| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/14/2004 - 12/15/2004 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41224 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [ ] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID OAKES
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/24/2004
Notification Time: 20:01 [ET]
Event Date: 11/24/2004
Event Time: 12:20 [MST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JEFFERY CLARK (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 ECCS LOOPS DECLARED INOPERABLE IN SUPPORT OF LOG TERM ACCIDENT MITIGATION
"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.
"On November 24, 2004, at approximately 12:20 Mountain Standard Time (MST), Palo Verde Nuclear Generating Station Unit 3 was operating at 0% power at approximately normal operating temperature and pressure when 3 of the 4 ECCS injection check valves were identified to be in a degraded condition. While performing normal torque verifications on the bonnet bolts for these check valves, it was identified that the graphoil seals were degraded in that the seal material had extruded past the retaining ring. Although there was no evidence of actual leakage associated with these valves, the long term integrity of the valves during post accident operation could not be assured. As a result, the Operators conservatively declared both trains of ECCS inoperable per LCO 3.5.3 and 3 of 4 Safety Injection Tanks inoperable per LCO 3.5.1, requiring entry into LCO 3.0.3. Operations also declared both RCS loops inoperable per LCO 3.4.5. A cooldown and depressurization of the RCS is in progress to Mode 5.
"Unit 3 was preparing for Mode 2 entry following a refueling outage when the degraded check valve seals were identified.
"Engineering continues to evaluate this condition.
"There were no RPS/ESF actuations, and none were required.
"There were no structures, systems or components that were inoperable at the start of event that contributed to the event.
"This condition did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. This condition did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified of this condition and this ENS notification."
* * * RETRACTION FROM DAN MARKS TO BILL HUFFMAN AT 14:52 EST ON 12/14/04 * * *
"Engineering has determined that these RCS PIV's (Pressure Isolation Valves) were always capable of performing their safety function.
"The extrusion of the graphite seal material for the check valves did not affect the capability of the RCS PIV check valves safety function and did not present a danger to the pressure boundary of the RCS. It was estimated that no more than about 5% of the graphite material was extruded. The loss of this small amount of packing material, did not challenge the integrity of the seal. This is based on industry experience and the results of Palo Verde tests. Also, the functionality of the SI check valves disc was not compromised since the internal disc to seat clearances achieved were within the range desired. Nevertheless, the seals for valves SIEV227, 237 & 247 were replaced while in Mode 5 to add additional margin to the joint design.
"LCO 3.0.3 and the other impacted LCO entries (3.4.5, 3.5.1, 3.5.3) were conservative and were not required.
"Therefore, this 10CFR50.72(b)(3)(v)(D) notification, ENS ID # 41224 of 11/24/2004, 20:01 ET, is retracted and no followup LER will be submitted for this event.
"The NRC Resident Inspector has been notified of the retraction and this notification."
R4DO (Pick) notified. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41250 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SUSAN WESTCOTT
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/09/2004
Notification Time: 07:48 [ET]
Event Date: 12/09/2004
Event Time: 02:04 [PST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
LINDA SMITH (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text RPS ACTUATION WHILE SHUTDOWN DUE TO FAILED FUSE
"During performance of Surveillance Testing on Intermediate Range Nuclear detector, a control power fuse blew. The plant was in Mode 3, and received a Reactor Trip signal which opened the Reactor Trip Breakers. All rods were on the bottom prior to the trip signal. Testing of Intermediate Range. Detectors has been suspended pending investigation. The plant remains in Mode 3."
The licensee will inform the NRC resident inspector.
* * * RETRACTION FROM L. PARKER TO M. RIPLEY 2013 EST, 12/14/04 * * *
"This is a retraction of NRC Event # 41250 'RPS Actuation While Shutdown.'
"On December 9, 2004, at 0204 PST, with Unit 2 in Mode 3 (Hot Standby), during testing of Intermediate Range Nuclear Detectors, a control power fuse blew, resulting in an actuation signal, and causing actuation of the Reactor Protection System (RPS). The reactor trip breakers opened, however, since all rods were fully inserted, no rod motion occurred. At 0448 PST, this event was reported as an eight hour non-emergency notification per 10 CFR 50.72 (b)(3) (iv)(A).
"Based on a subsequent review of the event against NUREG-1022 Rev. 2, the actuation was confirmed to be INVALID due to a blown fuse and not an actuation of the intermediate range neutron flux detector.
"Furthermore, with the unit in Mode 3 with all rods on the bottom, the RPS actuation had no effect, as the safety function had already been completed.
"Therefore, the event is not reportable under 10 CFR 50.72 or 10 CFR 50.73, and the event notification is retracted."
The licensee notified the NRC Resident Inspector. Notified R4 DO (G. Pick) |
| General Information or Other | Event Number: 41251 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: GROUND ENGINEERING CONSULTANTS
Region: 4
City: DENVER State: CO
County:
License #: 586-01
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/10/2004
Notification Time: 15:35 [ET]
Event Date: 12/10/2004
Event Time: 07:06 [MST]
Last Update Date: 12/10/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA SMITH (R4)
TOM ESSIG (NMSS)
| Event Text COLORADO AGREEMENT STATE REPORT - LOST SOURCE FROM A TROXLER MOISTURE DENSITY GAUGE
Colorado Department of Public Health and Environment received a report from a licensee, Ground Engineering Consultants, that they had possibly lost a Model 3440 Troxler Moisture Density Gauge containing an 8 milliCurie Am: Be source and an 8 milliCurie Cs-137 source. The technician transporting the gauge failed to properly secure the gauge in the back of his vehicle.
When the technician discovered the gauge missing, he backtracked and found pieces of the gauge on Arapahoe Road in metropolitan Denver. At the time of discovery, the licensee determined that the sources were intact in the shielding base on radiation surveys. Upon further investigation, it was discovered that the Cs-137 source was missing.
The licensee and technicians from the State of Colorado are currently searching the area for the lost source. The State of Colorado will provide an update on the results of the search.
* * * UPDATE FROM STROUD TO CROUCH ON 12/10/04 @ 1744 HRS EST * * *
Colorado Department of Public Health and Environment (CDPHE) informed the Operations Center that attempts to locate the missing source have proven unsuccessful. CDPHE Public Affairs has issued a press release to inform the public of the missing source and how to proceed if the source was found. CDPHE will provide an update to this event as necessary.
Notified R4DO (Smith), NMSS EO (Giitter), HQPAO (Burnell and Brenner). R4PAO (Dricks) and DHS.. |
| Power Reactor | Event Number: 41257 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: SCOTT MEIER
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/14/2004
Notification Time: 12:45 [ET]
Event Date: 12/14/2004
Event Time: 11:45 [EST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ROBERT HAAG (R2)
TERRY REIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR MANUALLY TRIPPED DUE TO FIRE ON UNIT 3 HP TURBINE
" U3 manually tripped (Shift Manager decision). Fire in U3 HP turbine near bearing housing (offsite assistance not required). All plant equipment functioned as designed."
A fire broke out near the #2 bearing housing on Unit 3 HP turbine and lasted about 9 minutes in length. Exact character of fire was not available at time of reporting. No unusual vibration readings or visual indications were observed prior to fire. Onsite fire brigade personnel responded to the turbine area without assistance of offsite emergency personnel. Five minutes into the event Unit 3 reactor was manually tripped. Nine minutes into the event, shift supervisor declared the fire was out. Fire personnel indicated the fire was "easily" put out. Licensee is evaluating action to be taken.
When Unit 3 reactor was manually tripped, all rods inserted fully. No primary or secondary power relief valves actuated. AFW activated as expected. Licensee chose to close the MSIV to slow down the cooldown rate. Presently, decay heat is being removed via the steam dump into the atmosphere.
Fire did not affect operational ability of Unit 4 or cause instability on the electrical grid.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41258 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BOB MURELL
HQ OPS Officer: MIKE RIPLEY | Notification Date: 12/14/2004
Notification Time: 14:55 [ET]
Event Date: 12/13/2004
Event Time: 15:12 [CST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
ROGER LANKSBURY (R3)
JOHN HICKEY (NMSS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 94 | Power Operation | 94 | Power Operation | Event Text CRITICALITY MONITORING DOSIMETERS NOT CONFIGURED CORRECTLY
"On December 13, 2004, in preparations for new fuel receipt inspection activities, it was determined that the Electronic Dosimeters (Eds) that were previously used to meet criticality monitoring requirements of 10 CFR 70.24, were not configured correctly. Specifically, the dose rate alarm function of the Eds had been disabled. It is unknown at this time if the Eds had previously been used in this in-correct configuration during two previous new fuel receipt inspection activities. Based on the potential that the requirements of part 70.24 were not met, this event is being reported pursuant of part 70.50(b)(2), 'An event in which equipment is disabled or fails to function as designed.'"
The Electronic Dosimeters were immediately re-configured correctly and new fuel receipt inspection activities will recommence. The licensee notified the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 41259 | Rep Org: NATIONAL RESPONSE CENTER
Licensee: ROZELL TESTING LABORATORIES
Region: 3
City: SPRINGFIELD State: MO
County:
License #: 24-32438-01
Agreement: N
Docket:
NRC Notified By: MS. CRUZ
HQ OPS Officer: MIKE RIPLEY | Notification Date: 12/14/2004
Notification Time: 17:10 [ET]
Event Date: 12/14/2004
Event Time: 15:45 [CST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
ROGER LANKSBURY (R3)
MELVYN LEACH (NMSS)
| Event Text DAMAGED TROXLER MOISTURE DENSITY GAUGE
The National Response Center reported that the licensee reported to them that a moisture density gauge was run over by a bulldozer at a construction site in Springfield, MO and that the area had been isolated.
In contacting the licensee, the RSO stated that the extent of damage to the gauge (Model 3440 Troxler 8 mCi Cs-137 and 40 mCi Am-241:Be) was as of yet unknown. The licensee plans on requesting local fire department Haz Mat Team assistance in performing surveys and will contact Troxler for information on recovering and returning the gauge. The licensee will be providing an update with additional details and status.
* * * UPDATE FROM E. HODGE (RSO) TO M. RIPLEY 2013 EST, 12/14/04 * * *
The licensee reported that the Springfield, MO Fire Department responded to the construction site, assisted in returning the damaged gauge to its transportation case, and performed a radiation survey of the gauge and the area where it was damaged. No area contamination or apparent source leakage was noted. The area has been cleared for access, and the gauge is being returned to the licensee's laboratory in Branson, MO where source leak testing will be performed prior to shipment to the manufacturer.
Notified R3 DO (Lanksbury) and NMSS EO (Leach). |
| Power Reactor | Event Number: 41260 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MATTHEW MINNICK
HQ OPS Officer: BILL HUFFMAN | Notification Date: 12/14/2004
Notification Time: 20:03 [ET]
Event Date: 12/14/2004
Event Time: 18:43 [EST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KENNETH JENISON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OSWEGO COUNTY PROMPT NOTIFICATION SYSTEM OUT OF SERVICE FOR GREATER THAN ONE HOUR
"Notified by [deleted] of the Oswego County Warning Point that the tone alert system (prompt notification system) was out of service for more than one hour as of 18:43 on 12/14/04. This requires a notification to the NRC for a major loss of notification capability in accordance with 10CFR50.72. The notification [from the County Warning Point] occurred on 12/14/04 at 19:07 via the RECS line (Radiological Emergency Communications System). Route Alert has been verified available [as backup to the tone alert system] and actions to restore [the tone alert system] are in progress."
The licensee states that the malfunction on the prompt notification system only rendered the tone alert radio system inoperable. The emergency sirens are not affected.
The licensee has notified the NRC Resident Inspector and Oswego County authorities. The licensee has also notified the Fitzpatrick nuclear power plant.
* * * UPDATE FROM NINE MILE POINT (D. MOORE) TO NRC (HUFFMAN) AT 23:06 EST ON 12/14/04 * * *
The prompt notification tone alert system was restored to operable at 21:45 EST on 12/14/04. Fitzpatrick and Oswego county are informed. |
| Power Reactor | Event Number: 41261 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID SPINDLER
HQ OPS Officer: MIKE RIPLEY | Notification Date: 12/14/2004
Notification Time: 23:22 [ET]
Event Date: 12/14/2004
Event Time: 18:43 [EST]
Last Update Date: 12/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KENNETH JENISON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OSWEGO COUNTY PROMPT NOTIFICATION SYSTEM OUT OF SERVICE FOR GREATER THAN ONE HOUR
"Oswego County Prompt Notification System was out of service greater than 1 hour. Time out of service 12/14/03 at 1843 [EST]. Time returned to service 12/14/04 at 2305 [EST]."
The licensee notified the NRC Resident Inspector. | |