ML20030E203
| ML20030E203 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/31/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8109180188 | |
| Download: ML20030E203 (2) | |
Text
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s TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 374ot 400 Chestnut Street Tower II C
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August 31, 1981 r
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Mr. Harold R. Denton, Sirector e
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission h
Washington, DC 20555
Dear Mr. Denton:
In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-25.0 50-296 In a July 21, 1981 meeting between NRC and TVA, regarding Browns Ferry physical security, a quGstion arose related to regulations (10 CFR 73 55(d)(8)) dealing with access control during eefueling outages in which aji fuel is removed from the reactor vessel. This letter outlines our interpretation regarding implementation of this regulation at the Browns Ferry Nuclear Plant.
Paragraph 73 55(d)(8) of 10 CPR requires, in part, the following:
Any time frequent access is permitted to containment such as during refueling or major maintenance, positive access control to assure that only a thorized personnel and materials are permitted into the containment shall be exercised by the licensee, with a guard or watchmen.
We believe the intent of this paragraph is to protect the integrity of both irradiated reactor fuel and vital areas.
At the present time Browns Ferry unit 1 is in a refueling outage with all fuel removed from the reactor. Furthermore, the currently approved Browns Ferry Physical Security Plan permits the designation of vital areas as nonvital by the plant manager when maintenance activit!es in a vital area will remove frem service all the vital equipment in that area.
At the conclusion of the outage we will perform two separate inspections. Before fuel loading the containment is inspecte' for explosives and incendiaries by a team made up of security, operatiors, and maintenance personnel.
Access control to the drywell is then established. Before final closure of the drywell a final inspection is performed as outlined in chapter 9 of the approved security plan.
8109180188 810831 6
1 DR ADOCK 0500025 41 0 An Equal Opportunity Employer
_2 Mr. Ilarold R. Denton August 31, 1981 We t>elieve that the intent of 10 CFR 73.55(d)(8) is ret given that there is no fuel in the vessel, the flexibility in designating vital areas noted in our approved physical security plan, and the inspections that are performed. We request that you review the requirements of 10 CFR 73.55(d)(8) and advise us immediately if your interpretation of this regulation is not in agreement with ours.
If you have any questions regarding this matter, please call Jim Doter at FTS 857-2014.
Very truly yours, TEtlNESSEE VAI. LEY A'D'.80RITY D1 a
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!!.' Mills, E nager Nuclear Regulation and Safety Subscribed and sworn t g efore me this u
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