| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/08/2005 - 04/11/2005 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41390 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDY ROBINSON
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 02/09/2005
Notification Time: 14:22 [ET]
Event Date: 02/09/2005
Event Time: 09:20 [EST]
Last Update Date: 04/08/2005 | 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 | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 91 | Power Operation | 91 | Power Operation | Event Text BOTH TRAINS OF THE CONTROL STRUCTURE EMERGENCY OUTSIDE AIR SUPPLY SYSTEM INOPERABLE
"At 09:20 am, on February 9th, the control room declared both trains of Control Structure Emergency Outside Air Supply System (CREOASS) inoperable. The control room was notified of an inoperable boundary door that was not closed and latched and therefore would not have allowed CREOASS to perform its safety function of maintaining the Control Structure at a positive pressure if required. The door was closed and locked [at 11:15] to restore the habitability boundary.
"The door has since been repaired [adjustment of latch mechanism].
"Initial investigation determined that the door had been unlocked at approximately 09:20 this morning by an elevator vendor to perform maintenance.
"This is being reported as an event or condition that could have prevented the fulfillment of the safety function required to mitigate the consequences of an accident.
"CREOASS was not called upon to function during the period that the door was not operable."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM LICENSEE (ROBINSON) TO NRC (HUFFMAN) @ 1328 EDT ON 4/8/05 * * *
The following information was provided by the licensee (licensee text in quotes):
"On 2/9/2005, PPL Susquehanna LLC reported a loss of safety function for the Control Room Emergency Outside Air Supply System (CREOASS) based on one of the Control Structure Habitability boundary doors being found partially open. Positive air pressure generated by the Control Structure HVAC System prevented the door closure mechanism from maintaining the door closed. The door was closed to restore the habitability boundary.
"The event was reported as a condition that could have prevented the fulfillment of the safety function required to mitigate the consequences of an accident.
"The Safety Function of the CREOASS is to provide adequate radiation protection to permit occupancy of the Control Room under accident conditions for the duration of the accident. The CREOASS accomplishes this by: 1) filtering the outside make-up air supply and 2) maintaining a positive pressure in the control structure habitability boundary to limit unfiltered air in leakage into the boundary. A subsequent engineering evaluation concluded that with the door closure mechanism providing a resistive force, CREOASS would have been able to maintain a positive pressure within the boundary and perform its safety function as described above. In conclusion, the reported condition did not result in a loss of safety function under 10CFR50.72 (b)(3)(v)(D) and is therefore being retracted."
The NRC Resident Inspector and R1DO (Noggle) have been notified. |
| General Information or Other | Event Number: 41557 | Rep Org: RI DEPT OF RADIOLOGICAL HEALTH
Licensee: MIRIAM HOSPITAL
Region: 1
City: PROVIDENCE State: RI
County:
License #: 7D-051-01
Agreement: Y
Docket:
NRC Notified By: JACK FERRUOLO
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/01/2005
Notification Time: 13:56 [ET]
Event Date: 03/30/2005
Event Time: [EST]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES TRAPP (R1)
ELMO COLLINS (NMSS)
| Event Text AGREEMENT STATE - LOST Am-241 SOURCE
An Am-241 sealed source (Serial #: NM-129 received in January 1978) was last inventoried in February 2005.
On the afternoon of March 30, 2005, it was concluded that a wand marker containing 2 mCi of Am-241 was missing. The marker had not been in use and was secured "in storage" in the Nuclear Medicine Hot Lab at the Miriam Hospital. Initially the source was considered to be misplaced. However, on March 30, 2005, the hospital's preliminary investigations had not recovered the source and it was reported as lost. The source is identified as an Am-241 (2mCi) wand formerly used as a marker for an ELCINT camera. The source is in a steel wand and is shielded until a window is opened when used as a marker. It was described as a steel rod with wires out the back end approximately 8 inches long and approximately 0.75 inches in diameter.
The Rhode Island RCA was notified of the incident on March 30, 2005 via a voice message and retrieved by RCA personnel on April 1, 2005 after returning from training out of state. The licensee is continuing a search of each campus in an attempt to retrieve or account for the source.
Event Report ID: RI-05-002
* * * UPDATE 1358 EDT ON 4/8/05 FROM JACK FERRUOLO TO PETE SNYDER VIA FAX * * *
"Investigation conducted on 1 April 05 at RI Hospital Campus of licensee with follow-up at Miriam Campus on 5 April 2006. Findings: Inventory records supported inventory and accountability of source on 11/29/04. Inventory record for 2/16/05 identified the Am-241 source as missing. Notification of RI RCA was not effected until 30 March 05. The source is as described above with the following clarifications: It has a wooden handle at one end-total length of wand increased to approx. 12 inches. A radiation symbol was embossed on the metal portion of the wand, however, the wand was typically placed in a scabbard thus concealing the radiation warning. The Hot tab was confirmed to be locked - key code locking mechanism. The source was stored in a separate waste storage location accessible only from the Hot Lab. All areas in the storage location were checked and the source was not recovered, it is presumed lost and not retrievable. Licensee has scheduled in service with all Nuclear medicine and physics staff to review protocols and to investigate further."
Notified R1DO (Noggle) and NMSS (Leach) |
| Power Reactor | Event Number: 41568 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: DON WALLS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/06/2005
Notification Time: 13:54 [ET]
Event Date: 04/06/2005
Event Time: 10:06 [CST]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LINDA HOWELL (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 | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text MAJOR LOSS OF COMMUNICATIONS CAPABILITY DUE TO OFFSITE FIBER OPTIC CABLE CUT
"On 4/6 at approximately 0900 Emergency Planning (EP) was notified by Arkansas Department of Health that they had lost communications with their Communications Center in Little Rock and asked ANO to perform tests to validate.
"Pope County 911 advised EP that there had been a major fiber optics cut east of Russellville. The NRC Resident also notified EP that their contact with Arlington and headquarters was out including commercial lines. Subsequent investigations revealed that ERDS, ENS, and Health Physics Network (HPN) lines are not functioning at ANO. Backup methods of communications are defined in the Emergency Plan procedures and are available.
"Establishment of communications are ongoing."
The licensee informed the State and NRC Resident Inspector.
* * * UPDATE FROM LICENSEE (HARRIS) TO NRC (HUFFMAN) AT 1507 EDT ON 4/8/05 * * *
The licensee reports that the fiber optic cut had been repaired and all phone circuits returned to operable status by 1618 CST on 4/6/05. The licensee has notified the NRC Resident Inspector. R4DO (Howell) notified. |
| General Information or Other | Event Number: 41571 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TSIT
Region: 4
City: FORT WORTH State: TX
County:
License #: L05697
Agreement: Y
Docket:
NRC Notified By: KAREN VERSER
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/06/2005
Notification Time: 16:50 [ET]
Event Date: 04/06/2005
Event Time: 07:00 [CST]
Last Update Date: 04/06/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA HOWELL (R4)
MELVYN LEACH (NMSS)
CNSNS (FAX)
| Event Text AGREEMENT STATE REPORT INVOLVING THEFT OF A TROXLER PORTABLE GAUGE
The following information was received via fax:
"On 4/6/2005, Linda McLean (NRC) notified Texas DSHS at 10:30 am that their regional office had just received a phone call from the White Settlement, TX Police Department. The police department had been notified of a burglary between 5:00 am and 7:00 am on the morning of April 6, 2005 involving a stolen Troxler (model 3411B) portable gauge containing 10 mCi of Cs-137, serial number 40-9599, and 40 mCi of Am-241, serial number 47-7075. Serial Number for the gauge is 11979. [The authorized user] contacted the police department that he had stopped by his girlfriend's apartment at 5:00 am. When he went outside at 7:00 am, the passenger window had been broken out of his pickup truck and the portable gauge he was planning on using for work had been removed. He stated his radio had been stolen two weeks earlier at the same address. Police report number is 0506384."
Texas Incident No.: I-8227 |
| Power Reactor | Event Number: 41575 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MICHAEL NEMCEK
HQ OPS Officer: ARLON COSTA | Notification Date: 04/08/2005
Notification Time: 05:32 [ET]
Event Date: 04/07/2005
Event Time: 20:28 [EST]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
KENNETH O'BRIEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text POTENTIAL INABILITY TO SAFE SHUTDOWN DUE TO INOPERABLE EMERGENCY DIESEL GENERATORS
The following information was provided by the licensee (licensee text in quotes):
"All three divisions of Emergency Diesel Generators were declared inoperable due to performing at risk design changes on the operable diesel. The design change was removed from the division one diesel and it was declared available at 2045 on 4/7/05. All three diesels remain inoperable."
Perry 1 is currently shutdown in refueling mode 5 and no core alterations are in progress. The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 41577 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: GRANT MELIN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/08/2005
Notification Time: 14:30 [ET]
Event Date: 03/12/2005
Event Time: 10:00 [EST]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
WALTER ROGERS (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 63 | Power Operation | 63 | Power Operation | Event Text OFFSITE NOTIFICATION OF INAPPROPRIATELY MARKED RADIOACTIVE MATERIAL PACKAGES
The licensee provided the following information via facsimile (licensee text in quotes):
"On March 12, 2005, Turkey Point received two packages from, Nucon International that were inappropriately marked. 49CFR173.422(a) requires that packages containing radioactive material be marked on the outside with the UN number proceeded by the letters 'UN.' The packages had the Radioactive Material marking an the outside of the inner packing. The shipment of the unmarked packages constitute an "Undeclared Hazardous Material" as defined in 49CFR171.8. In accordance with 49CFR171.16(a)4, a 30-day report documenting the event was submitted to DOT on April 8, 2005.
"The survey of the two packages confirmed there was no spread of contamination.
"This report is being submitted in. accordance with 10CFR50.72(b)(2)(xi) due to offsite notification to DOT of the above incident."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 41578 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEN HOFFMAN
HQ OPS Officer: WESLEY HELD | Notification Date: 04/08/2005
Notification Time: 16:32 [ET]
Event Date: 04/08/2005
Event Time: 15:43 [EDT]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
WALTER ROGERS (R2)
|
| 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 MAIN STEAMLINE ISOLATION VALVES CLOSED ON VALID SIGNAL
The following information was provided by facsimile (licensee quotes in text):
"Valid actuation of main steam isolation valves that was not a part of pre-planned testing. Actuation was caused by going above pressurizer high pressure block (1955 psig) with steamline pressure less than 775 psig. Main steam isolation signal was reset. Main steam isolation valves reopened. No plant transient."
The NRC Resident Inspector will be notified. |
| Hospital | Event Number: 41579 | Rep Org: LANKENAU HOSPITAL
Licensee: LANKENAU HOSPITAL
Region: 1
City: WYNNEWOOD State: PA
County:
License #:
Agreement: N
Docket:
NRC Notified By: NATHAN ANDERSON
HQ OPS Officer: WESLEY HELD | Notification Date: 04/08/2005
Notification Time: 17:18 [ET]
Event Date: 04/06/2005
Event Time: [EST]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
JAMES NOGGLE (R1)
MELVYN LEACH (NMSS)
| Event Text 10 CFR PART 21 REPORT INVOLVING POTENTIAL DEFECT IN AN HIGH DOSE RATE AFTERLOADING DEVICE
Lankenau Hospital reported an incident involving a Nucletron V2 microselectron High Dose Rate Afterloading device. The Hospital reports that a source stuck in a GYN transfer tube during quality operational checks. The source had to be manually retracted with a hand crank back into a safe position. Inspection of the GYN tube revealed a restriction (described as an edge) that developed on the end that connects to the treatment unit. The Hospital report states that the tube had been in use for two years and may have developed the restriction from normal wear and tear. The tube was replaced and the defective tube transferred to Nucletron. The Hospital report notes that normal wire transfer checks (without the source present) did not identify the problem - but probably should have. The Hospital report also stated that the restriction should not have prevent the source from being automatically retracted to its safe location once the emergency stop was actuated. The cause of the GYN tube restriction is unknown. |
| Power Reactor | Event Number: 41581 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE SAUER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/08/2005
Notification Time: 21:13 [ET]
Event Date: 04/08/2005
Event Time: 19:09 [EST]
Last Update Date: 04/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMES NOGGLE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text OFFSITE NOTIFICATION OF WATER DISCHARGE CONTAINING HYDRAZINE
The following information was provided by facsimile (licensee quotes in text):
"The licensee made notification to the New Jersey Department of Environmental Protection of a discharge of approximately 5000 gallons of water containing 7 parts per million of hydrazine. [The discharge went] to the Delaware river, via the storm drain system. The water originated from a feedwater system clearance that had an isolation valve leak by. The discharge was terminated at the time of discovery.
"There were no personnel injuries as a result of this event."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41582 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN REINSBURROW
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 04/09/2005
Notification Time: 04:53 [ET]
Event Date: 04/09/2005
Event Time: 00:50 [EST]
Last Update Date: 04/09/2005 | 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):
WALTER ROGERS (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 61 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAMMED FROM 61% POWER DUE TO LOW REACTOR WATER LEVEL
"On 04/09/05 at approximately 00:50 an automatic reactor scram occurred on Brunswick Unit 2. The Reactor Protection System (RPS) actuated on low reactor water level (LL1). All control rods inserted from the RPS signal. The LL1 signal also provided a Group 2 (floor and equipment drain isolation valves), 6 (monitoring and sampling isolation valves) and 8 (shutdown cooling isolation valves) isolation signal for the respective containment Isolation valves. Reactor low level 2 (LL2) resulted in a Reactor Core Isolation Cooling (RCIC) system actuation and injection into the reactor. The High Pressure Coolant Injection (HPCI) system actuated but did not inject because reactor water level recovered. The Reactor Water Cleanup system (RWCU) isolated (Group 3 isolation). Secondary Containment isolated and the Standby Gas Treatment (SBGT) system initiated. An Alternate Rod Insertion signal was received and the Reactor Recirculation Pumps tripped as designed. An investigation is in progress to determine the cause of the reactor level transient. Safety systems and isolations functioned as designed."
The NRC Resident Inspector was notified. |
| Power Reactor | Event Number: 41583 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CALVIN FIELDS
HQ OPS Officer: WESLEY HELD | Notification Date: 04/09/2005
Notification Time: 13:20 [ET]
Event Date: 04/09/2005
Event Time: 11:11 [EDT]
Last Update Date: 04/09/2005 | 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):
WALTER ROGERS (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON TURBINE TRIP DUE TO LOW AUTO STOP OIL PRESSURE ON PRESSURE SWITCHES
"At 11:11 Unit 1 Turbine Tripped initiating Reactor Trip. Initial Indications are Turbine Trip due to Lo Auto Stop Oil Pressure on 2 pressure switches. Investigating Switch Actuations.
"#2 and #4 S/G [Steam Generator] Atmospheric Relief Valves did not control properly and RxOp [Reactor Operator] closed valves with Control Switch.
"Current Conditions: U1 [Unit 1] Mode 3, Stm Dumps In Service Normal, RCS temp at 547.4F, Pressure 2238 psig. 2 AFW [Auxiliary Feedwater] trains In Service at Normal Operation.
"All Rods Fully Inserted. Yes."
The licensee indicated there was not excessive cooldown or depressurization in the steam generators whose atmospheric relief valves had to be manually closed.
The NRC Resident Inspector has been notified.
* * * UPDATE PROVIDED BY LICENSEE (FIELDS) TO NRC (HELD) ON 4/9/05 ON 1901 * * *
"AFW Actuation - due to FW [Feedwater] Isol[ation] tripping both MFPs [Main Feed Pumps] (trips start AFW)"
AFW includes 2 motor-driven and 1 turbine-driven pump.
R2DO (Rogers) notified. |
| Power Reactor | Event Number: 41584 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: QUENTIN HICKS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/10/2005
Notification Time: 11:46 [ET]
Event Date: 04/10/2005
Event Time: 05:00 [EST]
Last Update Date: 04/10/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JAMES NOGGLE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A | N | 0 | Refueling | 0 | Refueling | Event Text SCRAM SIGNAL RESULTING FROM FAILURE OF A SUPPLY VALVE TO THE SCRAM AIR HEADER
"Nine Mile Point Unit 1 received a valid RPS SCRAM signal from high water level in the SCRAM Dump Volume (SDV). While restoring the Hydraulic Control Rod Unit (HCU) for control rod 02-35 to service, the internals to the plug valve for the Instrument Air Supply (116 Valve) to the SCRAM Inlet and Outlet valves failed. This failure caused an approximate 1/2" hole in the SCRAM Air Header, which resulted in the SCRAM Air Header pressure lowering rapidly due to the leak.
"Operators at the HCU recommended isolating the SCRAM Air Header. The Shift Manager was contacted by the job supervisor and received permission to isolate the SCRAM Air Header. SCRAM inlet and outlet valves opened, SDV vents and drains closed due to the loss of SCRAM Air Header pressure. Approximately 3 minutes after SCRAM Air Header depressurization, a full SCRAM signal occurred as expected due to the water level in the SDV. There was no fuel in the Reactor Vessel (RPV). No Control Rod motion occurred due to all Control Rods being inserted or isolated for maintenance.
"Immediate (8 Hour Non-Emergency) notification of this event being made as a result of the requirements of 10CRF50.72(b)3(iv)(A)."
The licensee stated that more information on the event can be found in Nine Mile Point Internal document DER - NM-2005-1565.
The license will be notifying the NRC Resident Inspector. |
| Power Reactor | Event Number: 41585 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: WESLEY HELD | Notification Date: 04/10/2005
Notification Time: 12:08 [ET]
Event Date: 04/10/2005
Event Time: 11:50 [EDT]
Last Update Date: 04/10/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
JAMES NOGGLE (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO FAILED 125V DC BATTERY CHARGER
"At 0352 the 2C 125VDC battery charger failed. Fuses internal to the charger were found blown. Technical Specifications require restoration of the charger within 2 hrs or enter Mode 3 within the next 12 hrs and Mode 4 within the next 36 hrs. Investigation has not been able to restore the charger, and therefore the shutdown of the unit has commenced. Loads are currently being carried by the batteries, and personnel are monitoring battery voltage. Initial investigation has not identified any generic issues or any indication of tampering.
"This event is a Technical Specification required shutdown, and is reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(i). Additionally, this is a voluntary notification due to an anticipated press release associated with the downpower towards unit shutdown."
There is evidence of degraded insulation on wires inside the affected battery charger. Battery loads are very small with an initial estimate of battery life at 80 hours. All safety systems are operable. There is no impact on Unit 1.
Unit 2 is expected to reach Mode 3 at 1720 on 4/10/05.
The NRC Resident Inspector has been notified. State (FEMA) will be notified.
* * * UPDATE PROVIDED BY LICENSEE (HUFFORD) TO NRC (HELD) AT 2030 ON 4/10/05 * * *
"At 17:28 the plant completed a normal reactor shutdown and entered Mode 3 in accordance with plant procedures to fulfill the requirements of Technical Specification 3.8.4. There were no ECCS initiations and lowest water level was approximately -4 inches."
The licensee reported that the 2C battery charger was back in service but remained in the LCO due to battery requirements. They are also completing engineering evaluations for extent of condition.
The NRC Resident Inspector was notified.
R1DO (Noggle) notified. | |