05000368/LER-1978-029-03, /03L-0 on 781227:in Mode 1 Operation,During Main Turbine Roll,Main Steam Relief Valve 2PSV1053 Lifted,Due to Steam Dump Valve Failures.Valve Failed to Reseat,Causing RCS Temp to Drop 107 Feet within 52 Min

/03L-0 on 781227:in Mode 1 Operation,During Main Turbine Roll,Main Steam Relief Valve 2PSV1053 Lifted,Due to Steam Dump Valve Failures.Valve Failed to Reseat,Causing RCS Temp to Drop 107 Feet within 52 Min

ML19269C290
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/25/1979
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19269C282	List: 05000368/LER-1978-029-03, /03L-0 on 781227:in Mode 1 Operation,During Main Turbine Roll,Main Steam Relief Valve 2PSV1053 Lifted,Due to Steam Dump Valve Failures.Valve Failed to Reseat,Causing RCS Temp to Drop 107 Feet within 52 Min 05000368/LER-1978-030-03, /03L-0 on 781227:in Mode 1 Operation,During Main Turbine Roll,Main Steam Relief Valves 2PSV1053 Lifted,Due to Steam Dump Valve Failures.Failed to Reseat,Causing Excessive RCS Cooldown 05000368/LER-1978-032-03, /03L-0 on 781228:during Mode 2 operation,2P7A, Emergency Feedwater Pump a Tripped on Overspeed When Feeding Steam Generators.Cause Was Damaged Lead in Speed Control Unit ML19269C281
References
LER-78-029-03L, LER-78-29-3L, NUDOCS 7901310056
Download: ML19269C290 (1)

LER-1978-029, /03L-0 on 781227:in Mode 1 Operation,During Main Turbine Roll,Main Steam Relief Valve 2PSV1053 Lifted,Due to Steam Dump Valve Failures.Valve Failed to Reseat,Causing RCS Temp to Drop 107 Feet within 52 Min

Event date:
Report date:
3681978029R03 - NRC Website

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NRC FORM 366 U. S. NUCLE AR REGUL ATORY COMMISSION (7 77)

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60 (p t DOCKET hbMB E R 68 69 EVENT DATE le 75 HE,OHf DATE to EVENT DESCRIPTION AND PROBA0LE CONSEQUENCES h I01211 Mode 1 operation, during Main Turbine roll, Main Steam relief valve o 3 l 2PSV1053 lifted, due to steam dump valve failures (reference LER I6 TTl L5.0-318/78-SH. and failed to reseat, causing the RCS temperature to l

in ist i drop 1070F within 52 minutes, exceeding 1000F/hr. limit per T.S.3.4.9.1.b j

l0 j6 ] l for an approximate 10 minute period. No similar occurrences. Reportable I per T.S.6.9.1.9(b).

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RCS Tave was re-ppj stored to 5450F within 30 minute;; as required by Action Statement i 2 1 T.S.3.4.9.1.

An engineering evaluation was performed by the NSSS vendorg g i to determine the effects on the fracture toughness properties of the RCS.,

It was determined that the RCS remains acceptable for continued operation.

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