05000333/LER-1979-058-03, /03L-0:on 790903,HPCI Sys Turbine Was Uncoupled from Pump to Allow Overspeed Testing.Caused by Intentional Disabling to Satisfy Insurance Underwriters Requirement. Following Test,Pump & Turbine Recoupled & Sys Operable

/03L-0:on 790903,HPCI Sys Turbine Was Uncoupled from Pump to Allow Overspeed Testing.Caused by Intentional Disabling to Satisfy Insurance Underwriters Requirement. Following Test,Pump & Turbine Recoupled & Sys Operable

ML19209A748
Person / Time
Site:	FitzPatrick
Issue date:	10/01/1979
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19209A745	List: 05000333/LER-1979-058, Forwards LER 79-058/03L-0 05000333/LER-1979-058-03, /03L-0:on 790903,HPCI Sys Turbine Was Uncoupled from Pump to Allow Overspeed Testing.Caused by Intentional Disabling to Satisfy Insurance Underwriters Requirement. Following Test,Pump & Turbine Recoupled & Sys Operable
References
LER-79-058-03L, LER-79-58-3L, NUDOCS 7910050328
Download: ML19209A748 (2)

LER-1979-058, /03L-0:on 790903,HPCI Sys Turbine Was Uncoupled from Pump to Allow Overspeed Testing.Caused by Intentional Disabling to Satisfy Insurance Underwriters Requirement. Following Test,Pump & Turbine Recoupled & Sys Operable

Event date:
Report date:
3331979058R03 - NRC Website

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.AMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-058/03L-0 rige 1

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During plant heat up, as a part of normal startup operations, the HPCI System turbine was intentionally uncoupled f rom the pump to allow over speed testing of the turbine in accordance with F-ST-4K titled "HPCI Turbine Over Speed Testing." This action, while required by the Insurance Underwri ters, caused the HPCI System to be placed in a degraded mode identif f rd in Technical Speci ficat ions Appendix A, Paragraph 3.5.C. I.a.

Since the HPCI System is designed for the protection in the event of certain small brenk LOCA conditions between 150 and 1120 psig, the intentional disabling of the system at a pressure of less than 150 psig, did not represent any significant hazard to the public health and safety.

During the conduct of F-ST-4K, which was satisfactory and was witnessed by a representative of the insurance Underwriters, reactor pressure was maintained below 150 psig.

Following completion of the test the pump and turbine were re-coupled and the system demonstrated operable to meet the requi rements of Technical Speci fications Appendix A, Paragraph 4.5.C.

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