IR 05000247/2007402
| ML072960084 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/23/2007 |
| From: | James Trapp Plant Support Branch 1 |
| To: | Dacimo F Entergy Nuclear Operations |
| References | |
| FOIA/PA-2016-0148 IR-07-402 | |
| Download: ML072960084 (6) | |
Text
October 23, 2007
SUBJECT:
INDIAN POINT ENERGY CENTER - NRC PHYSICAL SECURITY BASELINE INSPECTION REPORT NOS. 05000247/2007402 AND 05000286/2007402
Dear Mr. Dacimo:
On September 14, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Indian Point Energy Center. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on September 14, 2007, with Pat Conroy, Director of Nuclear Safety Assurance and other members of your staff.
The inspection examined activities conducted under your licenses as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Warning: Violation of section 147 of the Atomic Energy Act, Safeguards Information is subject to civil and criminal penalties DETERMINATION MADE BY:
NAME/TITLE: James M. Trapp, Chief ORGANIZATION: RI/DRS/PSB1 BASIS - DG-SG-1 (300) Physical Protection Program SIGNATURE___/RA/______ DATE: 10/23/07 Mr. This report documents one finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiency was promptly corrected and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the site. The finding had a cross-cutting aspect in the in the area of human performance because a security officer was not fit for duty (was inattentive). However, because of the very low safety significance and because it is entered into your corrective action program, the NRC is treating this violation as a non-cited violation (NCV) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest this non-cited violation, 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; the Director of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Indian Point Energy Center (IPEC).
In accordance with 10 CFR 2.390 of the NRCs Rules 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 NRCs 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 concerns contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters 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 NRCs 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 Security-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.
50-247, 50-286 License Nos. DPR-26, DPR-64 Enclosure:
NRC Inspection Report Nos. 05000247/2007402 and 05000286/2007402 w/Attachment: Supplemental Information (CONTAINS (SGI) M