. The inspection team concluded screening and scoping of non safety related systems, structures, and components was implemented as required in 10 CFR 54.4{a){2), and the aging management portions of the license renewal activities were conducted as described in the License Renewal Application. The inspection results supported a conclusion that the proposed activities will reasonably manage the effects of aging in the systems, structures, and components identified in the application for a renewed license. The inspection concluded the documentation supporting the application was in an auditable and retrievable form.
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