IR 05000272/2008404
| ML083100576 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 11/04/2008 |
| From: | James Trapp Plant Support Branch 1 |
| To: | Joyce T Public Service Enterprise Group |
| References | |
| IR-08-404 | |
| Download: ML083100576 (5) | |
Text
November 4, 2008
SUBJECT:
SALEM AND HOPE CREEK GENERATING STATIONS - NRC PHYSICAL SECURITY PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT NOS. 0500272/2008404, 05000311/2008404 AND 05000354/2008404
Dear Mr. Joyce:
On September 26, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed a security Problem Identification and Resolution inspection at your Salem and Hope Creek Generating Stations. The inspection covered one or more of the key attributes of the security cornerstone of the NRC=s Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on September 26, 2008, with Mr. George Barnes, Mr. Robert Braun, and other members of your staff.
The inspection examined activities conducted under your licenses as they relate to security and compliance with the Commission=s rules and regulations and with the conditions of your licenses. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
This report documents two NRC-identified findings and two self-revealing findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspector left the site. The findings have cross-cutting aspects in the area of Human Performance H2(a), H2(c), and H4(a). Additionally, a licensee-identified violation which was determined to be of very low security significance is listed in this report. However, because of the very low security significance and because they are entered into your corrective action program, the NRC is treating these violations as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator Region I; When separated from its Enclosure, this document is DECONTROLLED. the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at the Salem and Hope Creek Generating Stations.
In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter 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). However, because of the security-related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter=s enclosure will not be available for public inspection.
In accordance with 10 CFR 2.390(b) (1) (ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC=s document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response ASecurity-Related Information - Withhold Under 10 CFR 2.390@ and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Sincerely,
/RA/
James M. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety
Docket Nos.
50-272, 50-311, 50-354 License Nos. DPR-70, DPR-75, NPF-57
Enclosure:
Inspection Report Nos. 0500272/2008404, 05000311/2008404, and 05000354/2008404 w/Attachment: Supplemental Information (OUO-SRI)