05000277/LER-1984-003, Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate

Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate

ML20084H437
Person / Time
Site:	Peach Bottom
Issue date:	05/03/1984
From:	Brooke Clark, Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-84-003, LER-84-3, NUDOCS 8405080061
Download: ML20084H437 (3)

LER-2084-003, Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate

Event date:
Report date:
2772084003R00 - NRC Website

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Ibach Hottom Atomic Ibwer Station - Unit 2 e is te toIo r2 r7 17 1 lorl01 2' f atti del Reactor Vessel IIcatup Rate Exceeded 100 Degrees Fahrenheit per hour.

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.4 n . . e , ,u- . . , . . .. . .,, a,- . . -.<-. , n a Abstract 2-84-03 Technical Specification 3.6.A.1 states that the average rate of reactor goolant temperature change during normal heatup or cooldown*shall not exceed 100 degrees Fahrenheit increase (or decrease) in any one hour period,

, During startup on Unit 2, the Reactor Operator noted that the heatup rate was exceeding the Technical Speci.fication limit of 100 degrees Fahrenheit in a 1-hour period per Surveillance Test 9.12 (Reactor Vessel Temperatures). In responding, the operator failed to take adequate corrective action rapidly enough and the reactor coolant temperature increased by 110 degrees Fahrenhalt within a one hour period.

General Electric has evaluated the excess heatup rate and concluded that it had a minimal effect on the reactor pressure vessel.

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During startup on Unit 2, the Reactor Operator noted that the heatup rate was exceeding the Technical Specification limit of 100 degrees Fahrenheit in a 1-hour period per Surveillance Test 9.12 (Reactor Vessel Temperature) . In responding, the operator failed to take adequate corrective action (inserting control rods and opening turbine bypass valves) rapidly enough. The result was that the reactor coolant temperature increased by 110 degrees Fahrenheit within a one hour period. Applicable Technical Specification Reference 3.6.A.1, states that the average rate of reactor coolant temperature change during normal heatup or ccoldown shall not exceed 100 degrees Fahrenheit increase (or, decrease) in any 1-hour period. ,,

Conseguences_gf_the Event:

IIcatup rates far greater than 100 degrees Fahrenheit per hour were considered in the original reactor vessel design analysis.,

This transient has been evaluated by GE and'detertained to have imposed only a negligible increase in the usage factor for-the most limiting reactor pressure vessel component.

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The cause of the event was personnel error.

Corrective Actions: -

d The responsible operator has been disciplined regarding his =

inadequate performance (for exceeding the heatup rate and failing ,

to take adequate action promptly enough). The station superintendent has issued a memo to all licensed operators to ensure that the intent of the Technical Specification heatup rate requirement is understood and to emphasize the use of diverse instrumentation available in the control room as a cross check on., '

reactor heatup rates. ,

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'b PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.191o1 12151841-4000 May 3, 1984 Docket No. 50-277 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Licensee Event Report This LER concerns the Unit 2 reactor vessel heatup rate exceeding its Technical Specification limit of 100 degrees Fahrenheit increase in a 1-hour period,-while in the startup mode.

Reference:

Docket No. 50-277 Report Number: 2-84-03 Revision Number: 01 Event Date: January 31, 1984 Report Date: May 3, 1984 Facility: Peach Bottom Atomic Power Station RD #1, Box 208, Delta, PA 17314 This LER is submitted pursuant to the requirements of 10 CFR 50.73 (A) (2) (1) (B) . The revised portion of this LER is identified by a vertical bar in the margin.

Very truly yours, N/Nd W. T. Ullrich Superintendent Nuclear Generation Division-cc: Dr. Thomas E. Murley, Administrator Region I, USNRC Mr. A. R. Blough, Site Inspector

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