ML20099E621

Special Rept Spr 85-001:on 850128,RCS Dilution Resulted in Increased Main Turbine/Generator Load.Action Initiated to Programmatically Address Operating Guidelines for Deviation from 100% Average Thermal Power

ML20099E621
Person / Time
Site:	Summer
Issue date:	02/14/1985
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
SPR-85-001, SPR-85-1, NUDOCS 8503140049
Download: ML20099E621 (2)

Text

,_.

SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFFICE 764 cowusiA. soutw cacousa 2sais I,CT .'E"~c. "i 85 f EB 19 9ekrMy 14,1985 NuCLEan OPERATIONS Dr. J. Nelson Grace Regional Administrator U.S. Nuclear Regulatory Commission Suite 2900 '

101 Marietta Street, NW Atlanta, GA 30323

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Special Report (SPR 85-001)

Dear Dr. Grace:

Attached is a Special Report for the Virgil C. Summer Nuclear Station.

This Special Report is being submitted pursuant to the requirements of Facility Operating License No NPF-12, Section 2, Item G.l.

Should there be any questions, please call us at your convenience.

r tr21y yours, i

i l d

O. W. Dixon, Jr.

RJB:OWD/ led Attachment cc: V. C. Summer K. E. Nciland T. C. Nichols, Jr./O. W. Dixon, Jr. R. A. Stough E. H. Crews, Jr. G. Percival E. C. Roberts C. W. Hehl W. A. WIliiams, Jr. J. B. Knotts, Jr.

D. A. Nauman I&E Washington Group Managers Document Management Branch O. S. Bradham INPO Records Center C. A. Price ANI Library S. R. Hunt NPCF J. F. Heilmaa File C. L. Ligon (NSRC) l5 31gO g 85 5 MM CC)P'/,

s 1 TEA N t

\

E

~ .

-Dr..J. Nelson Grace.

SPR 85-001' February 14, 1985 EVENT DESCRIPTION AND ACTION TAKEN At approximately 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on January 28, 1985, a Reactor Coolant System dilution was performed to increase Tavg from 585.5'F to the full load value of 587'F. This evolution resulted in an. increased main turbine / generator load of approximately 4 MWe. Upon discovery of the increased power level by the operating personnel at approximately 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, action was taken to reduce power. Power reductions continued during the remainder of the shift (1900-2400 hours) with effort to maintain steady state full power operation.

However, action taken did not preclude exceeding the "100%

steady-state licensed power level" of 2775 megawatts thermal as specified in Section 2, Item C.1 of the Facility Operating License No.

NPF-12. Reactor thermal power output average over the eight (8) hour period (1600-2400) was determined to be 2778.24 megawatts thermal or 100.11% of rated thermal power.

l ACTION TAKEN TO PRECLUDE RECURRENCE The Licensee considers this to be an isolated event. However, the following corrective action will be initiated no later than March 1, 1985. Action is being initiated to programmatically address operating guidelines for deviation from 100% averaged thermal power.

In addition, by copy of a' letter from the Director, Nuclear Plant Operations, Shift Supervisors are to assure that the power level'is maintained not greater than 100% of rated thermal power averaged over an eight-(8) hour period.

55f

- - - . . -. -. - . . . . - . . .-. - - - _ . _ - . ---