LR-N04-0594, Special Report 04-013-00

Special Report 04-013-00

ML050190234
Person / Time
Site:	Hope Creek
Issue date:	01/07/2005
From:	Perino C Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
04-013-00, LR-N04-0594
Download: ML050190234 (3)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge. New Jersey 08038-0236

@ PSEG LR-N04-0594 NuclearLLC JAN O7 2005 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SPECIAL REPORT 354/04-013-00 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 This Special Report is being submitted pursuant to the requirements of Hope Creek Technical Specification (TS) 3.5.1, Action g. TS 3.5.1. Action g states:

"Inthe event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70."

On October 10, 2004, the reactor was scrammed due to a steam leak (pipe failure) in the turbine building. As discussed in LER 354/2004-010-00 dated December 9, 2004, following the manual scram of the reactor, condenser vacuum began to degrade.

Operators began to reduce reactor vessel pressure using the turbine bypass valves to allow for use of the secondary condensate pumps for reactor water level control. Due to the continued degradation of condenser vacuum, the reactor feedwater pumps tripped. Actions were taken to transition reactor vessel water level and pressure control to the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) systems. The Control Room Supervisor (CRS) directed the reactor operator to close the turbine bypass valves. As the bypass valves were closed, reactor water level reached the Level 3 scram setpoint (+12.5 inches) and continued to trend downward.

RCIC was manually initiated to restore water level. As the turbine bypass valves were going closed, level continued to trend downward until reactor water level reached the Level 2 setpoint (-38") on two (A and B) of the four reactor vessel level channels. As a result of the Level 2 setpoint being reached HPCI automatically actuated and injected water to the reactor coolant system.

95-2168 REV. 7/99

-Document Control Desk 2 LR-N04-0594 JAN 0 7 2005 The HPCI automatic initiation and injection into the reactor vessel was the result of the trip of the reactor feedwater pumps and the transition to the condensate system for reactor feedwater level control.

An assessment of the total accumulated actuation cycles for the HPCI injection nozzles and the nozzle usage factors is currently in progress. The results of this assessment will be reported in a supplement to this Special Report by March 31, 2005.

If you have any questions regarding this submittal, please contact Brian Thomas at (856)339-2022.

Sincerely, Christina Perino Director - Licensing and Nuclear Safety

,Document Control Desk 3

, LR-N04-0594 JAN 'O7 2005 BJT C Mr. S. Collins, Administrator- Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 USNRC Senior Resident Inspector- Hope Creek (X24)

Distribution LER File 3.7