ML20024F455

LER 83-090/03L-0:on 830818,while Increasing Reactor/Turbine Power from 14 to 20%,rod Insertion Limit Violated.Caused by Operating Personnel Failure to Establish Plant Parameters. Emergency Boration initiated.W/830831 Ltr

ML20024F455
Person / Time
Site:	Summer
Issue date:	08/31/1983
From:	Bouknight R, Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
LER-83-090-03L, LER-83-90-3L, NUDOCS 8309090397
Download: ML20024F455 (3)

Text

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l c 12 l l On August 18, 1983, with the Plant in Mode 1, while increasing Reactor / Turbine l lo p ll power from 14% to 20%, the Rod Insertion Limit as specified in Technical l

lo 9 ll Specification 3.1.3.6, " Control Rod Insertion Limits," was violated. There j g o in l l were no adverse consequences due to the event. The Licensee cmplied with l

o ;,; j Action Statement (a) of the aforementioned Technical Specification.

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u o p 191919l CAUSE DESCRIPTION AND CORREC'ilVE ACTIONS b27 l 3 j o j l The cause of this event was due Co the failure of operating personnel to l

, l establish plant parannters. Immediate corrective action was the initiation of l

,,.,l Emergency Boration upon receipt of the Lo-Lo Alarm. All operators are to review l this report noting the inportance of evaluating the Plant conditions prior to g and during Plant statds change, y

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Vice P.ESIDENT wucosa. ore. rioN. August 31, 1983 g3 $[p g Ag 34 Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W.

Atlanta, Georgia 30303

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 83-090

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #83-090 for Virgil C.

Summer Nuclear Station. This Thirty Day Report is required by Technical Specification 6.9.1.13.(b) as a result of entry" into Action Statement (a) of Technical specification 3.1.3.6, Control Rod Insertion Limits," on August 18, 1983.

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

Very truly yours,

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O. W. ixo , .

RJB:OWD/mac/fjc Attachment V. C. Summer C. L. Ligon (NSRC) cc:

E. H. Crews, Jr. G. J. Braddick T. C. Nichols, Jr.,/O. W. Dixon, Jr.

J. C. Miller E. C. Roberts J. L. Skolds J. B. Knotts, Jr.

H. N. Cyrus I&E (Washington)

Group / General Managers Document Management O. S. Bradham R. B. Clary Branch C. A. Price INPO Records Center NPCF A. R. Koon File (Lic./Eng.)

D. A. Lavigne J. F. Heilman UFFICIAL

. . . CO.PY f6 213 t 1

Mr. James P. O'Reilly LER No.83-090 Page Two August 31, 1983 EVENT DESCRIPTION AND' PROBABLE CONSEQUENCES On August 18, 1983, with the Plant at 14% power, startup of the Secondary Plant was complete and the Generator was synchronized at 2323 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.839015e-4 months <br />. Boration was in progress through the normal boration flow path at approximately 15 gpm. A 6% Reactor / Turbine power increase was initiated to go to 20% power. At 2343 hours0.0271 days <br />0.651 hours <br />0.00387 weeks <br />8.915115e-4 months <br />, a Rod Insertion Limit Lo-Lo Alarm was received and Action Statement (a) of Technical Specification 3.1.3.6, " Control Rod Insertion Limits," was entered. There were no adverse consequences due to this event. The Licensee complied with the aforementioned action statement.

CAUSE AND CORRECTIVE ACTIONS The cause of this event was due to the failure of operating personnel to establish and maintain plant parameters prior to

-and during a change in plant power level.

Immediate corrective action upon receipt of the Lo-Lo Rod Insertion Limit Alarm was initiation of Emergency Baration. The alarm was cleared after approximately three (3) minutes. At the time of the alarm, the Rod Insertion Limit was 28 Steps Bank D; actual position was 26 Steps Bank D.

Additional' corrective action will be taken by the dissemination of this report'to all operators noting the importance of evaluating steady state and anticipated transient. conditions prior to changing plant status.

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