Event Notification Report for October 11, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/10/2001 - 10/11/2001
** EVENT NUMBERS **
38362 38366 38370 38371 38372 38373 38375
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|Power Reactor |Event Number: 38362 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/07/2001|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 13:02[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/2001|
+------------------------------------------------+EVENT TIME: 09:50[EDT]|
| NRC NOTIFIED BY: STEVE CHERBA |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 8 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED REACTOR TRIP DURING PLANT STARTUP OPERATIONS |
| |
| ". . . . This event occurred at 0950 hours this morning (10-7-01). Currently |
| the Unit is in Mode 3 with all systems normal. At the time of the trip the |
| unit was at approximately 8 % power (by RCS AT indication, about 6 to 7 % on |
| Power Range Nuclear Instrumentation) in power ascension and was just |
| preparing to roll the main turbine. |
| |
| "RCS Tavg was noted to decrease below the normal 547 �F no-load post-trip |
| value to about 535 �F by the Reactor Operator monitoring the temperature. At |
| the time of the trip one main feedwater pump was supplying the Steam |
| Generators (SG), with low-flow feedwater pre-heating in service. Main |
| feedwater isolated on the trip with the SGs being supplied post trip by the |
| motor driven Auxiliary Feedwater (AFW) Pumps. The RCS cooldown was |
| attributed to the #4 SG AFW flow control valve not closing as expected on |
| high flow thus allowing too much flow to #4 SG, as well as steam that was |
| still being supplied to low flow feedwater preheating. Operator actions |
| taken in response to the cooldown were to close the main steam stop valves, |
| and review AFW valve positions so as to limit steam flow from, and feed flow |
| to, the SGs. These actions were completed by 0959 hours, and were sufficient |
| to maintain temperature control. RCS temperature shortly recovered to 547 �F |
| at about 1032 hours, 10-7-01. No other significant abnormalities were noted, |
| pressurizer pressure decreased in response to the temperature transient, and |
| the subsequent RCS shrink caused RCS letdown to isolate on low pressurizer |
| level. The plant is presently stable in Mode 3. No other RPS or SI setpoints |
| were exceeded due to the trip and subsequent temperature transient. All |
| other systems and equipment functioned normally. |
| |
| "The initiating RPS signal was a high Power Range Nuclear Instrument Rate |
| Trip on 2 out of 4 channels. Cause of this rate trip is not definitively |
| known at this time, rapid event teams to investigate and evaluate the trip |
| have been initiated. Suspected cause is a Rod Control System problem." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE 0353EDT ON 10/10/01 FROM DALE TURINETTI TO S. SANDIN * * * |
| |
| The following information was received as an update to this report: |
| |
| "The cause of the Unit 2 reactor trip was a negative rate trip as a result |
| of a loss of Rod Control Motor Generator set voltage. The loss of voltage |
| was attributed to a failed open resistor on the North motor generator set |
| which caused a loss of voltage regulation. It is believed this loss of |
| voltage caused the north motor generator set to act as a load; and the south |
| motor generator set could not maintain the output voltage. The reduction in |
| voltage caused a collapse of field and the subsequent release of control |
| rods and resultant negative rate trip. |
| |
| "The motor generator set resistors have been replaced and associated relays |
| have been tested to ensure proper operation of the motor generator sets. |
| Plant power ascension is in progress with the unit in mode 1 and at 25%." |
| |
| The licensee informed the NRC resident inspector. Notified R3DO(Parker). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38366 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 10/09/2001|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 12:22[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 10/09/2001|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: JOHN SCHORK |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CLIFF ANDERSON R1 |
|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 N 0 Intermediate Shut|0 Intermediate Shut|
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LANCASTER COUNTY EMERGENCY SIRENS WERE FOUND INOPERABLE |
| |
| "At 11:30 AM on 10/9/01, TMI determined that the apparent inoperability of |
| emergency sirens in Lancaster County, Pennsylvania for approximately 3 days |
| met the criteria set forth in NUREG 1022, Rev. 2 for a major loss of |
| emergency offsite communications capability and that an immediate 8 hour |
| notification in accordance with 10 CFR 50.72(b)(3)(xiii) was required. |
| |
| "At approximately 8:55 am on Tuesday, October 9, 2001 the emergency sirens |
| in Lancaster County were inadvertently activated during routine maintenance |
| by Capitol Area Communications, the siren vendor. During the weekly |
| evaluation of system electronics on Tuesday, October 9, 2001, Capitol Area |
| Communications had discovered an anomaly with the system communications with |
| Lancaster County. Capitol Area Communications called Lancaster County and it |
| was found that apparently the transmitter for Lancaster County had been |
| incorrectly left turned off following recent maintenance performed on |
| Saturday, October 6, 2001 that occurred in the vicinity of the transmitter. |
| |
| "The transmitter was turned back on at approximately 8:55 am on Tuesday, |
| October 9, 2001. When the transmitter was turned on, a signal that had been |
| sent on Saturday, October 6, 2001 for the monthly Saturday test of the |
| sirens that had been received but not acted upon, was acted upon by the |
| transmitter which then activated the sirens. The sirens were silenced upon |
| recognition of the inadvertent actuation. Lancaster County is notifying |
| local media of the cause of the inadvertent siren actuation. |
| |
| "Subsequent discussions between Exelon Emergency Management personnel and |
| the siren vendor determined that the sirens for Lancaster County had |
| apparently been inoperable from sometime on Saturday, October 6 until today, |
| Tuesday, October 9. |
| |
| "The sirens in Lancaster County were reactivated when the transmitter [was |
| turned] back on. |
| |
| "The Lancaster County 911 dispatcher number 41 called the TMI Control Room |
| at approximately 9:00 AM. The Control notified a duty public information |
| representative of the siren malfunction. The duty Public Information |
| Representative spoke with Lancaster County Emergency Management at 9:13 am |
| who confirmed the information received from the 911 dispatcher. |
| Subsequently, at 9:15 am Exelon emergency management reconfirmed the |
| information received. |
| |
| "The site Sr. Resident Inspector has been informed of the event and the 8 |
| hour report. TMI Communications contacted the Lancaster County Commissioners |
| and PEMA to inform them of the event." |
| |
| * * * UPDATE 1423 10/10/2001 FROM SCHORK TAKEN BY STRANSKY * * * |
| |
| "This is a revision of the initial 8 hour notification made by TMI-1 per |
| Event Notification 38366 on October 9, 2001 at 1222 hours. The revised |
| notification is being submitted to document that the sirens in question were |
| out of service for approximately 4 days instead of the initial report of 3 |
| days and that a contributing cause to the event may be the software that is |
| used in performing the test. |
| |
| "Additional discussions between TMI Emergency Preparedness, Exelon Emergency |
| Preparedness, Lancaster County Emergency Management and Capitol Area |
| Communications that took place on Wednesday, October 10, 2001 determined |
| that the siren transmitter was out of service from Friday, October 5 to |
| Tuesday, October 9. In addition, a functional test of the computer software |
| used to perform the weekly test in Lancaster County found that the software |
| did not detect a failure of the sirens to actuate when the transmitter is |
| de-energized. The software does detect siren failures when the transmitter |
| is energized. Exelon Emergency Preparedness is contacting the software |
| vendor to obtain additional information. The software in question was |
| provided by AmerGen to the 5 risk counties for Three Mile Island Nuclear |
| Power Station." |
| |
| The NRC resident inspector has been informed of this update by the licensee. |
| Notified R1 IRC. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38370 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/10/2001|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 08:44[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/10/2001|
+------------------------------------------------+EVENT TIME: 02:53[EDT]|
| NRC NOTIFIED BY: CHRIS SERATA |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R1 IRC TEAM MANAGER R1 |
|10 CFR SECTION: | |
|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 N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC RPS ACTUATION ON LOW REACTOR VESSEL WATER LEVEL FOLLOWING UNIT |
| SHUTDOWN |
| |
| "Following the shutdown of Hope Creek Generating Station at the beginning of |
| the 10th Refueling Outage, a subsequent low reactor water level condition |
| occurred which resulted in actuation of the Reactor Protection System (RPS). |
| The low level occurred when reactor depressurization was terminated. The |
| unit was in Hot Shutdown at the time of the RPS actuation with all control |
| rods fully inserted. |
| |
| "Cooldown to Operational Condition 4 is in progress." |
| |
| |
| The licensee will inform the Lower Alloways Creek Township and the NRC |
| resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38371 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/10/2001|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 08:44[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/10/2001|
+------------------------------------------------+EVENT TIME: 03:32[EDT]|
| NRC NOTIFIED BY: CHRIS SERATA |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R1 IRC TEAM MANAGER R1 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RCS PRESSURE BOUNDARY LEAKAGE IDENTIFIED DURING CONTAINMENT WALK DOWN |
| |
| "During a Primary Containment walk down at the beginning of the Hope Creek |
| 10th Refueling Outage, inspection crews identified a cracked weld on the 'A' |
| Reactor Recirculation Loop elbow tap instrument piping, which is part of the |
| Reactor Coolant Pressure Boundary. The cracked weld is located where a 1" |
| tap connects to the 28" recirculation loop piping, and constitutes a part of |
| the Reactor Coolant Pressure Boundary. The unit was in Hot Shutdown |
| Operational Condition 3 at the time of discovery. |
| |
| "Technical Specification LCO 3.4.3.2.a has been entered due to leakage from |
| the Reactor Coolant Pressure Boundary, which requires the unit be in Cold |
| Shutdown by 03:32am on October 11, 2001. Cooldown to Operational Condition |
| 4 is in progress. |
| |
| "PSEG Nuclear is developing plans to repair the leak." |
| |
| The licensee described the leak as a fine spray which is much less than the |
| 10gpm averaged over a 10 minute period required to declare an Unusual Event |
| (ECG 2.1.1a, 2.1.1b). |
| |
| The licensee will inform the Lower Alloways Creek Township and the NRC |
| resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38372 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 10/10/2001|
|LICENSEE: LEIGHTON AND ASSOCIATES |NOTIFICATION TIME: 11:19[EDT]|
| CITY: IRVINE REGION: 4 |EVENT DATE: 10/08/2001|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: 3109-30 AGREEMENT: Y |LAST UPDATE DATE: 10/10/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KENT PRENDERGAST | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT |
| |
| "Licensee reported that a Troxler 3440 portable gauge containing 10 mCi of |
| cesium-137 and 50 mCi of americium-241:beryllium, in sealed sources, was |
| stolen from one of their technician's pick-up while being kept overnight at |
| the technician's home in Hemet. The gauge was in its transport case, locked |
| down in the bed of the vehicle with a 'shell.' |
| |
| "The gauge was stolen sometime after being parked at the technician' s home |
| on the evening of 10-8-01. |
| |
| "The stolen gauge was a Troxler 3440, S/N 14409." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38373 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 10/10/2001|
| UNIT: [] [2] [] STATE: AZ |NOTIFICATION TIME: 11:23[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 10/10/2001|
+------------------------------------------------+EVENT TIME: 07:45[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 |
|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 |75 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN BASED ON ASSUMED CEA |
| DEGRADATION |
| |
| "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 October 10, 2001, at approximately 07:45 MST, Palo Verde Nuclear |
| Generating Station (PVNGS) Unit 2 commenced a reactor shutdown required by |
| Technical Specification 3.0.3. |
| |
| "CEA degradation was observed during refueling of PVNGS Unit 3 and is |
| assumed to be transportable to Unit 2. As discussed in the Technical |
| Specification 3.1.5 Bases, mechanical failures may cause a CEA to become |
| inoperable. There were no reactivity anomalies in Unit 2 (or Unit 3) |
| indicating CEA degradation prior to this discovery. The condition is not |
| transportable to PVNGS Unit 1 CEAs because they were replaced during its |
| last refueling outage. |
| |
| "Preliminary investigation indicates the cause to be aging. |
| |
| "Limiting Condition for Operability (LCO) 3.1 .5 requires 'All full length |
| CEAs shall be OPERABLE..' No associated action in Technical Specification |
| 3.1.5 applies to the CEA degradation, therefore Unit 2 entered LCO 3.0.3. |
| |
| "No ESF actuations occurred and none were required. There were no |
| structures, systems, or components that were inoperable at the time of |
| discovery that contributed to this condition. There were no failures that |
| rendered a train of a safety system inoperable and no failures of components |
| with multiple functions were involved. The event did not result in the |
| release of radioactivity to the environment and did not adversely affect the |
| safe operation of the plant or health and safety of the public. |
| |
| "The NRC Resident Inspector has been notified." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38375 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/10/2001|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 15:38[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 10/10/2001|
+------------------------------------------------+EVENT TIME: 12:30[EDT]|
| NRC NOTIFIED BY: J. GROFF |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHAEL PARKER R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI INOPERABLE |
| |
| "On 10/10/01 at 12:30, while performing surveillance 24.202.01 'HPCI Pump |
| Time Response and Operability Test at 1025 psi', HPCI pump flow reached 5000 |
| gpm in 35 seconds (<29 seconds is acceptance criteria). HPCI was declared |
| INOPERABLE due to the surveillance failure. Plant personnel are evaluating |
| trend data to determine the cause of the failure. |
| |
| "All other ECCS systems and RCIC are OPERABLE. This is being reported under |
| 10CFR50.72(b)(3)(v)(D)." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
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