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Event Notification Report for February 20, 2004

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/19/2004 - 02/20/2004

EVENT NUMBERS
4053340534

Power Reactor
Event Number: 40533
Facility: PALO VERDE
Region: 4     State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN MARKS
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/20/2004
Notification Time: 13:00 [ET]
Event Date: 02/20/2004
Event Time: 10:33 [MST]
Last Update Date: 02/20/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JACK WHITTEN (R4)
TERRY REIS (NRR)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
OFFSITE NOTIFICATION DUE TO A PRESS RELEASE CONCERNING THE UNIT 2 SHUTDOWN

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the Information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"This ENS notification is to inform the agency of the shutdown of Palo Verde Nuclear Generating Station Unit 2, due to increasing primary to secondary leakage, for which a news release has been issued.

"Unit 2 was shutdown to Mode 3 on February 19, 2004 at 18:28 Mountain Standard Time (MST) following detection of increased primary to secondary leakage at approximately 15:22 MST. The leakage was less than the Technical Specification 3.4.14(d) limit of 150 gallons per day through any one SG. Steam generator #1 was isolated at approximately 18:40 MST. The unit has been cooled down to Mode 5 in preparation of maintenance to repair the steam generator. Current plant conditions are approximately 160 degrees F and 350 psia.

"The decision to issue a press release was made at approximately 09:00 MST on February 20, 2004. The press release was issued at approximately 10:33 MST.

"The NRC Resident Inspector has been notified of this ENS call."

This is the 1st cycle using these Steam Generators which were replaced in 2003. The licensee indicated that the change in in primary to secondary leakage was a step increase but was unable to accurately quantify the amount since it was less than 20 gallons per day.


Power Reactor
Event Number: 40534
Facility: ROBINSON
Region: 2     State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: MARTY ARNOLD
HQ OPS Officer: MIKE RIPLEY
Notification Date: 02/21/2004
Notification Time: 02:04 [ET]
Event Date: 02/20/2004
Event Time: 23:20 [EST]
Last Update Date: 02/21/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRIAN BONSER (R2)
Power Reactor Unit Info
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
EMERGENCY RESPONSE FACILITY INFORMATION SYSTEM INOPERABLE

"At 2220 hours EST, on February 20, 2004, the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Emergency Response Facility Information System (ERFIS) computer system became inoperable. The ERFIS computer system provides monitoring and communications capability for plant data systems including the Emergency Response Data System (ERDS), Safety Parameter Display System (SPDS), Meteorological Data link system, FAX modems for Emergency Preparedness functions, and the Inadequate Core Cooling Monitor (ICCM). Actions were completed to restore the ERFIS computer system to an operable status at 0053 hours on February 21, 2004. The loss of ERFIS requires alternate methods, as described in plant procedures, to be used for the above described functions. Therefore, it is expected that appropriate assessment of plant conditions, notifications, and communications could still have been made, if required, during the time that the ERFIS computer system was inoperable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. As previously stated, alternate means remained available to assess plant conditions, make notifications, and accomplish required communications, as necessary."

The licensee notified the NRC Resident Inspector.