Power Reactor Event Number: 41525
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD DESANCTIS
HQ OPS Officer: WESLEY HELD
Notification Date: 03/25/2005
Notification Time: 01:53 [ET]
Event Date: 03/24/2005
Event Time: 20:15 [EST]
Last Update Date: 03/25/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN ROGGE (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 DESIGN BASIS

The following information was obtained from the licensee via facsimile (licensee text in quotes):

"This is an 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 10CFR50.72. An event or condition that could have prevented mitigating the consequences of an accident.

"On 03/24/05 at 2015 operators discovered that a closed manual discharge valve for the positive displacement charging pump was leaking through allowing Reactor Coolant System to leak back to the refueling water storage tank. The leakage was 0.34 gallons per minute. This leakage is greater than the UFSAR limit for ECCS leakage outside containment.

"With leakage greater than the UFSAR allowed limits (greater than 3800 cc/hr), GDC-19 limits for control room habitability cannot be assured.

"Actions were taken and the leakage was stopped at 2040. The affected positive displacement charging pump is not a safety related pump and is not required for accident mitigation; however it is in the ECCS recirculation flow path during the cold leg injection phase of the accident mitigation.

"The licensee will notify the NRC Resident Inspector of this event."

The licensee will be notifying local authorities. The licensee reported that the event had no impact on Unit 1.

Power Reactor Event Number: 41530
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ART BREADY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2005
Notification Time: 00:35 [ET]
Event Date: 03/27/2005
Event Time: 22:00 [EST]
Last Update Date: 03/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
JOHN ROGGE (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Startup 0 Startup

Event Text

PLANT SHUTDOWN TO REPAIR SMALL REACTOR COOLANT SYSTEM LEAK

The following information was obtained from the licensee via facsimile (licensee text in quotes):

"While in OPCON 2 with the Main Turbine secured, Hope Creek personnel performed a Primary Containment entry to determine the source of slightly elevated unidentified leakage. This leakage has slowly trended up since plant start-up in February to approximately 0.73 gpm. With the current unidentified leak rate at 0.436 gpm, personnel identified a steam leak from an insulated decontamination port, sealed via a bolted flange, within the isolable boundary of the 'B' Reactor Recirculation pump. This was the only source of reactor coolant system leakage identified although some minor leakage (totaling approximately 250ml/min) from two drywell recirculation fans was also identified. This is a voluntary/courtesy Emergency Notification System (ENS) notification that Hope Creek is proceeding to Cold Shutdown to precisely identify and repair the leakage source. At the time of this notification, Hope Creek Generating Station is in OPCON 3 with plant cooldown in process."

The licensee reported this event under 10 CFR 50.72(b)(2) as a 4-Hour Non-Emergency Voluntary notification