| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/20/2004 - 02/23/2004 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40457 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: AUTHOR LEWIS
HQ OPS Officer: GERRY WAIG | Notification Date: 01/19/2004
Notification Time: 15:31 [ET]
Event Date: 01/19/2004
Event Time: 11:20 [EST]
Last Update Date: 02/20/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JULIO LARA (R3)
DAVID MATTHEWS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text CERTAIN PLANT DOORS MAY NOT BE ABLE TO WITHSTAND PRESSURE CREATED BY MAIN STEAM LINE BREAK
"On January 19, 2004, during on-going analysis of the effects of a Main Steam Line Break using new computer models, an issue was raised involving the capability of plant doors. Specifically, the preliminary analysis for a Main Steam Line Break in the Turbine Building determined that certain doors may not be able to withstand the initial pressure wave caused by a guillotine break of the main steam line.
"The preliminary analysis indicates that a pressure wave of approximately 2.7 psi is generated from such a main steam line break, which is more than the capability of several doors isolating safety-related equipment from the Turbine Building. The forces generated from this pressure wave could cause failure of the doors leading to both trains of low voltage switchgear, and the resultant steam environment could potentially render all low voltage AC equipment as well the station batteries inoperable. One train of the high voltage switchgear equipment could also be affected due to failure of the door leading to this room.
"Due to the potential loss of both trains of low voltage electrical distribution as a result of a steam line break, this issue is being reported as a non-emergency, 8-hour report in accordance with 10CFR50.72(b)(3)(ii)(B), a condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. Current steam line pressures are low enough such that all doors are capable of withstanding any forces resulting from a steam line break. Engineering evaluation of the issue is continuing."
The NRC Resident Inspector has been notified of this issue by the licensee. The licensee also plans to make a media/press release regarding this issue.
*** UPDATE ON 02/20/04 AT 1022 EST FROM LARRY MYERS TO JEFF ROTTON ***
"Further review and evaluation of this issue has determined that the pressure wave from a main steam line break in the Turbine Building results in pressures of less than 1.0 psi. Therefore, the affected doors would be able to withstand this pressure wave with one exception. The one exception is the door to a High Voltage Switchgear Room, which is different from the other doors in that it opens into the Switchgear Room and therefore has a very low capability to withstand a positive pressure in the Turbine Building. However, additional analysis determined that in the event of a main steam line break and possible failure of the door, the resultant environment in the room (i.e., temperature, pressure, and humidity) would be within the capability of the enclosed equipment, and equipment operability would not have been challenged.
"Accordingly, this issue is no longer considered an unanalyzed condition that would have significantly degraded plant safety, and therefore the notification made per 10CFR50.72(b)(3)(ii)(B) is retracted."
Notified R3O (Gardner) and NRR EO (Reis) |
| General Information or Other | Event Number: 40526 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: IRWIN INDUSTRIAL TOOL COMPANY
Region: 4
City: DeWitt State: NE
County:
License #: GL0158
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: ARLON COSTA | Notification Date: 02/17/2004
Notification Time: 15:30 [ET]
Event Date: 02/04/2004
Event Time: [CST]
Last Update Date: 02/17/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JACK WHITTEN (R4)
ROBERTO TORRES (NMSS)
| Event Text AGREEMENT STATE (NE) NOTIFICATION OF LOST TRITIUM SOURCES
The licensee reported that upon an inventory check in early February 2004, two general licensed self-luminous exit signs were missing and are currently unaccounted for. The two units were purchased from SRB Technologies, Inc (serial #'s 18132 and 16138) containing 24 curies of activity each as assayed in May of 1985. These exit signs were purchased and installed in 1985 and were removed and held in storage since 1990. The licensee has concluded that the exit signs were unintentionally disposed of or misplaced and thrown away during a clean-up of inventory from their change of ownership to Newell Rubbermaid Inc. Efforts of locating and recovering these units have been unsuccessful. The remaining five signs were placed in a single container and stored in a locked fireproof cabinet for subsequent transfer to their respective manufacturers for proper disposal. |
| 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)
|
| 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)
|
| 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. |
| Power Reactor | Event Number: 40535 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDAN Robinson
HQ OPS Officer: RICH LAURA | Notification Date: 02/21/2004
Notification Time: 12:06 [ET]
Event Date: 02/21/2004
Event Time: 10:05 [EST]
Last Update Date: 02/21/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PAMELA HENDERSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 80 | Power Operation | 80 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION OF MEDICAL EVENT AT SUSQUEHANNA
"At 10:05 AM PST, the Susquehanna LLC Shift Manager was notified that a member of the general public required medical assistance. The individual was at a company owned public recreation area adjacent to the Susquehanna LLC River Intake access road. The recreation area is outside the protected area. An ambulance was called to the scene, arriving at 10:28 and leaving at 10:52. The individual was transported to a local hospital. The LLEA and PEMA were notified of the incident."
The NRC Resident Inspector was notified. |
| Power Reactor | Event Number: 40536 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JAMES REDDY
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/21/2004
Notification Time: 15:48 [ET]
Event Date: 02/21/2004
Event Time: 08:41 [PST]
Last Update Date: 02/21/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JACK WHITTEN (R4)
|
| 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 RCIC SYSTEM INOPERABLE DUE TO POSSIBLE UNDERVOLTAGE RELAY FAILURE
"This ENS notification is made to report that on February 21, 2004 at 0841 PST Reactor Core Isolation Cooling was rendered inoperable due to RCIC-V-13 (RPV injection valve) motor operator losing power. Preliminary investigation indicates the undervoltage relay may have failed, resulting in a loss of control power for the valve and loss of valve position indication.
"The event is considered reportable to the NRC under 10 CFR 50.72(b)(3)(v)(D) based on guidance contained in NUREG 1022, "Event Reporting Guidelines," and NRC Regulatory Issue Summary (RIS) 2001-14, 'Position on Reportability Requirements for Reactor Core Isolation Cooling System Failure.' A follow-up LER will be issued under 10 CFR 50.73(a)(2)(v)(D)."
This event placed the plant in technical specifications LCO 3.5.3 which has a 14 day duration.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40537 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BARRY HEDRICK
HQ OPS Officer: RICH LAURA | Notification Date: 02/22/2004
Notification Time: 18:42 [ET]
Event Date: 02/22/2004
Event Time: 15:10 [EST]
Last Update Date: 02/22/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
PAMELA HENDERSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL SCRAM AT PEACH BOTTOM 2 DUE TO DECREASING CONDENSER VACUUM
"Peach Bottom Unit 2 reactor was manually scrammed due to degrading main condenser vacuum. The reactor was manually scrammed prior to reaching the automatic scram setpoint. All plant systems responded as expected with no significant issues noted. A Group II and Group III Primary Containment Isolation was received due to reactor water level passing through 1 inch. All isolation systems responded as required and repositioned to their expected positions."
The licensee also indicated that all control rods properly inserted into the core. The method of decay heat removal was using the main condenser. The licensee initiated a post scram review to identify and correct the source of degrading vacuum. The licensee also indicated the manual scram was initiated at 25 inches and lowering of condenser vacuum.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40538 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JIMMY BURGESS
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/22/2004
Notification Time: 19:02 [ET]
Event Date: 02/22/2004
Event Time: 17:30 [EST]
Last Update Date: 02/22/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN BONSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text UNIT 1 MANUALLY TRIPPED AFTER THE "B" SG FEEDWATER ISOLATION VALVE FAILED CLOSED
"The 1CF-42B (1B Steam Generator Feedwater Isolation Valve) failed closed with Unit 1 at 100% power. Operators performed a manual reactor trip as required by 'Loss of Normal Steam Generator Feedwater Supply', AP-06. Emergency procedures were utilized to respond and stabilize Unit 1 in mode 3. The plant is currently stable in mode 3 at normal operating pressure and temperature. Currently, steam generator levels are being maintained using the auxiliary feedwater system. Other than the failure of 1CF-42B (Initiating Event), all plant safety systems operated as required."
No primary or secondary safeties or reliefs lifted during the transient. All control rods fully inserted. The main condenser is in-service to remove decay heat. The licensee had identified a problem with the hydraulic motor associated with 1CF-42B and was in the process of developing corrective actions before the failure.
The licensee will inform both state/local agencies (courtesy notification) and has informed the NRC resident inspector. | |