Event Notification Report for August 22, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/21/2003 - 08/22/2003
EVENT NUMBERS
40098400954010640108
Power Reactor
Event Number: 40098
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: JEFF GARDINER
HQ OPS Officer: MIKE RIPLEY
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: JEFF GARDINER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 08/22/2003
Notification Time: 13:23 [ET]
Event Date: 08/22/2003
Event Time: 02:34 [PDT]
Last Update Date: 08/22/2003
Notification Time: 13:23 [ET]
Event Date: 08/22/2003
Event Time: 02:34 [PDT]
Last Update Date: 08/22/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (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 |
REACTOR CORE ISOLATION COOLING SYSTEM INOPERABLE
"This ENS notification is made to report that on August 22, 2003 at 02:34 PDT Reactor Core Isolation Cooling was isolated due to the discovery of a degraded pilot cell in the Division 1 250 VDC battery. Operators isolated the steam inlet valve to the RCIC turbine (RCIC-V-1) because the minimum flow bypass valve, RCIC-V-19, (a primary containment isolation valve) was declared inoperable and isolated to comply with the plant TS. Isolation of RCIC-V-1 effectively removed RCIC from service since it is the containment isolation valve.
"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)."
The licensee will be notifying the NRC Resident Inspector.
"This ENS notification is made to report that on August 22, 2003 at 02:34 PDT Reactor Core Isolation Cooling was isolated due to the discovery of a degraded pilot cell in the Division 1 250 VDC battery. Operators isolated the steam inlet valve to the RCIC turbine (RCIC-V-1) because the minimum flow bypass valve, RCIC-V-19, (a primary containment isolation valve) was declared inoperable and isolated to comply with the plant TS. Isolation of RCIC-V-1 effectively removed RCIC from service since it is the containment isolation valve.
"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)."
The licensee will be notifying the NRC Resident Inspector.
Power Reactor
Event Number: 40095
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE FULLER
HQ OPS Officer: RICH LAURA
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE FULLER
HQ OPS Officer: RICH LAURA
Notification Date: 08/22/2003
Notification Time: 04:05 [ET]
Event Date: 08/22/2003
Event Time: 02:59 [EDT]
Last Update Date: 08/22/2003
Notification Time: 04:05 [ET]
Event Date: 08/22/2003
Event Time: 02:59 [EDT]
Last Update Date: 08/22/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
TURBINE TRIP CAUSES AUTOMATIC REACTOR SCRAM AT OYSTER CREEK
The licensee reported that an automatic reactor scram occurred at 0259 due to a turbine generator trip from a hi-hi moisture separator water level. One control rod indicated position 02; however, the remainder of the control rods indicated full in. All other systems and components functioned as designed. The licensee is cooling the plant down to cold shutdown.
The licensee notified the NRC Resident Inspector.
The licensee reported that an automatic reactor scram occurred at 0259 due to a turbine generator trip from a hi-hi moisture separator water level. One control rod indicated position 02; however, the remainder of the control rods indicated full in. All other systems and components functioned as designed. The licensee is cooling the plant down to cold shutdown.
The licensee notified the NRC Resident Inspector.
Other Nuclear Material
Event Number: 40106
Rep Org: US AIR FORCE
Licensee: US AIR FORCE
Region: 4
City: Vance AFB State: OK
County:
License #: 42-23539-09AF
Agreement: Y
Docket:
NRC Notified By: MAJOR CRAIG REFOSCO
HQ OPS Officer: BILL GOTT
Licensee: US AIR FORCE
Region: 4
City: Vance AFB State: OK
County:
License #: 42-23539-09AF
Agreement: Y
Docket:
NRC Notified By: MAJOR CRAIG REFOSCO
HQ OPS Officer: BILL GOTT
Notification Date: 08/27/2003
Notification Time: 11:10 [ET]
Event Date: 08/22/2003
Event Time: 00:00 [CDT]
Last Update Date: 08/27/2003
Notification Time: 11:10 [ET]
Event Date: 08/22/2003
Event Time: 00:00 [CDT]
Last Update Date: 08/27/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
MICHAEL RUNYAN (R4)
DOUG BROADDUS (NMSS)
MICHAEL RUNYAN (R4)
DOUG BROADDUS (NMSS)
MISSING EXIT SIGN CONTAINING TRITIUM
On 08/22/03, while reviewing documentation following construction, personnel at Vance Air Force Base discovered that an exit sign containing 20 Curies of Tritium was misplaced. The sign was to be replaced with an electric sign. The construction occurred in late June 03. Personnel are conducting a search for the sign. It may have been disposed of in the regular trash.
On 08/22/03, while reviewing documentation following construction, personnel at Vance Air Force Base discovered that an exit sign containing 20 Curies of Tritium was misplaced. The sign was to be replaced with an electric sign. The construction occurred in late June 03. Personnel are conducting a search for the sign. It may have been disposed of in the regular trash.
Power Reactor
Event Number: 40108
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GARY INGRAM
HQ OPS Officer: ARLON COSTA
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GARY INGRAM
HQ OPS Officer: ARLON COSTA
Notification Date: 08/27/2003
Notification Time: 15:41 [ET]
Event Date: 08/22/2003
Event Time: 02:01 [CDT]
Last Update Date: 08/27/2003
Notification Time: 15:41 [ET]
Event Date: 08/22/2003
Event Time: 02:01 [CDT]
Last Update Date: 08/27/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MICHAEL RUNYAN (R4)
MICHAEL RUNYAN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID ACTUATION OF THE "A" STANDBY SERVICE WATER SYSTEM
"On August 22,2003, at 0201 Central Time, while operating at 100 percent power, Grand Gulf Nuclear Station experienced an invalid actuation of the 'A' Standby Service Water (SSW) System. A failed DC/DC converter power supply in Panel 1H22P400 for the Division 1 Diesel Generator (DG) resulted in a faulty DG speed monitor signal indicating DG speed greater than 450 revolutions per minute (RPM). The DG was not running since it was already inoperable due to a planned outage. The event occurred during restoration activities to prepare the DG for retest. The invalid DG start signal caused the outside air fan and SSW 'A' to auto start as designed to support DG operation. SSW 'A' started and functioned as designed. No other actuations occurred and all support systems functioned properly."
The licensee notified the NRC Resident Inspector.
"On August 22,2003, at 0201 Central Time, while operating at 100 percent power, Grand Gulf Nuclear Station experienced an invalid actuation of the 'A' Standby Service Water (SSW) System. A failed DC/DC converter power supply in Panel 1H22P400 for the Division 1 Diesel Generator (DG) resulted in a faulty DG speed monitor signal indicating DG speed greater than 450 revolutions per minute (RPM). The DG was not running since it was already inoperable due to a planned outage. The event occurred during restoration activities to prepare the DG for retest. The invalid DG start signal caused the outside air fan and SSW 'A' to auto start as designed to support DG operation. SSW 'A' started and functioned as designed. No other actuations occurred and all support systems functioned properly."
The licensee notified the NRC Resident Inspector.