ML20101N698
| ML20101N698 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/04/1996 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20013A240 | List: |
| References | |
| NUDOCS 9604090072 | |
| Download: ML20101N698 (3) | |
Text
..
Tennessee Valley Authonty Post office Box 2000. Soddy Dasy. Tennessee 37379 April 4,1996 TVA-SON-TS-96--
10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)
CHANGE 96-01, " CONVERSION FROM WESTINGHOUSE ELECTRIC CORPORATION t
FUEL TO FRAMATOME COGEMA FUEL (FCF) (MARK-BW17)"
In accordance with 10 CFR 50.90, we are enclosing an amendment to Licenses DPR-77 and DPR-79 to change the TSs of SON Units 1 and 2. The proposed change revises the appropriate specifications, surveillances, and bases to allow for the conversion from Westinghouse fuel to FCF. This will also include a discussion of
(
operation cycles that include mixed cores.
The proposed TS change is identified in Enclosure 1. The justification for the proposed TS change is provided in Enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in l. Enclosure 4 contains the application for withholding BAW-10220Pfrom 1
public disclosure. Enclosure 5 contains FCF Topical Report BAW-10220P, Revision 0, which is the proprietary version and contains specific terminology and methodology to support this submittal. The nonproprira.ary version (BAW-10220NP)is supplied in. A marked-up copy of the appropriate sections of the SON Updated Final Safety Analysis Report is being transmitted as supporting information and is contained in Enclosure 7. A sample of the proposed Core Operating Limits Report is contained in. Enclosure 9 contains the Westinghouse review to support the reduced thermal design flow for the large-break loss of coolant accidert evaluation.
4 i
\\
osnea s
Qv S, qL r6 f 9604090072 960404 j
3 k
PDR ADOCK 05000327 i
P PM ik
e U.S. Nuclear Regulatory Commission Page 2 April 4,1996 Since BAW-10220P, Revision 0 contains information proprietary to FCF, Enclosure 4.
contains the application for withholding and affidavit JHT/96-20 signed by FCF, the owner of the information. The application for withholding and the affidavit set forth the basis on which the information may be withheld from public disclosure by NRC and address with specificity the considerations listed in Section 2.790, Paragraph (b)(4) of the NRC regulations.
Accordingly, it is respectfully requested that information which is proprietary to FCF be withheld from public disclosure in accordance with 10 CFR, Section 2.790, of the NRC regulations.
Correspondence, with respect to the propriety aspects of the items listed above or the supporting FCF affidavit, should reference JHT/96-20 and should be addressed to J. H. Taylor, Manager of Licensing Services, Framatome Cogema Fuels, P. O.
Box 10935, Lynchburg, Virginia 24506-0935.
As has been previously discussed with NRC, TVA will convert to FCF fuel assemblies beginning with each unit's Cycle 9 core. The Unit 1 Cycle 8 refueling outage is presently scheduled to begin in early April 1997 and receipt of the Unit 1 approved cha. ge is needed prior to this date to support the outage. The Ur.it 2 Cycle 8 refueling outage is presently scheduled to begin in early October 1997. Therefore, it is requested that the implementation of each unit's TSs be required prior to start-up from each unit's respective Cycle 8 refueling outage.
Please direct questions concerning this issue to Bill Ludwig at (423) 843-7460.
Sincerely, R. H. Shell Manager SON Site Licensing Sworn to and subscribed before me this 5* day of 22A4u 1996 Y
h AAtary Public My Commission Expires /d %2/-98 Enclosures cc: See papa P i
U.S. Nuclear Regulatory Commission Page 3 April 4,1996 cc (Enclosures):
Mr. D. E. LaBarge, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director (w/o Enclosures)
Division of Radiological Health 3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident inspector Sequoyah Nuclear Plant 2600 lgou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 l
l l
4
..,,