IR 05000327/2013404
| ML13077A225 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/18/2013 |
| From: | Reis T Division of Reactor Safety I |
| To: | James Shea Tennessee Valley Authority |
| References | |
| EA-13-044 IR-13-404 | |
| Download: ML13077A225 (5) | |
Text
UNITED STATES rch 18, 2013
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000327/2013404 AND 05000328/2013404, PRELIMINARYGREATER THAN GREEN FINDING
Dear Mr. Shea:
On March 8, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection for your Sequoyah Nuclear Plant. 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 initially discussed at Sequoyah on January 17, 2013, with Mr. T. B. Marshall and other members of your staff. A final exit meeting was conducted by telephone on March 10, 2013, with Mr. J. Carlin and other members of your staff.
This inspection examined activities conducted under your license as they relate to security and compliance with the Commission=s rules and regulations, and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
The attached report documents a finding that has preliminarily been determined to be Greater than Green (i.e., a finding of greater than very low safety significance) that may result in the need for further evaluation to determine significance, and therefore the need for additional NRC action. The finding involved vehicle access control and is described in the enclosed inspection report. This finding was assessed based on the best available information, using the Physical Protection Significance Determination Process (PPSDP). The finding was immediately corrected and placed in the licensees Corrective Action Program while long term corrective action is being developed. The finding is also an apparent violation of NRC requirements and is being considered for escalated enforcement action in accordance with the Enforcement Policy, which can be found on the NRCs Web site at http://www.nrc.gov/reading-rm/doc-collections/enforcement. The finding also had a cross-cutting aspect in the area of Human Performance under H.1 (a), in that, the licensee failed to use a systematic process when faced with uncertain or unexpected plant conditions to ensure security is maintained. If you disagree with the cross-cutting aspect assigned to the finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement to the Regional Administrator, Region II, and the NRC Resident Inspector at the Sequoyah Nuclear Plant.
In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete our evaluation using the best available information and issue our final determination of safety significance within 90 days of the date of this letter. The significance determination process encourages an open dialogue between the NRC staff and the licensee; however, the dialogue should not impact the timeliness of the staffs final determination.
Before we make our final significance determination, we are providing you with an opportunity to: (1) attend a Regulatory Conference where you can present to the NRC your perspective on the facts and assumptions the NRC used to arrive at the finding and assess its significance, or (2) submit your position of the finding to the NRC in writing. If you request a Regulatory Conference, it should be held within 30 days of the receipt of this letter and we encourage you to submit supporting documentation at least one week prior to the conference in an effort to make the conference more efficient and effective. If a Regulatory Conference is held, it will not be open for public observation due to the security-related nature of the issues to be discussed.
If you decide to submit only a written response, such submittal should be sent to the NRC within 30 days of your receipt of this letter. If you decline to request a Regulatory Conference or submit a written response, you relinquish your right to appeal the final Significance Determination Process determination, in that by not doing either, you fail to meet the appeal requirements stated in the Prerequisite and Limitation sections of Attachment 2 of IMC 0609.
Please contact Mr. Binoy Desai, Chief, Plant Support Branch 2, Division of Reactor Safety, at (404) 997-4519 or in writing within 10 days from the issue date of this letter, to notify the NRC of your intentions. If we have not heard from you within 10 business days, we will continue with our significance determination and enforcement decision. The final resolution of this matter will be conveyed in separate correspondence.
Because the NRC has not made a final determination in this matter, a Notice of Violation will not be issued for the inspection finding at this time. In addition, please be advised that the number and characterization of the apparent violation described in the enclosed inspection report may change as a result of further NRC review.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. However, because of the security related information 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.
Because this issue involves security-related information, your response, should you choose to respond in writing, will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. 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 Proprietary Information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Terrence Reis, Director Division of Reactor Safety Docket No.: 50-327, 50-328 License No.: DPR-77, DPR-79 Enclosure:
Inspection Report 05000327/2013404 and 05000328/2013404 w/Attachment: Supp Info (OUO)
cc: (See page 4) ML13077A225 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII: DRS RII: DRS RII: DRP RII: EICS RII: DRS SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/
NAME A. RICHARDSON B. DESAI S. SHAEFFER C. Evans T. REIS DATE 3/12/2013 3/13/2013 3/13/2013 3/13/2013 3/18/2013 4/ /2013 4/ /2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO cc:
J. T. Carlin Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000, OPS 4A-SQN Soddy-Daisy, TN 37384-2000 J. W. Proffitt Manager, Site Licensing Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000, OPS 4C-SQN Soddy Daisy, TN 37384-2000 Mark Findlay General Manager, Security Operations Tennessee Valley Authority 1101 Market Street, EB 10B-C Chattanooga, TN 37402-2801 Frank A. Little Manager Site Security Operations Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000