U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/24/2003 - 01/27/2003
** EVENT NUMBERS **
38513 39528 39531 39532 39535 39536 39537
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38513 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/23/2001|
| UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 12:30[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/23/2001|
+------------------------------------------------+EVENT TIME: 12:10[EST]|
| NRC NOTIFIED BY: CHARLIE PIKE |LAST UPDATE DATE: 01/25/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO FLORIDA STATE INVOLVING RECOVERED SEA TURTLE FROM |
| UNIT 1 INTAKE STRUCTURE |
| |
| "A sea turtle with no external injuries but appearing to be distressed was |
| recovered from the Unit 1 Intake Structure. The State Stranding Coordinator |
| for sea turtles has been contacted." |
| |
| * * * UPDATE 11/23/01 AT 1255EST FROM CHARLIE PIKE TO S. SANDIN * * * |
| |
| "Turtle has died." |
| |
| The licensee informed both the State of Florida and the NRC Resident |
| Inspector. |
| |
| * * * UPDATE 1413EST ON 12/3/01 FROM JACK BREEN TO FANGIE JONES * * * |
| |
| At approximately 1215 EST on 12/3/01, a report was made to the Florida |
| Department of Fish and Wildlife concerning the recovery of an injured sea |
| turtle from the plant's intake canal. The turtle was a green sea turtle in |
| the intake canal that appeared distressed and looked to have a wound from a |
| boat motor on its back. It will be transferred to the State for |
| rehabilitation. |
| |
| The licensee plans to notify the NRC resident inspector. Notified |
| R2DO(MacAlpine). |
| |
| * * * UPDATE 1333EST ON 12/15/01 FROM JACK BREEN TO JOHN MACKINNON * * * |
| |
| At approximately 1215 EST on 12/15/01, a report was made to the Florida |
| Department of Fish and Wildlife Conservation Commission to pick up a Green |
| Turtle for rehabilitation. The Green Turtle was taken from the plant's |
| intake canal, and the turtle appears to have shark bites. |
| |
| The licensee plans to notify the NRC resident inspector. Notified R2DO |
| (Chuck Ogle). |
| |
| * * * UPDATE 1450EST ON 01/06/02 FROM TULLIDGE TO JOHN MACKINNON * * * |
| |
| At 1350EST, a notification to the State of Florida Department of Fish and |
| Wildlife Conservation Commission was made due to finding an injured |
| Loggerhead sea turtle in Unit 1 intake. The sea turtle was transported |
| offsite for rehabilitation. R2DO (Tom Decker) notified. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| ***UPDATE 1330EST ON 4/23/02 FROM JACK BREEN TO RICH LAURA*** |
| |
| The licensee rescued a Loggerhead sea turtle from the intake canal. The |
| Florida Fish and Wildlife Conservation Commission was notified, and the |
| turtle was turned over for rehabilitation. |
| |
| The NRC Resident Inspector was informed. Notified R2DO (B. Bonser). |
| |
| ***UPDATE 1241EDT ON 5/29/02 FROM DAVE WILLIAMS TO RICHARD LAURA*** |
| |
| The licensee reported that an offsite notification was made to the Florida |
| Fish and Wildlife Conservation Commission concerning the discovery of a live |
| loggerhead sea turtle found in the plant's intake canal. The turtle was |
| lethargic and was sent for rehabilitation. |
| |
| The NRC Resident Inspector was informed. Notified R2DO (K. Landis). |
| |
| ***** UPDATE AT 1125 EDT ON 06/01/02 FROM CHARLES MARPLE TO LEIGH TROCINE |
| ***** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1020 on 06/01/02, a notification was made to the Florida Fish and |
| Wildlife Conservation Commission regarding a weak and emaciated Loggerhead |
| turtle found in the plant intake barrier net. The turtle will be sent |
| off-site to the Marine Life Center for Rehabilitation." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R2DO (Kerry Landis). |
| |
| *****UPDATE AT 11:53 EDT ON 6/2/02 FROM MARPLE TO LAURA****** |
| |
| "A notification was made to the Florida Fish and Wildlife Conservation |
| Commission regarding a dead small green sea turtle found in the tangle net. |
| The turtle will be maintained on ice for a postmortem examination." |
| |
| The NRC resident inspector was notified. Notified R2DO (K. Landis) |
| |
| *****UPDATE AT 12:45 EDT ON 7/18/02 FROM BREEN TO LAURA****** |
| |
| A notification was made to the State regarding a dead green sea turtle that |
| was removed from the intake canal. |
| |
| The NRC resident inspector will be notified. |
| |
| Notified R2DO (C. Payne |
| |
| ***UPDATE AT 1045 EDT ON 10/20/02 FROM KORTH TO NORRIS*** |
| |
| A Loggerhead turtle was retrieved from the plant's intake canal. The turtle |
| was in need of rehabilitation. Per the plant's turtle permit, the Florida |
| Fish and Wildlife Conservation Commission (FWCC) was notified at 0927 EDT. |
| |
| The NRC Resident Inspector has been notified. |
| |
| Notified R2DO (Barr) |
| |
| * * * UPDATE AT 1338 EDT ON 10/22/02 FROM KELLY KORTH TO GERRY WAIG * * * |
| |
| A Loggerhead turtle was retrieved from the plant's intake canal. The turtle |
| was in need of rehabilitation. Per the plant's turtle permit, the Florida |
| Fish and Wildlife Conservation Commission (FWCC) was notified at 1250 EDT. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| Notified R2DO (Bob Haag) |
| |
| * * * UPDATE ON 11/22/2002 @ 1821 BY FIELDS TO GOULD * * * |
| |
| The licensee notified the Florida Department of Environmental Protection of |
| the recovery of a distressed loggerhead sea turtle from their intake canal. |
| The turtle was taken to a rehabilitation facility. |
| |
| The NRC Resident inspector will be notified. Notified R2DO (David Ayres). |
| |
| * * * UPDATE AT 1320 EST ON 12/16/02 FROM BILL PARKS TO GERRY WAIG * * * |
| |
| "On 12-16-02, two loggerhead turtles were retrieved from the plant's intake |
| canal. The turtles were determined to be in need of rehabilitation. The |
| injuries to the turtles are not causal to plant operation. Per the plant's |
| turtle permit, the Florida Fish and Wildlife Conservation Commission (FWCC) |
| was notified at 1230 EST. This non-emergency notification is being made |
| pursuant to 10 CFR 50.72(b)(2)(xi) due to the notification of FWCC." |
| |
| The NRC Resident inspector will be notified. Notified R2DO (Mike Ernstes). |
| |
| * * * UPDATE AT 1350 EST ON 1/25/03 FROM DAVE FIELDS TO MIKE RIPLEY * * * |
| |
| "The State of Florida Department of Environmental Protection was notified |
| that an injured juvenile loggerhead sea turtle was retrieved from the plant |
| intake canal. The turtle was sent to a rehabilitation facility." |
| |
| The NRC Resident inspector will be notified. Notified R2DO (Ken Barr). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39528 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 01/21/2003|
|LICENSEE: FUGRO SOUTH |NOTIFICATION TIME: 12:10[EST]|
| CITY: HOLLYWOOD PARK REGION: 4 |EVENT DATE: 01/20/2003|
| COUNTY: STATE: TX |EVENT TIME: 16:30[CST]|
|LICENSE#: L03875-002 AGREEMENT: Y |LAST UPDATE DATE: 01/21/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |TOM ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM OGDEN | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST AND SUBSEQUENTLY FOUND TROXLER MOISTURE |
| DENSITY GAUGE |
| |
| The following information was received from the Texas Department of Health, |
| Bureau of Radiation Control, Incident Investigation Group via facsimile: |
| |
| "Driver/Operator was at construction site on north side of San Antonio. |
| Reported that he placed the gauge, without transport case, on the tailgate |
| of his company pickup and completed his paperwork in the cab. When [he] |
| completed [the paperwork], he forgot the gauge was still sitting on the |
| tailgate and drove off from the site. Approximately 300 feet down the |
| access road to Loop 1604, he realized that he had not put his gauge away. |
| To return to the site, he had to loop around several access roads to get |
| back to the area. When he arrived back at the construction site, he could |
| not locate the gauge. He called his company for assistance. The company |
| sent other employees to search the entire area without result and then |
| reported the gauge missing to both the Hollywood Park and San Antonio Police |
| Departments. In a call to the Agency [Texas Department of Health] at |
| approximately 7:30 a.m. on January 21, 2003, it was reported that they |
| believe the gauge was found by another contractor who was also departing the |
| site the night before. It is believed that the gauge was put into the back |
| of [the other contractor's] truck. The gauge is a Troxler 3440, Serial |
| Number 30433, with two sealed sources: Cs-137, 8 millicuries, Serial Number |
| 750-4901: and Am-241/Be, 40 millicuries, Serial Number 47-27488. The |
| Radiation Safety Officer called at 10:53 a.m. on January 21, 2003, saying |
| the gauge was recovered at the construction site at 7:30 a.m. this morning |
| (01/21/2003) from another contractor who had found it onsite. The |
| construction superintendent, when notified at home on the evening on January |
| 20, 2003, had located the contractor who found the gauge, and arranged for |
| the pickup this morning. The RSO did not have full details but has the |
| gauge back in his possession. The gauge was visually inspected for damage |
| and no apparent damage was noted. Radiation levels were normal for the |
| gauge. However, a leak test was performed on the gauge. Results are |
| pending. Both Police Departments have been notified of the recovery. It is |
| not known if the helicopter flight was performed during the hours of |
| darkness. [Hollywood Park Police notified the FBI and arranged for a |
| helicopter to search for the gauge with infrared equipment.]" |
| |
| The vehicle was a company pick-up truck. (No description given or known by |
| reporting official.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39531 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 01/24/2003|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 08:32[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/24/2003|
+------------------------------------------------+EVENT TIME: 00:45[EST]|
| NRC NOTIFIED BY: KEN HOFFMAN |LAST UPDATE DATE: 01/24/2003|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE OF ALL REFUELING WATER STORAGE TANK LEVEL INDICATORS |
| |
| "Event or condition that at time of discovery could have prevented the |
| fulfillment of the safety function (FWST [Refueling Water Storage Tank] Auto |
| Swap over). |
| |
| "Refueling Water Tank Level indication for all three channels failed high |
| due to failure of automatic heat tracing which resulted in instrument lines |
| freezing. Exited condition at 0342 hours on 1/24/03." |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39532 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 01/24/2003|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 11:23[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/24/2003|
+------------------------------------------------+EVENT TIME: [EST]|
| NRC NOTIFIED BY: BARRY D. COLEMAN |LAST UPDATE DATE: 01/24/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS ENS AND OFFSITE COMMUNICATION |
| |
| "A major telephone line between Plant Hatch and Uvalda [GA] was damaged |
| (cut) causing a major loss of communication system. |
| |
| "The ENS was inoperable, but the NRC could be notified by commercial line. |
| The Prompt Notification (NOAA radios) was inoperable. Approximately one |
| half of the ability to call offsite was lost (one half of the lines). |
| |
| "Note: The Prompt Notification System (NOAA radios) were returned to service |
| at 1115 [EST]. Total out of service time was 45 minutes." |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * * UPDATE RECEIVED VIA FAX AT 1601 EST ON 1/24/03 FROM BARRY COLEMAN TO |
| MIKE RIPLEY * * * * |
| |
| "We have a new update from Bell South. The line that was cut was not between |
| the plant and Uvalda [GA]. They're repairing the cable now and expect all |
| circuits to be restored by 4:00 PM. Apparently, some land clearing crews |
| were working near the buried fiber between the plant and Baxley [GA] and |
| severed BellSouth's fiber. |
| |
| "NOAA Problem - NOAA was already running on the secondary transmitter fed |
| from Baxley. When the Baxley feed was cut this morning, the whole system |
| shut down because the primary transmitter (fed from Brunswick) was already |
| in error mode, for reasons unknown to us. We powered the entire system down |
| and it started transmitting on the primary Brunswick feed as it should have |
| been." |
| |
| The licensee notified the NRC resident inspector. Notified R2 DO (K. Barr). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39535 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 01/25/2003|
| UNIT: [1] [] [] STATE: VA |NOTIFICATION TIME: 09:25[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/25/2003|
+------------------------------------------------+EVENT TIME: 07:00[EST]|
| NRC NOTIFIED BY: ALISON MacKELLAR |LAST UPDATE DATE: 01/25/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 25 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR TRIP ON LO-LO STEAM GENERATOR WATER |
| LEVEL |
| |
| "At 0700 hours, with Surry Power Station Unit 1 at 25% reactor power during |
| power ascension, an automatic reactor trip was generated due to 2/3 channels |
| on 'B' S/G Lo-Lo Level. |
| |
| "All control rods fully inserted into the core as designed. Borated as |
| necessary to ensure adequate shutdown margin. The shutdown margin for Unit 1 |
| was determined to be satisfactory. 'A' and 'B' motor driven auxiliary |
| feedwater pumps automatically initiated as designed on low low steam |
| generator level following the trip. The turbine driven auxiliary feedwater |
| pump tripped. All three Main Steam Trip Valves were manually closed due to |
| the primary RCS cooldown. Primary RCS temperature decreased to approximately |
| 526 degrees. Currently RCS temperature is stable at 547 degrees on the |
| Secondary Power Operated Relief Valves. |
| |
| "No primary safety or power operated relief valves were actuated during the |
| event. No indication of primary to secondary leakage exists, therefore no |
| adverse radiological consequences resulted from this event. |
| |
| "All electrical busses remained energized following the trip and all |
| emergency diesel generators are operable. There were no radiation releases |
| due to this event, nor were there any personnel injuries or contamination |
| events. The cause of the event is being investigated. |
| |
| "Unit 1 is currently at Hot Shutdown with RCS temperature being maintained |
| at approximately 547 degrees. |
| |
| 'Unit 2 was not affected by this event and remains stable at 100% power |
| operations. |
| |
| "This event is being reported in accordance with 10CFR50.72(b)(2)(iv) and |
| 10CFR50.72(b)(3)(iv)." |
| |
| Operators were in the process of transitioning between manual and automatic |
| S/G water level control when the automatic trip occurred. The licensee will |
| investigate the cause of the automatic turbine driven auxiliary feedwater |
| pump trip. |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39536 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 01/25/2003|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 17:35[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/25/2003|
+------------------------------------------------+EVENT TIME: 14:14[EST]|
| NRC NOTIFIED BY: JOHN DUFF |LAST UPDATE DATE: 01/25/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: |HERB BERKOW NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP DUE TO A MAIN GENERATOR TRIP |
| |
| "At 1414 hours, with Surry Power Station Unit 2 at 100% reactor power an |
| automatic reactor trip was generated due to a main generator trip. The main |
| generator tripped due to a differential lockout. |
| |
| "Individual rod position indications (IRPI) for three control rods indicated |
| between 11 and 20 steps following the trip. An emergency boration was |
| initiated followed by a normal boration in accordance with station |
| procedures to ensure adequate shutdown margin. The shutdown margin for Unit |
| 2 was determined to be satisfactory. All other control rod indications fully |
| inserted into the core as designed. The three IRPIs that initially did not |
| indicate fully inserted slowly drifted to less that 10 steps. |
| |
| "All three auxiliary feedwater pumps automatically initiated as designed on |
| low low steam generator level following the trip. Currently RCS temperature |
| is stable at 547 degrees and being controlled by condenser steam dump |
| valves. No primary or secondary safety or power operated relief valves were |
| actuated during the event. No indications of primary to secondary leakage |
| exist. |
| |
| "All electrical busses transferred properly following the trip and all |
| emergency diesel generators are operable. At the time of the Unit 2 reactor |
| trip, Surry Unit 1 was off-line due to a previous trip. Load shed occurred |
| on the station service busses as designed. As a result of the load shed |
| signal, the Surry Unit 1 "A" Main Feed Pump tripped. The Unit 1 "B" Main |
| Feed Pump had previously been shut down. This resulted in a loss of both |
| Main Feed Pumps on Unit 1 and restarted the Unit 1 Motor Driven Auxiliary |
| Feedwater Pumps. |
| |
| "There were no radiation releases due to this event, nor were there any |
| personnel injuries or contamination events. The cause of the Unit 2 trip is |
| being investigated. |
| |
| "Unit 2 is currently at Hot Shutdown with RCS temperature being maintained |
| at approximately 547 degrees. Unit 1 is also at Hot Shutdown with RCS |
| temperature being maintained at approximately 547 degrees. |
| |
| "This event is being reported in accordance with 10CFR50.72(b)(2)(iv) and |
| 10CFR50.72(b)(3)(iv)." |
| |
| The licensee is investigating the cause of the main generator trip. The |
| licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39537 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/26/2003|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 02:21[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/26/2003|
+------------------------------------------------+EVENT TIME: 00:17[EST]|
| NRC NOTIFIED BY: CHARLES ARCHEY |LAST UPDATE DATE: 01/26/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHRISTINE LIPA R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |55 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| "Cook Nuclear Plant Unit 2 Technical Specification 3.8.1.1.b requires two |
| separate and independent diesel generators to be operable. Action b |
| specifies [that] if one diesel is inoperable, then 'restore diesel |
| generators to OPERABLE status within 72 hours or be in at least HOT STANDBY |
| within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.' |
| Unit 2 diesel generator 2-OME-150-CD (Unit 2 CD diesel generator) has been |
| inoperable since 04:00 on January 23, 2003 for scheduled maintenance. |
| During post-maintenance testing, diesel load fluctuations occurred which |
| continued to render the diesel inoperable. Diagnostic testing continues on |
| the Unit 2 CD diesel generator. When it became evident operability of the |
| Unit 2 CD diesel generator would not occur by the expiration of the 72 hour |
| Limiting Condition of Operation at 04:00 on January 26, Cook Unit 2 began a |
| power reduction from 100% reactor thermal power. The power reduction began |
| at 00:17 on January 26 at a rate of approximately 20% per hour with a plan |
| to manually trip the reactor to enter Mode 3 (Hot Standby) at 17% reactor |
| thermal power at approximately 05:00. A cooldown to Mode 5 (Cold Shutdown) |
| is expected within 30 hours of the entry to Mode 3 (Hot Standby) in |
| accordance with Technical Specification 3.8.1.1, action b. |
| |
| "This Four Hour Report is being made in accordance with 10 CFR |
| 50.72(b)(2)(i) for the initiation of a nuclear plant shutdown required by a |
| plant's Technical Specifications. |
| |
| "There were no emergency plan or radiological release issues with this Unit |
| 2 event. Unit 1 remains in Mode 5 with a main transformer replacement in |
| progress." |
| |
| The Licensee notified the NRC Resident Inspector. |
| |
| * * * * UPDATE FROM CHARLES ARCHEY TAKEN BY MIKE RIPLEY AT 2310 EST ON |
| 1/26/03 * * * * |
| |
| The licensee provided the following revised wording to reflect a |
| re-evaluation of the Technical Specification requirements for the transition |
| to Mode 5 if the Unit 2 CD diesel generator remains inoperable: |
| |
| "Cook Nuclear Plant Unit 2 Technical Specification 3.8. 1. 1 .b requires two |
| separate and independent diesel generators to be operable. Action b |
| specifies if one diesel is inoperable, then 'restore diesel generators to |
| OPERABLE status within 72 hours or be in at least HOT STANDBY within the |
| next 6 hours and in COLD SHUTDOWN within the following 30 hours.' Unit 2 |
| diesel generator 2-OME-150-CD ('Unit 2 CD diesel generator') has been |
| inoperable since 04:00 on January 23, 2003 for scheduled maintenance. |
| During post-maintenance testing, diesel load fluctuations occurred which |
| continued to render the diesel inoperable. Diagnostic testing continues on |
| the Unit 2 CD diesel generator. When it became evident operability of the |
| Unit 2 CD diesel generator would not occur by the expiration of the 72 hour |
| Limiting Condition of Operation at 04:00 on January 26, Cook Unit 2 began a |
| power reduction from 100% reactor thermal power. The power reduction began |
| at 00:17 on January 26 at a rate of approximately 20% per hour with a plan |
| to manually trip the reactor to enter Mode 3 (Hot Standby) at 17% reactor |
| thermal power at approximately 05:00. |
| |
| "Transition to Mode 3 is expected after the 72 hour time limit is exceeded |
| (04:00 on January 26) and before 10:00 on January 26 (6 hours following |
| expiration of the 72 hour time limit). Transition to Mode 5 is expected |
| before 16:00 on January 27 (within the following 30 hours) if the Unit 2 CD |
| diesel generator remains inoperable. |
| |
| "This Four Hour Report is being made in accordance with 10 CFR |
| 50.72(b)(2)(i) for the initiation of a nuclear plant shutdown required by a |
| plant's Technical Specifications. |
| |
| "There were no emergency plan or radiological release issues with this Unit |
| 2 event. Unit 1 remains in Mode 5 (Cold Shutdown) with a main transformer |
| replacement in progress." R3DO (Christine Lipa) notified. |
| |
| The NRC Resident Inspector was notified of this update by the licensee. |
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