ML20086G988
| ML20086G988 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/06/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086G990 | List: |
| References | |
| NUDOCS 9507170367 | |
| Download: ML20086G988 (5) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION V0GTLE ELECTRIC GENERATING PLANT. UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425 ENVIRONMENTAL ASSESSMENT AND l
FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Connission (the Commission) is considering issuance of an exemption from certain requirements of its regulations to Facility Operatino License Nos. NPF-68 and NPF-81. These licenses are issued to Georgia Power Company, et al. (GPC, or the licensee) for operation of the Vogtle Electric Generating Plant, Units 1 and 2, located in Burke County, Georgia.
ENVIRONMENTAL ASSESSMENT 3
Identification of Proposed Action:
The proposed action is in accordance with the licensee's application dated February 14, 1995, for exemption from certain requirements of 10 CFR 73.55,
" Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage." The exemption would allow implementation of a hand geometry biomatrics system to control site access at Vogtle so that photo identification badges may be taken offsite by individuals not employed by the licensee who have been granted unescorted access into protected and vital areas.
The Need for the Proposed Action:
Pursuant to 10 CFR 73.55, paragraph (a), GPC shall establish and maintain an onsite physical protection system and security organization. Regulation 10 CFR 73.55(d), " Access Requirements," paragraph (1), specifies that the
" licensee shall control all points of personnel and vehicle access into a g
protected area." Regulation 10 CFR 73.55(d)(5) specifies that, "A 9507170367 950706 PDR ADOCK 05000424 P
. numbered picture badge identification system shall be used for all individuals vbo are authorized access to protected areas without escort." Regulation 10 CFR 73.55(d)(5) also states that an individual not employed by the licensee (i.e., contractors) may be authorized access to protected areas without escort provided the individual " receives a picture badge upon entrance into the protected area which must be returned upon exit from the protected area...."
Cutrently, unescorted access into protected areas at the Vogtle plant is controlled through the use of a photograph on a badge /keycard (hereafter referred to as a " badge"), which is stored at the access point when not in use.
The security officers at each entrance station use the photograph on the badge to visually identify the individual requesting access. The badges for GPC employees and contractor personnel who have been granted unescorted access are given to the individuals at the entrance location upon entry and are returned upon exit.
In accordance with 10 CFR 73.55(d)(5), the badges are not allowed to be taken offsite.
The licensee proposes to implement an alternate unescorted access control system that would eliminate the need to issue and retrieve badges at the entry point and would allow all individuals with unescorted access to keep their badges when departing the site.
An exemption from 10 CFR 73.55(d)(5) is required to permit contractors to take their badges offsite instead of returning them when exiting the site.
Environmental Imoacts of the ProDosed Action 1 The Commission has completed its evaluation of the licensee's application.
Under the proposed system, each individual who is authorized unescorted access would have the physical characteristics of their hand (hand geometry) registered with their badge number in the access control system.
When an individual enters the badge into the card reader and places the hand
- - -. ~ _ _
- on the measuring surface, the system would record the individual's hand image.
i The unique characteristics of the hand image would be compared with the previously. stored template to verify authorization for entry.
Individuals, i
including licensee employees and contractors, would be allowed to keep their badges when departing the site.
Based on the Sandia report, "A Performance Evaluation of Biometric Identification Devices," SAND 91-0276.UC-906, Unlimited Release, June 1991, that concluded hand geometry equipment possesses strong performance and high detectiun characteristics, and on its own experience with the current photo-identification system, the licensee determined that the proposed hand geometry system would provide the same level of assurance as the current system that access is only granted to authorized individuals.
Since both the badge and hand geometry would be necessary for access into the protected areas, the l
proposed system would provide a positive verification process.
Potential loss of a badge by an individual, as a result of taking the badge offsite, would not enable unauthorized entry into protected areas. The licensee has stated it will implement a process for periodically testing the proposed system to ensure continued overall level of performance equivalent to that specified in the regulation.
The Physical Security Plan will be revised to include implementation and testing of the hand geometry access control system and to allow licensee employees and contractors to take their badges-offsite.
The licensee has determined that the proposed hand geometry access control process for identifying personnel will provide the same high assurance objective regarding onsite physical protection as provided by the photo-identification process now in use.
The access process will continue to be under the observation of security personnel. A numbered picture badge identification system will continue to be
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,, used for all individuals who are authorized access to protected areas without escorts. Badges will continue to be displayed by all individuals while inside the protected areas.
Accordingly, the Commission concludes that this proposed action would result in no significant radiological environmental impacts. With regard to potential non-radiological impacts, the proposted action does not affect non-radiological plant effluents and has no other environmental impact.
Therefore, the Commission concludes that there are no significant non-radiological environmental impacts associated with the proposed action.
Alternative to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action. Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
This action did not involve the use of any resources not previously considered in the Final Environmental Statement related to operation of the Vogtle Electric Generating Plant, Units 1 and 2, dated March 1985.
Aaencies and Persons Consulted:
In accordance with its stated policy on June 13, 1995, the staff consulted with the Georgia State official, Mr. James Setser of the l
Environmental Protection Division, Georgia Department of Natural Resources, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed exemption.
Based upon the foregoing environmental
. assessment, the Commission has concluded that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the request for exemption dated February 14, 1995, which is available for public inspecticn at the Commission's Public Document Room, The Gelman Building, 2120 L Street, NW., Washington, DC at the local public document room located at the Burke County Public Library, ?l2 Fourth Street, Waynesboro, Georgia.
Dated at Rockville, Maryland, this 6th ' y of July 1995.
FOR THE NUCLEAR REGULATORY. COMMISSION ub%
>L He bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation I
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