Event Notification Report for October 18, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/15/1999 - 10/18/1999
** EVENT NUMBERS **
36249 36294 36295 36296 36297 36298 36299 36300 36301 36302 36303 36304
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36249 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/01/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 03:19[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/30/1999|
+------------------------------------------------+EVENT TIME: 23:30[EDT]|
| NRC NOTIFIED BY: STEVE SAUER |LAST UPDATE DATE: 10/15/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RHR PUMP DISCHARGE VALVE FAILED TO CLOSE ON DEMAND. |
| |
| The #12 Residual Heat Removal (RHR) pump motor operated discharge valve |
| failed to close upon demand. This valve is required by Emergency Operating |
| Procedures to be closed during cold leg recirculation to provide long term |
| containment spray. The cause of the failure is currently under |
| investigation. |
| |
| The licensee plans to inform the NRC resident inspector and Lower Alloways |
| Creek Township. |
| |
| * * * RETRACTION AT 1201 ON 10/15/1999 FROM SAUER TAKEN BY STRANSKY * * * |
| |
| "Further evaluation of the function of the 12 [RHR] pump discharge (12SJ49) |
| has determined that the failure of the valve to stroke in the closed |
| direction could not alone have prevented fulfillment of its safety function. |
| NUREG 1022, page 66, states that in determining reportability of an event or |
| condition it is not necessary to assume an additional random failure in that |
| system. Without an additional failure, both trains of RHR would have been |
| available. |
| |
| "Although the emergency operating procedures are not specific, aligning the |
| other loop for containment spray and leaving the failed SJ49 aligned for |
| cold leg injection would be the expected action." |
| |
| The NRC resident inspector has been informed of this retraction. The NRC |
| operations officer notified the R1DO (Noggle). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36294 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/15/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 07:49[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/15/1999|
+------------------------------------------------+EVENT TIME: 07:40[EDT]|
| NRC NOTIFIED BY: JIM BROOKS |LAST UPDATE DATE: 10/15/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF PLANT PAGING SYSTEM |
| |
| The plant paging system was found to be inoperable. Technicians are |
| troubleshooting the system. Radios were distributed to the plant operators |
| as a means of backup communication. |
| |
| The licensee plans to notify the NRC Resident Inspector and the State of |
| Vermont Nuclear Engineer. |
| |
| * * * UPDATE AT 1026 ON 10/15/1999 FROM BROOKS TAKEN BY STRANSKY * * * |
| |
| The plant paging system has been restored. |
| |
| The NRC resident inspector has been informed of this update by the licensee. |
| The NRC operations officer notified the R1DO (Noggle). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36295 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/15/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 12:50[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/15/1999|
+------------------------------------------------+EVENT TIME: 09:10[CDT]|
| NRC NOTIFIED BY: OSLAND |LAST UPDATE DATE: 10/15/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: |JOHN ZWOLINSKI NRR |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| MEDIA INTEREST - FIRE AND EXPLOSION ONE MILE FROM PLANT SITE |
| |
| The licensee received notification at approximately 0910 CDT today |
| concerning an explosion and fire at the 3M Manufacturing Facility which is |
| located approximately one mile north of Quad Cities Nuclear Power Station. |
| The explosion and fire occurred in a building containing flammables and |
| paint. There has been news media interest, and the Rock Island County |
| emergency officials have been notified. The latest report is that the fire |
| is terminated and the there are no toxic fumes. The U.S. Coast Guard has |
| closed traffic on the Mississippi River. The licensee remains in close |
| contact with the county officials, and the licensee has been providing |
| support to the facility with equipment and personnel. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36296 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/15/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 13:09[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 10/15/1999|
+------------------------------------------------+EVENT TIME: 10:00[EDT]|
| NRC NOTIFIED BY: BILL BANDHAUSER |LAST UPDATE DATE: 10/15/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF THE 'A' ONCE-THROUGH STEAM GENERATOR (OTSG) TUBES ARE |
| DEFECTIVE. |
| |
| Plant personnel determined that the inspection of the 'A' OTSG found 10 of |
| 528 tubes to have "indication of a defect" using the plus point probe |
| inspection of the lower tube sheet secondary face ding/dent population. |
| |
| Because there is no qualified sizing technique for circumferential |
| crack-like or volumetric indications in this region, it cannot be |
| demonstrated that the through-wall depth penetration of these indications is |
| less than 40% of the tube wall. Therefore, the tubes containing these |
| indications must be classified as "Defective." |
| |
| Since more than 1% of the sample size was determined to be defective, the |
| inspection result is classified as "C-3" as defined in paragraph |
| 5.6.2.10.2.f of the Crystal River Unit 3 Improved Technical Specifications |
| (ITS). |
| |
| Table 5.6.2-2 of Crystal River Unit 3 ITSs requires that this "C-3" result |
| be reported to the NRC per 10 CFR 50.72. |
| |
| This condition is considered to be a serious degradation of a principal |
| safety barrier (Reactor Coolant System) discovered while shutdown. |
| |
| Prior to the current Crystal River Unit 3 plant shutdown on 10/01/99, the |
| actual primary to secondary leakage through the 'A' OTSG was significantly |
| below the allowable limit of ITS 3.4.12.d (less that 150 gallons per day). |
| |
| The NRC Resident Inspector was notified of this event notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36297 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 10/15/1999|
|LICENSEE: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION TIME: 15:59[EDT]|
| CITY: Minneapolis REGION: 3 |EVENT DATE: 10/04/1998|
| COUNTY: STATE: MN |EVENT TIME: 12:00[CDT]|
|LICENSE#: 42-23539-01A AGREEMENT: N |LAST UPDATE DATE: 10/15/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN MADERA R3 |
| |GAIL GOOD R4 |
+------------------------------------------------+SCOTT MOORE NMSS |
| NRC NOTIFIED BY: JULIE COLEMAN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSING TWO LENSATIC COMPASSES WHICH EACH CONTAIN 190 mCi OF TRITIUM |
| |
| BACK IN EARLY OCTOBER OF 1998, TWO LENSATIC COMPASSES WERE SHIPPED IN AN |
| COMMUNICATIONS EQUIPMENT TOOLBOX TO CAMP RIPLEY, MN, FOR A DEPLOYMENT |
| EXERCISE. EACH LENSATIC COMPASS CONTAINED 190 mCi OF TRITIUM. DURING AN |
| ANNUAL INVENTORY DURING THE MONTH OF AUGUST OF 1999, IT WAS DISCOVERED THAT |
| THESE TWO LENSATIC COMPASSES WERE MISSING. THE UNIT (934 COMMUNICATIONS |
| FLIGHT UNIT) SEARCHED THROUGH ALL THEIR EQUIPMENT, AND THE TOOLBOX |
| CONTAINING THE COMPASSES WAS NOT FOUND. THE USAF UNIT REPORTED THE |
| COMPASSES MISSING ON SEPTEMBER 16, 1999, TO THEIR COMMAND. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36298 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 10/16/1999|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 06:08[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 10/16/1999|
+------------------------------------------------+EVENT TIME: 02:53[PDT]|
| NRC NOTIFIED BY: NEIL SCHEUERLEIN |LAST UPDATE DATE: 10/16/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |GAIL GOOD R4 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
| |CARR FEMA |
| |WILLIAM BRACH NMSS |
| |TED MICHAELS REXB |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO EARTHQUAKE LOCATED ABOUT 100 MILES FROM SITE. |
| (Refer to event #36299 for a related event at Palo Verde.) |
| |
| An earthquake of magnitude 7.0 occurred at 0247 PDT at coordinates 34 |
| degrees 35.73 minutes north, 116 degrees 16.09 minutes west. This location |
| is about 32 miles north of Joshua Tree, California, and 47 miles |
| east-southeast of Barstow, California. This information is from the U.S. |
| Geological Survey Southern California Seismic Network. |
| |
| The licensee felt the earthquake, which was followed by the seismic alarms |
| actuating. The plants are in operation with no problems. Inspections were |
| carried out per procedures as well as the declaration of the Unusual Event |
| at 0253 PDT. The licensee expects to be out of the Unusual Event in less |
| than 1 hour. |
| |
| The licensee notified the NRC Resident Inspector and state/local |
| authorities. |
| |
| * * * UPDATE AT 0635 EDT ON 10/16/99 FROM NEIL SCHEUERLEIN TO FANGIE JONES * |
| * * |
| |
| The licensee exited the Unusual Event at 0330 PDT on 10/16/99. |
| |
| The licensee notified the NRC Resident Inspector and state/local |
| authorities. The NRC operations officer notified R4DO (Gail Good), NRR EO |
| (William Bateman), IRO (Frank Congel), and FEMA (Carr). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36299 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 10/16/1999|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 06:55[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 10/16/1999|
+------------------------------------------------+EVENT TIME: 03:05[MST]|
| NRC NOTIFIED BY: JIM BLAZICK |LAST UPDATE DATE: 10/18/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |GAIL GOOD R4 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |RICHE FEMA |
| |WILLIAM BRACH NMSS |
| |TED MICHAELS REXB |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO EARTHQUAKE FELT ON SITE. (Refer to event |
| #36298 for a related event at San Onofre.) |
| |
| An earthquake of magnitude 7.0 occurred at 0247 MST at coordinates 34 |
| degrees 35.73 minutes north, 116 degrees 16.09 minutes west. This location |
| is about 32 miles north of Joshua Tree, California, and 47 miles |
| east-southeast of Barstow, California. This information is from the U.S. |
| Geological Survey Southern California Seismic Network. |
| |
| The licensee felt the earthquake, and the strong motion accelerometer |
| alarmed. An approximate intensity level of 0.015g's has been determined. |
| Unit 1 is defueled, and Units 2 and 3 are in operation with no problems. |
| Inspections were carried out per procedures as well as the declaration of |
| the Unusual Event. Engineering walkdowns and evaluations are in progress |
| per procedure. |
| |
| The Unusual Event was entered and exited at 0305 MST. |
| |
| The licensee notified the NRC Resident Inspector as well and state/local |
| authorities. |
| |
| ***************** UPDATE AT 0100 EDT ON 10/18/99 FROM DANN DAILEY TO LEIGH |
| TROCINE ***************** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "This is a followup of the ENS notification at 0353 MST on 10/16/99. 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, another followup notification will be made via the |
| ENS or under the reporting requirements of 10CFR50.73." |
| |
| "On [10/16/99], at approximately 0247 MST, an earthquake, referred to as the |
| 'Hector Earthquake,' of approximate magnitude 7.0 occurred, its epicenter |
| located about 32 miles north of Joshua Tree, California. Joshua Tree, |
| California is located approximately 220 miles west of the Palo Verde Nuclear |
| Generating Station. At approximately 0248 MST, the vibratory ground motion |
| reached and actuated the Palo Verde Seismic Monitoring Instrumentation |
| switches. Specifically, the strong motion accelerometer trigger located in |
| the Unit 1 containment building tendon gallery exceeded the threshold value |
| of 0.01g. The vibratory ground motion also was felt by personnel in all |
| three Palo Verde control rooms. Operations personnel immediately retrieved |
| data from the actuated instrument and performed analysis to determine the |
| magnitude of the vibratory ground motion. Initial analysis of the Seismic |
| Monitoring Instrumentation tape recordings completed at approximately 0305 |
| MST indicated a seismic event of about 0.015g. This is well below the |
| magnitude of the 0.10g spectra Operating Basis Earthquake (OBE) and the |
| 0.20g spectra Safe Shutdown Earthquake (SSE). Based on the validation of |
| the earthquake per the Emergency Action Level 6.6 Technical Bases, the Unit |
| 1 Shift Manager declared (and immediately exited due to the event being |
| over) a Notification of an Unusual Event (NUE) applicable to all three units |
| due to a seismic event." |
| |
| "The NRC was notified at 0353 MST on 10/16/99 via the Emergency Notification |
| System (ENS). The criteria for the ENS notification were |
| 10CFR50.72(a)(1)(i) due to the declaration of an Emergency Class and |
| 10CFR50.72(b)(1)(iii) due to the natural phenomenon that poses an actual |
| threat to the safety of the nuclear power plant. Further analysis of the |
| seismic data concluded the measured motions of structures and components |
| were less than 14% of the OBE and should have no effect upon facility |
| features important to safety. Based on the low magnitude of the vibratory |
| ground motion and satisfactory plant walkdowns, an actual threat to safety |
| did not exist. The ENS notification per 10CFR50.72(b)(1)(iii) is hereby |
| retracted. The initial notification stated a press release was expected to |
| be made; therefore, 10CFR50.72(b)(2)(vi) also applied. No media interest |
| existed; therefore, no press release was made. The ENS notification per |
| 10CFR50.72(a)(1)(i) remains valid." |
| |
| "Following declaration of the NUE, the Maricopa County Sheriff's Office and |
| the Arizona Department of Public Safety were notified at approximately 0313 |
| MST via the Notification and Alert Network (NAN). The Palo Verde Emergency |
| Coordinator recommended that no protective actions be taken. No protective |
| actions were implemented by state or county agencies." |
| |
| "Operations personnel performed an immediate walkdown of plant equipment. |
| No abnormalities caused by the seismic event were observed. There were no |
| structures, systems, or components that were inoperable that contributed to |
| this event. There were no failures that rendered a train of a safety system |
| inoperable, and no failures of components with multiple functions were |
| involved. No engineered safety feature (ESF) actuations occurred, and none |
| were required. The event did not result in any challenges to the fission |
| product barrier or result in any releases of radioactive materials. The |
| event did not adversely affect the safe operation of the plant or health and |
| safety of the public." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R4DO (Good), NRR EO (Bateman), and IRO (Congel). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36300 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/16/1999|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 12:06[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/16/1999|
+------------------------------------------------+EVENT TIME: 11:35[EDT]|
| NRC NOTIFIED BY: JOEL GORDON |LAST UPDATE DATE: 10/17/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |CAUDLE JULIAN R2 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |DEPUY FEMA |
| |FRANK CONGEL IRO |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO THE NATIONAL WEATHER SERVICE ISSUING A |
| HURRICANE WARNING FOR THEIR AREA. (Refer to event #36302 for a related |
| event.) |
| |
| THE LICENSEE ENTERED EMERGENCY PLAN IMPLEMENTING PROCEDURE 2.6.21 (ADVERSE |
| WEATHER, ETC.) AND ABNORMAL OPERATING PROCEDURE 13 (ADVERSE WEATHER, ETC.) |
| AFTER THE NATIONAL WEATHER SERVICE ISSUED A HURRICANE WARNING FOR THEIR |
| AREA. HURRICANE IRENE IS AT LEAST 20 HOURS FROM THEIR LOCATION. ALL THEIR |
| EMERGENCY CORE COOLING SYSTEMS AND EMERGENCY DIESEL GENERATORS ARE FULLY |
| OPERABLE IF NEEDED, AND THEIR ELECTRICAL GRID IS STABLE. |
| |
| CURRENTLY, WIND DIRECTION IS FROM 043 DEGREES, WIND SPEED IS 10.7 mph, THE |
| STABILITY CLASS IS 'D,' AND THERE IS NO PRECIPITATION. BOTH UNITS HAVE TO |
| BE IN HOT SHUTDOWN 2 HOURS PRIOR TO HURRICANE FORCE WINDS REACH THE SITE. |
| |
| THE LICENSEE HAS NOTIFIED THE UNITED STATES COAST GUARD, STATE OF NORTH |
| CAROLINA, AND LOCAL SURROUNDING COUNTIES OF THEIR EMERGENCY DECLARATION. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. |
| |
| * * * UPDATE AT 2328 EDT ON 10/17/99 BY JUDITH DANIEL TO FANGIE JONES * * * |
| |
| The Unusual Event was terminated at 2313 EDT. The plant is stable and |
| suffered no damage due to the hurricane. |
| |
| The licensee notified the NRC Resident Inspector. The NRC operations center |
| notified the R2DO (Caudle Julian), NRR EO (William Bateman), and FEMA |
| (Bagwell). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36301 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 10/16/1999|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 18:06[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/16/1999|
+------------------------------------------------+EVENT TIME: 14:28[CDT]|
| NRC NOTIFIED BY: B HUBBARD |LAST UPDATE DATE: 10/16/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DURING TESTING OF THE TRAIN "B" (1EA2) 6.9kV BUS, THE ALTERNATE POWER SUPPLY |
| BREAKER FAILED TO CLOSE AND THE BUS WAS LOCKED OUT. |
| |
| The loss of voltage due to the lockout of the 1EA2 6.9kV bus caused a loss |
| of power to the containment particulate iodine gaseous (PIG) monitor which |
| actuated a CVI (containment ventilation isolation). The containment |
| ventilation was already isolated, so no valves repositioned. The blackout |
| sequencer also received an undervoltage actuation. This caused several |
| operator lockouts including a turbine-driven auxiliary feedwater start |
| signal, which was out of service, and a trip of one of the two operating |
| spent fuel pool cooling pumps. The second spent fuel pool cooling pump was |
| returned to service about 40 minutes after it had initially lost power. |
| Spent fuel pool temperature increased from approximately 104 degrees F to |
| about 106 degrees F during the time period that the second spent fuel pool |
| cooling pump was de-energized. About 0.25% of the fuel has been reloaded |
| back into Comanche Peak Unit 1's core. |
| |
| The sequencer was de-energized to prevent any unnecessary actuations. The |
| train "B," 1EA2, 6.9kV bus was re-energized from the normal offsite source, |
| and the spent fuel pool cooling pump was restarted. The residual heat |
| removal system was energized from the train "A," 1EA1, 6.9kV bus, and its |
| operation was not interrupted by the loss of train the "B," 1EA2, 6.9kV bus. |
| The train "B," 1EA2, 6.9kV bus emergency diesel generator is tagged out of |
| service for maintenance. |
| |
| The cause of the bus lockout is under investigation. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36302 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/17/1999|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 09:37[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/17/1999|
+------------------------------------------------+EVENT TIME: 08:38[EDT]|
| NRC NOTIFIED BY: DAVID JENKINS |LAST UPDATE DATE: 10/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: |JAMES HUFHAM, REG 2 IRC |
|APRE 50.72(b)(2)(vi) 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING THE OPENING OF STORM DRAIN BASIN BYPASS |
| VALVES IN PREPARATION FOR THE POTENTIAL ONSET OF HURRICANE IRENE (Refer to |
| event #36300 for additional information.) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "EVENT: On October 17, 1999, at 0838, the bypass valves from the site's |
| storm drain basin directly to the circulating water discharge canal were |
| opened to prevent site flooding (which could cause significant damage to |
| plant equipment and/or possibly endanger personnel safety) due to the |
| potential arrival of Hurricane Irene. Past experience has shown that the |
| installed pump capacity will not keep up with the rain expected during a |
| hurricane. The valves were opened prior to hurricane force winds reaching |
| the site to avoid exposing personnel to the hurricane. Opening these valves |
| is reportable to he state of North Carolina in accordance with the site |
| National Pollutant Discharge Elimination System permit (Permit No. |
| NC0007064)." |
| |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION: None - Opening these bypass valves |
| will allow storm water from the hurricane to flow directly from the storm |
| drain collection basin to the discharge canal without radiological/chemical |
| monitoring at the stabilization pond. The contents of the basin were |
| sampled prior to opening the bypass valves." |
| |
| "CORRECTIVE ACTION(S): These bypass valves will be closed as soon as |
| installed systems can cope with the rainfall on site and winds have |
| decreased to a safe level to send personnel out to close them." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36303 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 10/17/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 14:24[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/17/1999|
+------------------------------------------------+EVENT TIME: 13:32[EDT]|
| NRC NOTIFIED BY: ED HYNE |LAST UPDATE DATE: 10/17/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INTEGRATED LEAK TEST FAILURE IN THE REACTOR BUILDING CLOSED COOLING WATER |
| SYSTEM |
| |
| "Failure of IST [Integrated System Test] testing for RBCLC [reactor building |
| closed loop cooling] containment isolation AOVs resulted in performance of |
| 'as-found' Type-C LLRT. Results of local leak test was 'gross' failure. |
| The failure was determined from inability to obtain test pressure and |
| quantify leakage. Based on these results, it is assumed Tech Spec allowable |
| containment leakage has been exceeded." |
| |
| The plant will remain shutdown until repairs are made. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36304 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/17/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 20:13[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/17/1999|
+------------------------------------------------+EVENT TIME: 19:22[EDT]|
| NRC NOTIFIED BY: BRIAN HAY |LAST UPDATE DATE: 10/17/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |JAMES NOGGLE R1 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
| |GARY BELCHER FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT BASED ON UNIDENTIFIED RCS LEAK GREATER THAN 10 GPM INSIDE |
| CONTAINMENT |
| |
| An Unusual Event was declared at 1954 EDT due to unidentified or pressure |
| boundary leakage from the reactor coolant system (RCS) greater than 10 gpm, |
| estimated at about 16 gpm, in the containment. At the time, there were |
| personnel in the containment that heard the leak occur and saw steam issuing |
| from a transmitter room. All personnel were evacuated from the containment. |
| There was only a slight increase in radiation indications on containment |
| monitors with no alarms. The leak appears to be from a loop-3 flow |
| transmitter from indications on the control boards. |
| |
| There was no release of radioactive material to the environment. |
| |
| The licensee notified the NRC Resident Inspector and state/local |
| authorities. |
| |
| * * * UPDATE AT 2100 EDT ON 10/17/99 FROM BRIAN HAY TO FANGIE JONES * * * |
| |
| The Unusual Event was terminated at 2050 EDT. The leak was isolated, it was |
| on an RCS loop-3 flow transmitter. |
| |
| The licensee notified the NRC Resident Inspector and state/local |
| authorities. The NRC operations center notified the R1DO (James Noggle), |
| NRR EO (William Bateman), IRO (Frank Congel), and FEMA (Bagwell). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021