United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2004 > October 14

Event Notification Report for October 14, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/13/2004 - 10/14/2004

** EVENT NUMBERS **


41118

To top of page
Power Reactor Event Number: 41118
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICK DESANCTIS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/13/2004
Notification Time: 19:14 [ET]
Event Date: 10/13/2004
Event Time: 15:41 [EDT]
Last Update Date: 10/13/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BRIAN MCDERMOTT (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

REACTOR COOLANT LEAKAGE OUTSIDE CONTAINMENT EXCEEDING FINAL SAFETY ANALYSIS LIMITS

"This is all 8 hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10 CFR 50.72.

"On 10/13/04 at 1541, the control room was notified that tight system isolation boundaries could not be achieved on the 23 Charging pump [positive displacement pump]. The pump was tagged to support maintenance. Although the leak rate has not been quantified, it is suspected that it was greater than the UFSAR limit for ECCS leakage outside containment.

"With leakage greater than the UFSAR allowed limits (greater than 3840 cc/hr), GDC-19 limits for control room habitability cannot be assured.

"Actions have been completed to restore system integrity. The affected positive displacement charging pump is not a safety related pump and is not required for accident mitigation; however it is exposed to the ECCS recirculation flow path during the cold leg injection phase of the accident mitigation.

"The licensee has notified the NRC Resident Inspector of this event. The local township will also be notified."

The licensee stated that the leakage has been isolated; there was no indication of an increase in radiation levels during the leakage; and that the duration of the leakage was approximately 3 hours.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012