ML083020120
| ML083020120 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 12/01/2008 |
| From: | Mcconnell K NRC/FSME/DWMEP/DURLD |
| To: | |
| txp3 | |
| Shared Package | |
| ML083020133 | List: |
| References | |
| Download: ML083020120 (6) | |
Text
GENERAL ELECTRIC COMPANY DOCKET NO. 50-183 THE ESADA EXPERIMENTAL VALLECITOS SUPERHEAT REACTOR AMENDMENT TO FACILITY LICENSE Amendment No. 7 License No. DR-10
- 1. The U. S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by GE-Hitachi dated June 23, 2008 (ADAMS No.
ML081780099), with supplements dated August 11, 2008 (ML082260044),
August 19, 2008 (ML082350078) and October 9, 2008 (ML082840704), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
2
- 2. Accordingly, the license is amended as indicated in the attachment to this license amendment.
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/
Keith I. McConnell, Deputy Director Decommissioning and Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Protection Programs
Attachment:
License Amendment No. 7 Facility License No. DR-10 Docket No. 50-183 Date of issuance: December 1, 2008
LICENSE AMENDMENT NO. 7 FACILITY LICENSE NO. DR-10 DOCKET NO. 50-183 Replace all pages of Appendix A, Technical Specifications EVESR, with the attached revised pages. The changed areas are identified by a marginal line.
Remove Insert Technical Specifications Page 1 Technical Specifications Page 1 Technical Specifications Page 2 Technical Specifications Page 2 Technical Specifications Page 3 Technical Specifications Page 3 Attachment
Facility License No. DR-10 Appendix A Technical Specifications EVESR A. SITE
- 1. Plant Area
- The plant area shall consist of a controlled access area defined by the reactor containment building and its ventilation system. Personnel access shall be controlled by knowledgeable plant personnel as established by written procedure.*
- 2. Principal Activities The principal activities carried on within the plant area shall be the possession of the reactor facility, the dismantling of components other than the reactor pressure vessel and activities authorized by licenses issued by appropriate regulatory authorities.
B. ADMINISTRATIVE AND PROCEDURAL REQUIREMENTS
- 1. General Activities involving access to plant area and use of any area or in-place equipment shall be conducted under the direction of a designated facility supervisor with functional responsibility and commensurate authority to maintain the facility in a safe and secure condition at all times. The facility manager shall have extensive reactor knowledge and shall utilize the resources of other licensee personnel as necessary to provide an effective safety program.
- 2. Review and Audit (a) Written procedures for control of access to the plant area, use of the plant area facilities and equipment and for periodic inspection of the facility shall be established and approved by the manager to whom the facility supervisor reports.
(b) Written procedures specified in 2.(a) above shall be reviewed by technically qualified personnel responsible to a management position other than the facility supervisor (the Nuclear Safety group) in accordance with a written charter for that function.
(c) The Nuclear Safety group shall periodically audit activities conducted in the plant area to verify that effective radiological control practices are maintained.
C. HEALTH AND SAFETY
- 1. Radiation Monitoring Radiation monitoring instruments shall be available as appropriate to prevent exposure of personnel to radiation in accordance with the standards of Part 20.
A general radiation survey shall be conducted, at least annually.
- 2. Ventilation
- A ventilation particulate monitor shall be operable whenever the containment building is ventilated.*
- 3. Surveillance and Security Access to areas of the EVESR containment shall be controlled in a manner consistent with the requirements of 10 CFR 20.1601, Control of access to high radiation areas, as applicable.
- 4. Removal of Materials and Equipment As a radiation and contamination control measure, all materials and equipment removed from radioactive materials areas shall be monitored and released in accordance with Vallecitos Nuclear Center site *procedures* and in compliance with the standards of 10 CFR Part 20.
D. RECORDS Sufficient records shall be kept to establish that the facility is being maintained within the limitations of the facility license.