PNO-IV-85-058A, on 851118,administrative 5% Thermal Power Limit of Section 2c of License NPF-40 Exceeded.Caused by Shift Supervisor Misunderstanding Commission Vote on Full Power License.Shift Supervisor Disciplined

PNO-IV-85-058A:on 851118,administrative 5% Thermal Power Limit of Section 2c of License NPF-40 Exceeded.Caused by Shift Supervisor Misunderstanding Commission Vote on Full Power License.Shift Supervisor Disciplined

ML20136G053
Person / Time
Site:	River Bend
Issue date:	11/19/1985
From:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
References
PNO-IV-85-058A, PNO-IV-85-58A, NUDOCS 8511220241
Download: ML20136G053 (2)

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November 19, 1985 PRELIMINARY NOTIFICATION OF EVENT OR UtiUSUAL OCCURRENCE -- PN0-IV-85-58A This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by NRC staff on this date.

FACILITY: Gulf States Utilities Licensee Emergency Classification:

River Bend Station Notification of Unusual Event St. Francisville, LA Alert Docket 50-458 Site Area Emergency General Emergency 1 Not Applicable

SUBJECT:

PERSONflEL ERROR IN EXCEEDING REDUCED THERMAL LlitlT

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This updates our PN0-IV-85-58 entitled " Reduced Thermal Limit Potentially Exceeded," dated November 18, 1985.

The licensee reported to the NRC via ENS at 2337 on November 18, 1985, that the administrative 5% thertial power limit of Section 2c of the license was exceeded in that indicated sower was allowed to go to approximately 6.5% by average APRM reading for 21ours and 15 minutes on the morning of November 18. At the time of this occurrence, reactor power was being raised to perform turbine testing. This testing involved steam chest warming and

, k turbine rolling and was scheduled to be conducted at a reactor power of approximately 7% if the full lower license was available, otherwise at 5%.

5 The results of the Conmission vote on the River Bend full power license were hN misunderstood by the shift supervisor on duty. When questioned by oncoming shif t operators, this error was then discovered and indicated reactor power was reduced within limits. Actual reactor power based on steam flow was y, calculated to be approximately 3.5% during this occurrence.

$' The shif t supervisor involved in this event has been ruoved f rom shif t duties for 7 days during which time he will not receive his license bonus and was further disciplined with I day of f without pay. Other nen.bers of the shif t y will be interviewed by management and counseled prior to resuming shift (cont.onpage2) l CONTACT: E. H. Johnson, FTS 728-0106

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duties. All oth:;r op3 rating crews are also being briefed on this event. The licensee conducted a management review of this event and concluded that the i shif t turnover process needs to be improved to prevent such misunderstanding in the future. For the next several weeks the licensee has decided that the shift turnover will be conducted by the assistant plant manager for operations, the operations supervisor or his assistant.  ;

Region IV sent the project section chief to the site on November 19. 1985, to review this event and determine the adequacy of these actions including interviews with personnel involved, lie is being assisted by the SRI and the  ;

RI as well as the SRI from Ffvt St. Vrain, who is at the plant this week to observe startup testing. The onsite RIV staff will continue to monitor licensee activities on this event.

NRR. IE and the state of Louisiana have been informed.

This information is current as of 1:00 p.m. (CST) November 19. 1985.

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