| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/29/2008 - 09/02/2008 ** EVENT NUMBERS ** |
 | Fuel Cycle Facility | Event Number: 44448 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: JOE BARLETTO
HQ OPS Officer: PETE SNYDER | Notification Date: 08/28/2008
Notification Time: 17:35 [ET]
Event Date: 08/28/2008
Event Time: 11:43 [CDT]
Last Update Date: 08/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
OTHER UNSPEC REQMNT
| Person (Organization):
REBECCA NEASE (R2)
NADER MAMISH (NMSS)
| Event Text LEAK IN HIGH PRESSURE FIRE WATER SYSTEM
"At 1143, on 8/28/08, the Plant Shift Superintendent was notified of a large water leak on High Pressure Fire Water system (HPFW) A-12 in building C-333 due to a piping rupture. The HPFW system provides water for fire suppression to the plant's process buildings. A-12 is 1 of 66 HPFW systems in this process building. Leak analysis indicates the HPFW system A-12 would not have been able to perform its intended safety function while the leak was occurring. The leak was determined to be between the process building and the post indicating valve (PIV). The PIV for this system was closed which isolated the leak. Required TSR LCO actions have been and are being performed. This is being reported as an event in which equipment is disabled or fails to function as designed when the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and no redundant equipment is available.
"The NRC Senior Resident Inspector has been notified of this event."
* * * UPDATE PROVIDED BY ROD COOK TO JASON KOZAL ON 8/29/08 AT 1611 * * *
"On 8/29/08, the Kentucky Department of Water (KDOW) was notified that approximately 30,000 gallons of recirculating water (RCW) from the HPFW system containing 4 ppm phosphorus residual was discharged through Outfall 9. RCW discharge to Outfall 9 is reportable to KDOW as a bypass of a treatment system that causes an exceedance of a permit limit per 401 KAR 5:065 Section 1(12)(f).
"The NRC Senior Resident Inspector has been notified of this event."
Notified R2DO (Nease) and NMSS EO (Mamish). |
| Power Reactor | Event Number: 44450 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JOHN STODDARD
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/29/2008
Notification Time: 10:50 [ET]
Event Date: 08/29/2008
Event Time: 10:07 [EDT]
Last Update Date: 08/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
RAY POWELL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION RELATED TO CERTAIN FIRE CONDITIONS
"During an engineering review, a condition was identified in which, under certain fire conditions, possible damage scenarios, and required operator actions, the ability to meet the performance criteria of the approved fire protection program may be challenged. Specifically it was postulated under certain fire conditions affecting the control room, the ability to maintain pressurizer level within the indicated range (high) may be challenged leading to water relief through the pressurizer safety valves. The pressurizer safety valves are not qualified for water relief.
"Compensatory actions to address the risk of fire in areas of concern are in place.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii).
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 44453 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CURTIS DUNSMORE
HQ OPS Officer: PETE SNYDER | Notification Date: 08/30/2008
Notification Time: 17:47 [ET]
Event Date: 08/30/2008
Event Time: 15:03 [EDT]
Last Update Date: 08/30/2008 | 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):
REBECCA NEASE (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text TURBINE ELECTRO-HYDRAULIC CONTROL MALFUNCTION LEADS TO REACTOR SCRAM
"At 1503 hours EDT, an Electro-Hydraulic Control (EHC) system malfunction caused the Unit 2 Main Turbine bypass valves (BPV) to start cycling. Initially, BPV 1 partially opened and closed followed shortly thereafter by four BPVs going full open. At that time the order was given to insert a manual scram. An automatic scram signal occurred just as the operator was beginning to insert the manual scram.
"Preliminary investigation of the automatic scram signal indicates that it was initiated by low Relay Emergency Trip Supply (RETS) pressure to the main turbine control valves due to the EHC malfunction. Reactor water level momentarily dropped below Low Level during the response. This resulted in Primary Containment Isolation System (PCIS) Group 2 and Group 6 isolations, as expected.
"All control rods fully inserted. All systems responded as designed. This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) due to the Reactor Protection System actuation and 10 CFR 50.72(b)(3)(iv)(A) due to the PCIS Group 2 and Group 6 actuations.
"Unit 1 was not affected by this event and remains at 100% power. The NRC resident inspector has been notified." |
| Power Reactor | Event Number: 44454 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: JERRY GRUBB
HQ OPS Officer: VINCE KLCO | Notification Date: 09/01/2008
Notification Time: 00:16 [ET]
Event Date: 08/31/2008
Event Time: 23:00 [CDT]
Last Update Date: 09/01/2008 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
VIVIAN CAMPBELL (R4)
BRIAN McDERMOTT (IRD)
MIKE CHEOK (NRR)
ERIC LEEDS (NRR)
ELMO COLLINS (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text NOTIFICATION OF UNUSUAL EVENT DUE TO HURRICANE WARNING ONSITE
Site declared a notification of unusual event under HU6/ EAL 7. The site is predicted to experience hurricane force winds from Gustav. As a conservative measure, the plant shutdown was completed at 2232 CDT.
The licensee has notified the NRC Resident Inspector, state and local emergency management agencies.
Notified DHS (Hill) and FEMA (Blankenship). |
| Power Reactor | Event Number: 44456 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [ ] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: SUSAN GARDNER
HQ OPS Officer: PETE SNYDER | Notification Date: 09/01/2008
Notification Time: 17:03 [ET]
Event Date: 09/01/2008
Event Time: 10:35 [PDT]
Last Update Date: 09/01/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
VIVIAN CAMPBELL (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 46 | Power Operation | Event Text SHUTDOWN DUE TO EMERGENCY DIESEL GENERATOR SHORTING RING CRACKS
"On September 1, 2008, at about 1035 PDT, Southern California Edison (SCE) began a planned shutdown of San Onofre Unit 3. This shutdown is in anticipation of exceeding the Allowed Outage Time (AOT) of 14 days of Technical Specification 3.8.1 Action B.4 for an inoperable Diesel Generator (Train B). The AOT is due to expire on September 2, 2008 at about 0200. If the system cannot be restored within the allowed outage time, a plant shutdown is required. The initiation of this shutdown is being reported in accordance with 10CFR50.72(b)(2)(i).
"An inspection of the DG generator revealed cracks in the shorting ring, requiring replacement of the generator. Post maintenance testing performed after replacement revealed anomalous readings. SCE determined that problem identification, repair and post test could not be performed before expiration of the AOT. Consequently, shutdown has been initiated.
"At the initiation of the shutdown, SONGS Unit 3 was operating at full power. SONGS Unit 2 is operating at approximately 99 percent power.
"The NRC Resident Inspectors have been briefed on the shutdown plans and will be provided with a copy of this report." | |