05000315/LER-1981-034-03, /03L-0:on 810804,during Power Reduction, Pressurizer Pressure Dropped Below Min Tech Specs.Caused by Turbine Load Reduction Rate Being Greater than Reactor Power Reduction Rate.Event Will Be Reviewed by Operators

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/03L-0:on 810804,during Power Reduction, Pressurizer Pressure Dropped Below Min Tech Specs.Caused by Turbine Load Reduction Rate Being Greater than Reactor Power Reduction Rate.Event Will Be Reviewed by Operators
ML20010G182
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 09/03/1981
From: Campbell D
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20010G174 List:
References
LER-81-034-03L, LER-81-34-3L, NUDOCS 8109150411
Download: ML20010G182 (2)


LER-1981-034, /03L-0:on 810804,during Power Reduction, Pressurizer Pressure Dropped Below Min Tech Specs.Caused by Turbine Load Reduction Rate Being Greater than Reactor Power Reduction Rate.Event Will Be Reviewed by Operators
Event date:
Report date:
3151981034R03 - NRC Website

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q NRC FORM 366 U.S. NUCLE AR REGULATORY COMMISSION

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60 61 DOCKET NUMBER tid 69 EVENT D ATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 10 iO i2i I WHILE REDUCING REACTOR POWER FROM 35. TO 8% IN PREPARATION FOR TURBINE OVERSPEEDl TESTING, PRESSURIZER PRESSURE TWICE WITHIN A TEN-MINUTE PERIOD DROPPED BELOW THE MINI-l IO lai i io i4i l MUM PRESSURE LIMIT OF 2220 PSIA REQUIRED BY TECHNICAL SPECIFICATION 3.2.5.-DURING THEl l FIRST INSTANCE THE PRESSURE DROPPED TO 2210 PSIA FOR APPR0XIMATELY TWO-MINUTES l

ioi3i DURING THE SECOND INSTANCE THE PRESSURE DROPPED TO 2198 PSIA FOR APPROXIMATELY THREE-l 101s 1 i l 0 l 7 l l MINUTES. THERE WAS N0 THREAT TO THE PUBLIC HEALTH AND SAFETY. PREVIOUS SIMILAR l

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44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1i l 0 l l BOTH TRANSIENTS WERE RESULTS OF TURBINE LOAD REDUCTION RATE BEING GREATER THAN REACTOR l li ii j i POWER REDUCTION RATE. B0T4 THE TURBINE AE THE REACTGR WERE BEING CONTROLLED MANU-1 i1,i l ALLY. DURING THE FIRST INSTANCE AN OVE"#0RRECTION OF REACTOR POWER OCCURRED CAUSING i l A DROP IN TAVE AND THE RESULTING DROP IN PRESSURIZER PRESSURE. DURING THE SECOND l

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SUPPLtNENT TO LER N0.81-034/03L-0 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES (10) t 78-99, 78-73, 78-72. DOCKET NUMBER 050315 - NO PREVIOUS SIMILAR EVENTS ON UNIT ONE.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

OPERATED RELIEF VALVE WHICH RESULTED IN A DROP IN TAVE AND PRESSURIZER PRESSURE.

TO PREVENT RECURRENCE, THIS EVENT WILL BE REVIEWED BY ALL LICENSED OPERATORS.

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