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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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).            |
+------------------------------------------------------------------------------+