LR-N08-0164, Special Report - Safety Relief Valve (SRV) Acoustic Monitor

Special Report - Safety Relief Valve (SRV) Acoustic Monitor

ML082260423
Person / Time
Site:	Hope Creek
Issue date:	08/05/2008
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N08-0164
Download: ML082260423 (2)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 AUG Oii5 2008 Technical Specification 6.9.2 64 0 PSEG NuclearLLC U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354

Subject:

Special Report - Safety Relief Valve (SRV) Acoustic Monitor This special report is being submitted pursuant to the requirements of Hope Creek Technical Specification (TS) 3.3.7.5, "Accident Monitoring Instrumentation" Table 3.3.7.5-1 Action 80, due to the "L" SRV Acoustic Monitor being inoperable for greater than 30 days. Action 80 requires initiation of actions in accordance with TS 6.9.2. TS 6.9.2 requires "Special reports shall be submitted... within the time period specified for each report". This report is being submitted since the repairs to the monitor will not be completed within the 30-day period.

On July 17, 2008 multiple unexpected alarms were received in the Control Room indicating that the "L"SRV valve was open. This alarm is initiated via the acoustic monitor. All other plant parameters indicated the SRV was closed. The "L" acoustic monitor was declared inoperable and TS 3.3.7.5 Table 3.3.7.5-1 Action 80 was entered.

Troubleshooting activities have isolated the most probable cause as either the acoustic sensor or the signal cables in the drywell. These components are located in the inert drywell and cannot be accessed while the unit is at power.

Repairs to the "L" acoustic monitor will be made during the next refueling outage, RF15, currently scheduled for April of 2009, or during the next forced outage of sufficient duration to allow containment de-inerting, drywell entry and acoustic monitoring troubleshooting and repair.

There are no regulatory commitments in this report.

Should you have any questions concerning this letter, please contact Philip J. Duca at (856) 339-1640.

Sincerely, John F, Perry Plant Manager - Hope Creek -

95-2168 REV. 7/99

Page 2 Document Control Desk LR-N08-0164 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625