IR 05000336/2007404

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IR 05000336-07-404 and 05000423-07-404; on 10/18-19/2007, Millstone Power Station, Units 2 & 3; Event Followup
ML073320545
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 11/27/2007
From: James Trapp
Plant Support Branch 1
To: Christian D
Dominion Resources
References
IR-07-404
Download: ML073320545 (5)


Text

November 27, 2007

SUBJECT:

MILLSTONE POWER STATION - NRC EVENT FOLLOWUP INSPECTION REPORT 05000336/2007404 AND 05000423/2007404

Dear Mr. Christian:

On October 19, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an event follow-up inspection at your Millstone Power Station Unit 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on October 19, 2007, with Mr.

Jordan, Plant Manager, 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 inspector 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: 11/27/07 Mr. This report documents one finding of very low safety significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiency was 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 finding had a cross-cutting aspect in the area of human performance because the expectations regarding procedural compliance were not clearly communicated (H.4(b)).

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, Office of Enforcement, United States Nuclear Regulatory Commission, Washington DC 20555-0001; and the NRC Resident Inspector at the Millstone Power Station.

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.

50-336, 50-423 License Nos. DPR-65, NPF-49 Non-Public Enclosure: Inspection Report Nos. 05000336/2007404 and 05000423/2007404 w/Attachment: Supplemental Information (CONTAINS (SGI) M