| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/13/2007 - 04/16/2007 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 43238 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: SARA ANDERSON
HQ OPS Officer: JASON KOZAL | Notification Date: 03/14/2007
Notification Time: 20:36 [ET]
Event Date: 03/14/2007
Event Time: 14:55 [EDT]
Last Update Date: 04/13/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
CHRIS HOTT (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 HPCI DECLARED INOPERABLE
"During performance of a Unit 2 High Pressure Coolant Injection System (HPCI) Pump, Valve, Flow and Unit Cooler Functional and In-service Test, the High Pressure Coolant Injection System (HPCI) was declared inoperable. The inoperability is due to failure of AO-2-23-042 "HPCI Steam Line Drain Inboard Isolation to Main Condenser" to open. The AO-2-23-042 is normally open and its passive safety function is to remove any steam condensation from the HPCI pump turbine steam supply line. HPCI is a single train safety system rendered inoperable by this condition."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION RECEIVED FROM DAVID FOSS TO JOE O'HARA AT 1431 ON 4/13/07 * * *
"The purpose of this notification is to retract a previous report made on 3/14/07 at 2036 hours (EN# 43238). Notification of this issue to the NRC on 3/14/07 was initially made as a result of the discovery of a failure of AO-2-23-042 'HPCI Steam Line Drain Inboard Isolation to Main Condenser' to open. This condition was discovered during performance of a routine Unit 2 High Pressure Coolant Injection System (HPCI) Pump, Valve, Flow and Unit Cooler Functional and In-Service Test. Failure of this valve to open results in water condensing in the HPCI steam supply line. HPCI had already been considered inoperable since approximately 0934 hours on 3/14/07 as a result of the performance of the test. Repairs were made to the AO-2-23-042 valve and HPCI was returned to an operable status by 2205 hours (IR 603918).
"Since the initial report, it has been determined that this condition is not reportable. HPCI was declared inoperable as a result of the performance of the surveillance test and therefore, the HPCI system inoperability was considered a planned evolution. In accordance with NUREG-1022, reporting of planned inoperabilities are not required to be reported unless a condition is discovered that could have prevented the system from performing its function. Water entering the HPCI steam supply piping only occurred as a result of the performance of the surveillance test and could not have caused HPCI to be inoperable during non-test conditions. The AO-2-23-042 is normally open when HPCI is required to be operable and its passive open safety function is to remove any steam condensation from the HPCI pump turbine steam supply line. The active safety function of the valve is to close on design basis events involving the initiation of HPCI. The passive open safety function is not required when the HPCI system is inoperable for testing. The active safety function was unaffected by this condition.
"The NRC resident has been informed of the retraction."
Notified the R1DO(Krohn). |
| General Information or Other | Event Number: 43296 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: ALLEGHENY RODNEY
Region: 1
City: NEW BEDFORD State: MA
County:
License #: 15-7052
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/11/2007
Notification Time: 14:23 [ET]
Event Date: 03/27/2007
Event Time: [EDT]
Last Update Date: 04/11/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL PERRY (R1)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE REPORT - MALFUNCTIONING SHUTTER
The State provided the following information via facsimile:
The licensee uses a Themo Electron Model SR-U2 device, serial number 1179BC, to measure thickness. The device contains a Sr-90 50 millicurie source. On 03/27/07 the gauge shutter stuck open. The unit was secured by restricting access to the one door that leads to the area where the gauge is located. The gauge vendor has been called. On 03/30/07, a contractor, RSI, came in to repair the broken spring on the gauge. |
| General Information or Other | Event Number: 43297 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: ALLEGHENY RODNEY
Region: 1
City: NEW BEDFORD State: MA
County:
License #: 15-7052
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/11/2007
Notification Time: 15:02 [ET]
Event Date: 04/10/2007
Event Time: [EDT]
Last Update Date: 04/11/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL PERRY (R1)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE REPORT - MALFUNCTIONING GAUGE SHUTTER
The State provided the following information via facsimile:
The licensee uses a Themo Electron Model SR-U2 device, no serial number provided, to measure thickness. The device contains a Sr-90 50 millicurie source. On 04/10/07, the licensee left a phone message that the gauge shutter stuck closed [Different gauge than reported in EN #43296]. A contractor has been called to fix the gauge. |
| Fuel Cycle Facility | Event Number: 43303 | Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PIKETON State: OH
County: PIKE
License #: GDP-2
Agreement: Y
Docket: 0707002
NRC Notified By: ERIC R. SPAETH
HQ OPS Officer: JOHN MacKINNON | Notification Date: 04/15/2007
Notification Time: 23:30 [ET]
Event Date: 04/15/2007
Event Time: 09:30 [EDT]
Last Update Date: 04/16/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
JOEL MUNDAY (R2)
ABY MOHSENI (FSME)
| Event Text SAFETY SYSTEM ACTUATION - AUTOCLAVE HIGH CONDENSATE LEVEL ALARM RECEIVED DURING HEATUP
"At 0930 hours, Autoclave (AC) # 2 in the X-344 Facility experienced a Steam Shutdown due to high condensate level alarms (A) and (B) actuating. The AC was in applicable TSR Mode II 'Heating' for 45 minutes when the actuation occurred. This is considered a valid actuation of a 'Q' Safety System. The autoclave was placed in MODE IV 'Shutdown' and declared inoperable by the Plant Shift Superintended (PSS). An investigation is underway to determine the cause of the actuation. No release of radioactive material occurred as a result of the incident. This event is being reported in accordance with UE2-RA-RE1030 Appendix D. J. 2. Safety Equipment Actuation."
The NRC was notified of this by the licensee. | |