ML20215C693
| ML20215C693 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/09/1986 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215C696 | List: |
| References | |
| NUDOCS 8612150340 | |
| Download: ML20215C693 (2) | |
Text
gth Ca Electric & Gas Company Dan A.
u Coumb 29218 Nuclear Operations SCE&G
~*
December 9,1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12
]
Technical Specification Change Design Features
Dear Mr. Denton:
South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Virgil C. Summer Nuclear Station Technical Specifications, Section 5.3.1, " Fuel Assemblies". This change, as shown on Attachment I, would allow SCE&G the flexibility to reconstitute fuel assemblies in order to reduce coolant activity and utilize the remainin defective fuel rods. g energy in fuel assemblies which contain small numbers of In a reconstitution process, the fuel rods can be removed or replaced with dummy rods. This reconstitution is accomplished by either removing the top or bottom nozzle, inspecting and removing the defective rods, replacing the failed rods with dummy rods or leaving the defective rod locations empty, and reattaching the nozzle. The process also enables serviceable fuel rods and dummy rods to be transferred to a new fuel assembly skeleton in the event a skeleton is damaged.
Because the specific fuel inventory in reconstituted assemblies cannot be determined in advance of a refueling,in each relo'ad core the reconstituted assemblies will be evaluated using standard methods currently utilized in accepted Westinghouse reload methodology topicals. Existing safety criteria and design limits will continue to be applied to the reconstituted assemblies including consideration in the core physics analysis of peaking factors and core i
l average linear heat rate effects.
l 1 is a discussion of SCE&G's No Significant Hazards Determination.
This change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee. Please find enclosed the l
application fee of $150.00 required by 10CFR170.
If you should have any questions, please advise.
l l
l ery u yours, N
l 8612150340 861209 D
0 ma PDR ADOCK 05000395 i
P PDR k 00l O
4I
o Mr. Harold R. Denton Page Two December 9,1986 AMM: DAN /dwf Attachments pc:
O. W. Dixon, Jr/T. C. Nichols, Jr.
E. H. Crews, Jr.
E. C. Roberts O. 5. Bradham J. G. Connelly, Jr.
D. R. Moore W. A. Williams, Jr.
J. Nelson Grace Group Managers W. R. Baehr C. A. Price i
C. L. Ligon (NSRC)
R. M. Campbell, J r.
K. E. Nodland R. A.Stough G. O. Percival R. L. Prevatte J. B. Knotts, Jr.
l H. G. Shealy l
NPCF l
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