| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/28/2005 - 03/29/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41521 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: G.E. HEALTHCARE
Region: 3
City: ARLINGTON HEIGHTS State: IL
County:
License #: IL-01109-01
Agreement: Y
Docket:
NRC Notified By: DARREN PERRERO
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/24/2005
Notification Time: 11:48 [ET]
Event Date: 03/24/2005
Event Time: [CST]
Last Update Date: 03/25/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LAURA KOZAK (R3)
TOM ESSIG (NMSS)
BENJAMIN SANDLER (TAS)
| Event Text MISSING SHIPMENT OF 105 BRACHYTHERAPY (I-125) SEEDS TOTALING 66 MILLICURIES
GE Healthcare, also known as Medi Physics, reported that a package of radioactive material had not been received as expected by Northwest Arkansas Medical Center in Springdale, Arkansas. The package, which contains 105 brachytherapy seeds, was to be delivered on Monday March 21, 2005. The seeds contain approximately 0.63 milliCi of activity each, with a total package activity of 66 milliCi. The maximum radiation level on the surface of the package is less than 0.5 milliR/hr.
The material was sent via FedEx on Friday March 18 and received at the FedEx facility in Tulsa, Oklahoma on March 19. No further information has been logged since. Medi Physics' customer service group has begun their investigation.
The Arkansas Division of Radiation Control has been advised of the situation.
IL report number: IL050022
*** UPDATE FROM STATE OF IL (G. VINSON) TO (J. KNOKE) AT 15:14 EST ON 3/25/05 ***
The State of IL, Division of Nuclear Safety, called to indicate the missing package containing 105 brachytherapy seeds was located in the Fed Express facility in Arkansas. The package, which was estimated to be found about 11:30 EST on 3/25/05, was intact and in its original condition. The licensee believes the missing package was in the possession of Fed Ex at all times, with no third party intervention. The brachytherapy seeds are being returned to G.E. Healthcare to determine that all seeds are accounted for and to further investigate how the package was lost within the Fed Ex system.
Notifications were given to R3 (Kozak), NMSS (Moore), and TAS (Sandler). |
| Other Nuclear Material | Event Number: 41526 | Rep Org: GEO-TECHNOLOGY ASSOCIATES, INC
Licensee: GEO-TECHNOLOGY ASSOCIATES, INC
Region: 1
City: STERLING State: VA
County:
License #: 19-30479-01
Agreement: N
Docket:
NRC Notified By: TED UPSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/25/2005
Notification Time: 16:18 [ET]
Event Date: 03/25/2005
Event Time: 07:00 [EST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
JOHN ROGGE (R1)
DANIEL GILLEN (NMSS)
BENJAMIN SANDLER (TAS)
| Event Text TROXLER GAUGE REPORTED STOLEN
Geo-Technology Associates, Inc. (GTA) reported the theft of a Troxler gauge, Model 3411, Serial # 15742. The source strength of this gauge is 8 milliCi of Cs-137 and 40 milliCi of Am-241. A contract employee was last seen with the gauge when he signed out for the device at GTA's office on the morning of 3/24/05. He was supposed to have gone to a construction job site in Gainesville, VA, and then return to GTA's office that evening with the Troxler gauge. It is unknown at this time if he reported to the jobsite or returned to the office.
An employee of GTA came into the office about 07:00 on 03/25/05 and discovered the Troxler gauge missing. Normally a worker returns equipment (Troxler gauge) to the office at the end of each workday. The GTA employee reported the possible theft to the Loudoun County Sheriff in VA.
*** UPDATE FROM T. UPSON TO J. KNOKE AT 19:30 ON 03/25/05 ***
An employee of GTA called to report the Troxler gauge was returned to GTA's office sometime between 17:00 and 18:00 on 03/25/05. It was assumed to be the contract employee who originally signed out for the gauge had returned it since it was found inside the locked office of GTA. No visible damage to the device was detected. GTA indicated that early next week a decision would be made on whether or not they will rescind the sheriff's report of a stolen Troxler gauge.
* * * UPDATE FROM T. UPSON TO W. GOTT AT 0950 ON 03/28/05 * * *
The licensee reported that, since the gauge was returned intact and undamaged, they did not plan on pursuing charges against the individual that allegedly used the gauge.
Notified R1DO (J Trapp) and NMSS (Essig). |
| Power Reactor | Event Number: 41530 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ART BREADY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/28/2005
Notification Time: 00:35 [ET]
Event Date: 03/27/2005
Event Time: 22:00 [EST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
JOHN ROGGE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Startup | 0 | Startup | Event Text PLANT SHUTDOWN TO REPAIR SMALL REACTOR COOLANT SYSTEM LEAK
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"While in OPCON 2 with the Main Turbine secured, Hope Creek personnel performed a Primary Containment entry to determine the source of slightly elevated unidentified leakage. This leakage has slowly trended up since plant start-up in February to approximately 0.73 gpm. With the current unidentified leak rate at 0.436 gpm, personnel identified a steam leak from an insulated decontamination port, sealed via a bolted flange, within the isolable boundary of the 'B' Reactor Recirculation pump. This was the only source of reactor coolant system leakage identified although some minor leakage (totaling approximately 250ml/min) from two drywell recirculation fans was also identified. This is a voluntary/courtesy Emergency Notification System (ENS) notification that Hope Creek is proceeding to Cold Shutdown to precisely identify and repair the leakage source. At the time of this notification, Hope Creek Generating Station is in OPCON 3 with plant cooldown in process."
The licensee reported this event under 10 CFR 50.72(b)(2) as a 4-Hour Non-Emergency Voluntary notification. The NRC Resident Inspector has been notified and the licensee plans to notify LAC Township. |
| Power Reactor | Event Number: 41531 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: TOM OSELAND
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/28/2005
Notification Time: 01:12 [ET]
Event Date: 03/27/2005
Event Time: 19:30 [CST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
LAURA KOZAK (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 85 | Power Operation | 85 | Power Operation | Event Text ELECTRICAL SAFETY BUS TRIP DURING QUAD CITIES UNIT 1 REFUELING OUTAGE
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"At 1930, Unit 1 experienced a loss of 480 VAC busses 18 and 19. This caused a loss of power to the Control Room Emergency Ventilation System (CREVS) and the CREVS Air Conditioning System (CREVS AC). This event also caused a loss of power to the U1 equipment that was supporting the Alternate Decay Heat Removal (ADHR) mode of operation.
"Power was restored to Bus 19 at 2001 and Bus 18 at 2013. The restoration of Bus 18 also restored power to CREVS and CREVS AC. All systems supporting ADHR were restored by 2015. At the time of the occurrence, the estimated time to boil without decay heat removal capability was 571 minutes. All isolations and actuations occurred as expected. The cause of the bus trips is being investigated.
"This Event is being reported under 50.72 (b)(3)(v)(B) and 50.72 (b)(3)(v)(D)."
The licensee stated at the time of the event, Busses 18 and 19 were cross-tied and the feeder breaker to Bus 18 tripped open. The breaker was changed out and power to Busses 18 and 19 restored. The cause of the Bus 18 feeder breaker trip has not yet been determined.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM THE LICENSEE (OSELAND) TO NRC (HUFFMAN) AT 0312 EST ON 3/28/05 * * *
The licensee stated that the Alternate Decay Heat Removal pumps from Unit 2 remained in service so that all decay heat removal was not lost. The Unit 1 primary coolant system temperature increase during the 45 minute duration of this event was approximately 1 degree. R3DO (Kozak) has been notified. |
| Hospital | Event Number: 41532 | Rep Org: ST JOSEPH REGIONAL MEDICAL CENTER
Licensee: ST JOSEPH REGIONAL MEDICAL CENTER
Region: 3
City: SOUTH BEND State: IN
County:
License #: 13-02650-02
Agreement: N
Docket:
NRC Notified By: JOHN SCHEU
HQ OPS Officer: BILL GOTT | Notification Date: 03/28/2005
Notification Time: 11:13 [ET]
Event Date: 02/23/2004
Event Time: [CST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
| Person (Organization):
KENNETH RIEMER (R3)
TOM ESSIG (NMSS)
| Event Text MEDICAL EVENT
The following information was supplied by the licensee:
"Two patients involved in what we now think to be reportable events.
1. A.M. 2-23-04 to 2-24-04
2. R.M. 3-01-04 to 3-02-04
"In both cases the patients were being treated for endometrial cancer with brachytherapy. A new Wang vaginal applicator was used. The tandem was loaded with incorrect size sources (of Cs-137) which then had the ability to slide out of the intended treatment position through the placement spring when the patient would sit in a more up-right position. With the sources out of position they would irradiate the patients inner thigh. The dose to the thigh had to be estimated based on estimated time the patient was in an up-right position and the effect seen on the skin.
"At the time these incidents took place it was not felt that reportable events had taken place because of the calculated exposure to the thigh, patient symptoms, and the interpretation of 35.3045 (a) (1)(2), (3).
"One of the patients (A.M.) returned recently (1/05) with an ulcer at the area of thigh exposure. This has caused the radiation therapy staff to reevaluate their dose estimation to the patients. After review, it is believed that reportable events my have occurred based on 35.3045 (A) (3).
"This conclusion was formulated on 3-25-05 after a staff meeting and 1 received the final letter from the physician today 3-28-05."
The tandem manufacturer recommends 3M seeds and the facility used Amersham seeds which resulted in the seeds shifting. A total of 5 patients were treated. The initial estimates determined that the exposure was less than the reportable limit. All the patients were notified of the exposure.
One of the two overexposed patients is responding well to treatment. The other patient may have received the higher dose. The remaining three patients appear to have received less than the reportable dose. |
| Power Reactor | Event Number: 41533 | Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES SHELL
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/28/2005
Notification Time: 14:21 [ET]
Event Date: 03/28/2005
Event Time: 14:21 [EST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVID AYRES (R2)
|
| 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 PLANNED OUTAGE OF SPDS DUE TO SYSTEM UPGRADE
The licensee faxed the following information:
"On Tuesday, March 29, 2005, Surry Power Station will remove a portion of the Emergency Response Facilities Computer System (ERFCS) in the Main Control Room (MCR) for planned upgrades to a new system for increased reliability and improved human interface design. For approximately 1 week, there will not be a qualified Safety Parameter Display System (SPDS) available in the MCR.
"During the time period that SPDS is unavailable in the MCR while the upgrade is occurring, the replacement SPDS system is available in the MCR on the Plant Computer System (PCS), but final testing will not qualify the software until completion of this work. There will also remain one ERFCS terminal operable in both the Technical Support Center (TSC) and Local Emergency Operations Facility (LEOF) with operable SPDS throughout the duration of this work. The Emergency Response Data System (ERDS) will remain available from those terminals for the duration of this planned work and normal data transmission capability will remain in the event of an emergency.
"Since SPDS will be out of service for greater than 1 hour, this report is being submitted in accordance with the guidance in 10CFR50.72(b)(3)(xiii) and NUREG-1022."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41534 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CRAIG INGOLD
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/28/2005
Notification Time: 15:27 [ET]
Event Date: 03/28/2005
Event Time: 13:59 [CST]
Last Update Date: 03/28/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
KENNETH RIEMER (R3)
HERB BERKOW (NRR)
JACK CRLENJAK (IRD)
FEMA ()
DHS ()
|
| 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 UNUSUAL EVENT DECLARED DUE TO HYDROGEN LEAK
The licensee faxed the following information:
"Following the Unit 2 trip, (due to a malfunction of the generator protection circuitry), a hydrogen leak was identified on the Unit 2 main generator. The leakage was sufficient enough to cause a flammable gas release affecting normal plant operation. The Unusual Event was declared under HU6 - Hazards and Other Conditions. The State and local authorities were notified at 14:09 CST. There is NO fire, it is a hydrogen release only."
The licensee said the hydrogen totalizer, which indicated a flow rate of 100 cfm, may be a probable area of leakage. The hydrogen leaked directly into the turbine building. Air samples indicated personnel breathing apparatus was not required. The licensee expects to exit from the UE once the hydrogen system was purged with CO2. Estimated timeframe is 3-6 hours.
The licensee notified the NRC Resident Inspector.
*** UPDATE FROM D. BRAGLIA TO J. KNOKE AT 17:40 EST ON 3/28/05 ***
The licensee terminated their Unusual Event at 17:40 EST, and the plant status is 0% power / Mode 3. The hydrogen leak was determined to be from a bushing on the main generator. The hydrogen leakage is believed to have lasted only 5 minutes.
The licensee notified the State and NRC Resident Inspector.
Notified R3DO (Riemer), IRD Manager (Crlenjak), NRR EO (Berkow), FEMA and DHS. |
| Power Reactor | Event Number: 41535 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CRAIG INGOLD
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/28/2005
Notification Time: 15:27 [ET]
Event Date: 03/28/2005
Event Time: 12:46 [CST]
Last Update Date: 03/28/2005 | 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):
KENNETH RIEMER (R3)
HERB BERKOW (NRR)
JACK CRLENJAK (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE TO GENERATOR PROTECTION CIRCUITRY
The licensee faxed the following:
"Unit 2 reactor trip due to generator protection circuitry. Auxiliary feedwater actuated as expected. There were no additional malfunctions or unexpected plant response. The cause of the generator protection circuitry induced trip is still under investigation.
"This is a 4 hour notification of an RPS actuation per 10CFR 50.72(b)(2)(iv)(B). The 8 hour notification of an auxiliary feedwater system actuation per 10CFR 50.72(b)(3)(iv)(A) is being made under the same telephone call."
See Event 41534.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41536 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: CLYDE BAUER
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/28/2005
Notification Time: 15:52 [ET]
Event Date: 03/28/2005
Event Time: 10:35 [EST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
JAMES TRAPP (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Cold Shutdown | Event Text RCS THROUGH WALL LEAKAGE IDENTIFIED AT WELDED PIPING JUNCTION
"At 1035 hours on the morning of 3/28/05, investigation into a previously reported leak (Event #41530) identified an approximate 3 inch through wall flaw at the welded junction of the 4 inch diameter decon port and the 28 inch diameter 'B' Reactor Recirculation Systems pump suction piping. The identification of the indication required the removal of insulation in order to complete the inspection. The unidentified leakage rate is below Tech Spec limits and the leak location is within the isolable boundary of the 'B' Reactor Recirculation Pump. This failure constitutes a welding or material defect in the primary coolant system that is not acceptable under ASME Section XI for ASME Code Class 1 piping.
"This report is being made under Hope Creek Event Classification Guide RAL# 11.2.1 in accordance with 10CFR50.72(b)(3)(ii). At the time of this notification, the Hope Creek Generating Station is in OPCON 4 at 150 degrees reactor coolant temperature to support piping repairs."
The licensee informed the Lower Alloways Creek Township and NRC Resident Inspector. |
| Power Reactor | Event Number: 41537 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JAMES MILLIGAN
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/28/2005
Notification Time: 17:15 [ET]
Event Date: 03/28/2005
Event Time: 12:48 [CST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
WILLIAM JOHNSON (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text NOTIFICATION OF A FORCED OUTAGE EXPECTED TO LAST LONGER THAN THREE DAYS.
The licensee faxed the following information:
"At 1248, 03/28/05, Callaway Plant notified the Missouri Public Service Commission (MPSC) of a forced outage expecting to last longer than three days. This notification was performed in accordance with 4CSR2403.190(3)(B).
"The information was supplied to the MPSC:
* the plant shutdown occurred at 0520, 03/26/05 due to a minor leak in the Essential Service Water system,
and that additional repairs were going, to be performed while shutdown.
* the scope of the work addition had not been finalized and a formal restart date had not been established.
"This ENS notification is being made in accordance with 10CFR50.72(b)(2)(xi) for notification of another government agency."
The licensee notified other governmental agencies and the NRC Resident Inspector. |
| Power Reactor | Event Number: 41538 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE HOLZMANN
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/28/2005
Notification Time: 17:19 [ET]
Event Date: 03/28/2005
Event Time: 13:43 [CST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KENNETH RIEMER (R3)
|
| 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 LOSS OF EMERGENCY SIREN CAPABILITY DUE TO POWER OUTAGE
"The purpose of this 8 Hour notification is to inform the Nuclear Regulatory Commission of a Loss of Emergency Preparedness Capabilities per NUREG 1022 and 10CFR50.72(b)(3)(xiii). Specifically, at 1455 central standard time on 3/28/05, Point Beach Nuclear Plant was notified that Emergency Plan Sirens, P012, P013, and P014 were out of service. These three sirens constitute 59.32% loss of population coverage.
"The time that the emergency sirens went out of service was 1343 CST, 3/28/05. These sirens are fed from Two Rivers Water/Light (WIPPI). Point Beach Nuclear Plant has contacted Manitowoc County Dispatch at 1517 of the loss of population coverage, and subsequent power restoration. Two Rivers Municipal Utilities has restored power to the Emergency Plan Sirens at 1533 on 3/28/05."
The licensee informed the NRC Resident Inspector.
*** UPDATE FROM J.FOUSE TO J. KNOKE AT 19:02 EST ON 03/28/05 ***
The licensee faxed the following update:
"The purpose of this update is to provide additional clarification to EN#41538. At 1343 CST, Emergency Plan Siren P012 went out of service due to a power outage. The loss of P012 represents a 3.38% loss in population coverage in and of itself. At 1502 CST, Emergency Plan Sirens P013, and P014 went out of service due to a power outage. When all three sirens are out, as they were from 1502 to 1533 CST, the loss of coverage to the population is 59.32%.
"Power was restored to Emergency Plan Sirens P012, P013, and P014, and they were returned to service at 1533 CST. The remainder of EN#41538 remains accurate as written."
The licensee informed the NRC Resident Inspector.
Notified the R3DO( Riemer). |
| Power Reactor | Event Number: 41539 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: AL PROKASH
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/28/2005
Notification Time: 22:53 [ET]
Event Date: 03/28/2005
Event Time: 15:30 [CST]
Last Update Date: 03/28/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
KENNETH RIEMER (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown | Event Text HISTORICAL REPORT - AFTER-THE-FACT OPERABILITY ASSESSMENT
The licensee provided the following information:
"This event notification reports a previously unrecognized reportable event that occurred in 2002. This past event is being reported under the criterion of 10CFR50.72(b)(3)(ii)(B), an event or condition that results in the plant being in an unanalyzed condition.
"On 1/23/2002, at 1815 hours, while the plant was operating at full power, the plant entered a 72 hour Technical Specifications (TS) limiting conditions for operation (LCO) for one train of the Residual Heat Removal (RHR) system. The RHR system LCO was entered when the plant discovered a potential for reaching pump runout under specific post-accident operating conditions for single pump operation of the Component Cooling Water (CCW) system. The CCW system provides cooling support to the RHR system for post-accident long term recirculation core and containment cooling operation. The RHR train was returned to service at 2002 hours on 01/25/2002, within the TS allowed 72 hours, after a flow limiting device was installed on a non-critical CCW system flaw control air operated valve.
"An after-the-fact past operability assessment of the condition found that, compared to corrective actions taken to remove the potential for runout, the condition potentially existed since original plant design. As a minimum, it existed for a period longer than the TS allowed LCO for the RHR system. Therefore, an unanalyzed condition did exist and as such this is a late report."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41540 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PHIL CHASE
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/28/2005
Notification Time: 23:56 [ET]
Event Date: 03/28/2005
Event Time: 17:38 [EST]
Last Update Date: 03/29/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JAMES TRAPP (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 HIGH PRESSURE COOLANT INJECTION TEMPORARILY INOPERABLE
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"Unit 2 High Pressure Coolant Injection (HPCI) [was] declared inoperable due to a loose control power fuse clip associated with the HPCI Pump Suction from Suppression Pool Valve HV-055-212041. The loose clip resulted in loss of control power to this DC motor operated valve and therefore rendered the HPCI system inoperable. The fuse clip has been replaced and the HPCI system returned to an operable status. This report is being made pursuant to 10CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident."
The licensee will notify the NRC Resident Inspector. | |