ML20199F805
| ML20199F805 | |
| Person / Time | |
|---|---|
| Site: | 07002928 |
| Issue date: | 01/27/1998 |
| From: | Weber M NRC |
| To: | |
| Shared Package | |
| ML20199F669 | List: |
| References | |
| NUDOCS 9802040121 | |
| Download: ML20199F805 (2) | |
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., oce:g g- .1 UNITED STATES
- S NUCLEAR REGULATORY COMMISSION b f WASHINGTON, D.C. 3004&0001
%,,,,,. January 27, 1998 DOCKET: 70-2928 LICENSEE: Tennessee Va; ley Authority (TVA)
Watts Bar Nuclear Plant, Unit 2 Chattanooga, Tennessee
SUBJECT:
SAFETY EVALUATION REPORT: APPLICATION DATED SEPTEMBER 29, 1997, REQUEST TO TERMINATE LICENSE SNM-1873 BACKGROUND The Watts Bar Nuclear Plant is located on the Tennessee River in Rhea County, Tennessee, approximately 50 miles northeast of Chattanooga. The plant consists of two nuclear reactors.
Unit i has an operating license, NPF-90, and Unit 2 has a Construction Permit CPPR 92, Docket 50-391, and a new fuel storage License SNM-1873, Docket 70 2928. Special Nuclear Material License SNM-1873 was issued on February 17,1981. This licenso authorizes the receipt, possession, inspection, and storage of fuel assembles and fuel rods, and will expire by a certain date or upon conversion of the construction permit to an operating license. The license has been extended several times in the past by amending the expiration date. By application dated September 29,1997, the licensee requested termination of License SNM-1873 instead of renewing it past the curre,7t date of October 31,1997, because the new fuel storage aree and associated activities would continue under the Unit 1 operating license (NPF 90). Since the licensee requested termination prior to the expiration date, the license is considered active pending final NRC action on the request.
DISCUS WN in supps f its request to terminate License SNM-1873, TVA, pursuant to 10 CFR 70.38, provideo o ampleted NRC Form 314, ' Certificate of Disposition of Materials," demonstrating that all special nuclear material obtained under License SNM-1873 was transferred to other authorized recip;ents. In addition, the licensee explair ed that no radiological contamination survey was required since the plant new fuel storage areas and activities covered by License SNM 1873 are currently covered by the Unit 1 operating license. Thus, any contamination associated with SNM-1873, if it existed, would be dealt with under NPF 90.
In eva:uating the licensee's request, the staff used the guidance provided in NUREG/3R-0241, "NMSS Handbook for Decommissioning Fuel Cycle and Material Licensees.' Based on the information provided by the licensee in its submittal dated September 29,1997, and information provided by the NRR project manager and regional and rasident inspectors, this license meets the conditions _for a Type l Decommissioning type, i.e., the licensee possessed and used only sealed sources, no activation of adjacent materials occurred during storage and possession of the fresh fuel, and the most recent leak test results demonstrate that the sources did not leak while in the licensee's possession. Accordingly, in order for NRC to approve the termination 9002040121 9G0127 PDR ADOCK 07002928 C PDR
9 I
2 request, the licensee is required to submit a completed NRC Form 314 and provide a demonstration or survey that the new fuel storage area is contamination free or demonstrate the affected areas arc covered under a separate license.
The staff reviewed the licensee's submitted NRC Form 314 and determined that the special nuclear material had been transferred to authorized recipients, and no material is currently possessed under License SNM-1873. Also, the staff agrees that no special contamination survey is required for the termination of this license, because the new fuel storage area and routine contamination surveys are currently covered under Unit 1 operating license, NPF 90.
The staff finds the information acceptable.
EtiVIRONMENTAL REVIEW
- The licensee's termination request is considered administrative in nature, because the new fuel storage area and new fuel activities are continuing ur. der the Unit 1 operating license Therefore, the staff has determ'ned that the following conditions have been met:
- 1. There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
- 2. There is nc significant increase in individual or cumulative occupational radiation exposure.
- 3. There is no significant construction impact.
- 4. There is no significant increase in the potential for or consequences from radiological accidents.
Accordingly, pursuant to 10 CFR 51.22(c)(11), neither an environmental assessment nor an environmental impact statement is warranted for this action.
CONCLUSION Based on the discussion, the staff concludes that the proposed termination request can be granted without undue risk to the workers and public.
The Region 11 inspection staff and NRR project manager have no objection to this proposed action.
A Princloal Contributor .. , /
- - /M Michael Lamastra g 7, /'N f sy 1
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