Power Reactor

Event Number: 43132

Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BERNIE LITKETT
HQ OPS Officer: STEVE SANDIN

Notification Date: 01/30/2007
Notification Time: 00:49 [ET]
Event Date: 01/29/2007
Event Time: 23:10 [EST]
Last Update Date: 02/01/2007

Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)( iv)(B) - RPS ACTUATION - CRITICAL

Person (Organization) :
CHRISTOPHER CAHILL (R1)

Unit

SCRAM Code

RX CRIT

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

A/R

Y

22

Power Operation

0

Hot Shutdown

AUTOMATIC REACTOR SCRAM ON LOW REACTOR PRESSURE VESSEL (RPV) WATER LEVEL

"On 1/29/07 with Hope Creek reactor startup in progress, in mode 1 at 22% Reactor power, Secondary Condensate Pump Minimum Flow Control Valves began to cycle. Reactor water level reached 39" (RPV level 7) and then lowered to 30" (RPV level 4). Manual control of the Reactor Feed pumps was taken, however, RPV water level continued to lower to 15" (Reactor scram on RPV water level is 12.5") at which time the reactor mode switch was locked in shutdown. There were no ECCS injections and all ECCS systems are operable. Initial review of the event indicates that all systems operated as expected with the exception of the Secondary Condensate pump minimum flow valves and the 'A' IRM failed to insert. Current plant conditions as of 1/30/07 at 0010 are: Hope Creek is in mode 3 at 565 psig. The Main Steam Line Isolation valves are open. 'B' and 'C' Primary Condensate Pumps, 'B' and 'C' Secondary Condensate Pumps, and 'A' Rx Feed Pump are feeding the vessel. All control rods have fully inserted on the scram and Main Turbine Bypass valves are removing decay heat."

The licensee will inform the LAC (Lower Alloways Creek Township) and has informed the NRC Resident Inspector.

* * * UPDATE FROM REED TO HUFFMAN AT 1719 EST ON 2/01/07 * * *

"Based on the post-trip review performed by the licensee, it was determined that the in-service Reactor Feed Pump Minimum Flow Recirculation Valve opened in response to the feed flow adjustments. Reactor vessel level reached the low-level trip set point and an automatic reactor scram occurred. During the event analysis it was determined that the operator initiated the manual scram two seconds after the automatic low level scram occurred. A post event equipment performance review concluded that the Secondary Condensate Pump Minimum Flow Recirculation Valves operated as expected."

The licensee notified the NRC Resident Inspector. The R1DO (Cahill) notified.