ML20028A988
| ML20028A988 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/23/1982 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8211290285 | |
| Download: ML20028A988 (2) | |
Text
r 4
J' SOUTH CAROLINA ELECTRIC & gas COMPANY post oppuca 7m COLUMBIA. SOUTH CAROUNA 29218 O. W. DixON, JR.
VICE PatSiDENT NucLEAn OpenArsoNS November 23, 1982 1
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 Interpretation of License Condition 2.C.(14)
Dear Mr. Denton:
The purpose of this letter is to establish South Carolina Electric and Gas Company's (SCE&G) interpretation of Operating License Condition 2.C.(14) concerning operation of the Virgil C.
Summe r Nuclear Station at 50% rated thermal power.
For normal plant operations, the following criteria will be applied:
the average power level over any eight hour shift should not exceed the steady-state licensed power level of 50%. It is permissible to briefly exceed the steady-state licensed power level by as much as 2% for as long as 15 minutes.
In no case should 52%
l power be exceeded, but lesser power " excursions" for longer periods l
shall be allowed with the above as guidance (i.e.,1% excess for 30 l
minutes, 1/2% for one hour, etc, shall be allowed).
There are'no limits the number of times these
" excursions" may occur, or the time interval that must separate such " excursions".
To conduct standard startup testing at the 50% power level, 50% rated thermal power may be exceeded by 2% to 5% for short durations.
Because of flux tilts, indicated reactor power may be as high as 60% on some channels.
For these tests, the overpower reactor trip will be set at 70%.
The expected duration of these tests is approximately three (3) days.
Conduct of these tests at 50% power level as described above is in agreement with the Safety Evaluation Report Supplement No. 5 (NUREG 0717).
i Bo f
o l
1 8211290205 821123
~
PDR ADOCK 05000395 P
n j'
Mr. Harold R.
Denton Interpretation of License Condition 2.C.(14)
Page Two November 23, 1982 If you have any questions, please let us know.
Very truly your,
4hk{
O. W. Dixon, Jr.
NEC:OWD:dwr cc:
V.
C.
Summer G.
H. Fischer H. N. Cyrus T.
C. Nichols, Jr.
O. W. Dixon, Jr.
M.
B.
Whitaker, Jr.
J.
P. O'Reilly H. T. Babb D.
A. Nauman C. L. Ligon (NSRC)
W.
A. Williams, Jr.
R. B. Clary O.
S.
Bradham A. R. Koon M. N. Browne G. J. Braddick J. L. Skolds J.
B. Knotts, Jr.
B. A. Bursey NPCF File