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Event Notification Report for January 10, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/07/2000 - 01/10/2000

                              ** EVENT NUMBERS **

36568  36569  36570  36571  36572  36573  

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|Power Reactor                                    |Event Number:   36568       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 01/07/2000|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 09:29[EST]|
|   RXTYPE: [3] CE                               |EVENT DATE:        01/07/2000|
+------------------------------------------------+EVENT TIME:        07:30[CST]|
| NRC NOTIFIED BY:  OSCAR PIPKINS                |LAST UPDATE DATE:  01/07/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT FIRE SYSTEM FPM-18 HAD BEEN OPERATING OUTSIDE THE PLANT       |
| DESIGN BASIS                                                                 |
|                                                                              |
| "[At 0730 CST on 01/07/00], with the plant operating at 100% power, the      |
| licensee determined that Fire System FPM-18 had been operating outside the   |
| plant design basis due to having a sprinkler system pressure and flow demand |
| that could exceed the water supply capability (fire pumps).  [Fire] System   |
| FPM-18 was found to be deficient by over 170 psi.  The fire area (RAB-6) is  |
| an electrical penetration area located at the +35[-foot elevation] of the    |
| Reactor Auxiliary [Building].  This area has cables from both trains located |
| therein.  The 'B' Train is the protected train, with [1-hour] fire wrap.     |
| This area is also provided with [fire] detection and suppression.  Ongoing   |
| determinations found the fire loading in the fire area to exceed the         |
| [1-hour] fire rating of the cable fire wrap.  At that point, it was          |
| determined that a fire in that area could result in not being able to        |
| achieve safe shutdown.  The system had been declared inoperable on           |
| [01/05/00,] and compensatory measures [including the posting of a continuous |
| fire watch] were established.  There was no actual fire event involved, so   |
| there had been no actual impact on health and safety as a result of this     |
| condition."                                                                  |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36569       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 01/07/2000|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 10:58[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        01/07/2000|
+------------------------------------------------+EVENT TIME:        08:29[EST]|
| NRC NOTIFIED BY:  JEFF GROFF                   |LAST UPDATE DATE:  01/07/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT ENTERED TECH SPEC 3.0.3 AFTER BOTH SUBSYSTEMS OF THE LOW PRESSURE       |
| COOLANT INJECTION (LPCI) SYSTEM WERE RENDERED INOPERABLE DURING MAINTENANCE  |
| ACTIVITIES.                                                                  |
|                                                                              |
| "At 0829 on 1/7/2000, the E1150-F015A Division I Low Pressure Core Injection |
| (LPCI) Inboard Isolation Valve lost power.  The Fermi 2 Accident Analysis    |
| takes credit for the operation of the E1150-F015A with the initiation of     |
| 'LPCI Loop Select Logic,' to inject with both divisions of LPCI during a     |
| [loss of coolant accident (LOCA)].  With the E1150-F015A inoperable, both    |
| Division 1 and Division 2 LPCI subsystems were declared Inoperable.  T.S.    |
| 3.5.1 and T.S. 3.0.3 were immediately entered.  Operators were dispatched to |
| the [motor control center (MCC)] area and reported that MCC 72CF position 2C |
| was in the open position.  [An] operator noted maintenance activities in the |
| area and no damage to the MCC.                                               |
|                                                                              |
| "At 0837, the MCC was re-energized, restoring power to the E1150-F015A, and  |
| T.S. 3.5.1 and 3.0.3 were exited.  Currently, all maintenance activities in  |
| the vicinity of the MCC area have been put on hold pending investigation.    |
|                                                                              |
| "During the time of this event, [the] Division I Core Spray System was in a  |
| scheduled maintenance outage.                                                |
|                                                                              |
| "This event is being reported under 10CFR50.72(b)(2)(iii)(D), 'Any event or  |
| condition that alone could have prevented the fulfillment of the safety      |
| function of structures or systems needed to: D) Mitigate the consequences of |
| an accident'."                                                               |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36570       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 01/07/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 15:51[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/07/2000|
+------------------------------------------------+EVENT TIME:        12:00[CST]|
| NRC NOTIFIED BY:  VERNON CARLSON               |LAST UPDATE DATE:  01/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OBSERVATION OF UNUSUAL CAVITATION NOISE AND VIBRATION OF THE HIGH PRESSURE   |
| CORE SPRAY PUMP DURING QUARTERLY INSERVICE TESTING (IST)                     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During the quarterly IST surveillance on the high pressure core spray pump, |
| unusual cavitation noise and vibration was observed.  Abnormal low suction   |
| pressure alarms were also noted.  These conditions could not be explained,   |
| and therefore, the high pressure core spray pump was declared inoperable,    |
| and plant engineering was contacted to investigate.  The data collected on   |
| the surveillance test was satisfactory including vibration readings.  The    |
| abnormal conditions were noted during system realignment for continuation of |
| the testing."                                                                |
|                                                                              |
| The cause of the unusual cavitation noise and vibration of the high pressure |
| core spray pump is currently under investigation.  In accordance with        |
| Technical Specification 3.5.1, the reactor core isolation cooling system was |
| verified to be operable within one hour.  Technical Specification 3.5.1 also |
| requires the licensee to restore the high pressure core spray system to an   |
| operable status within 14 days or place the unit in Cold Shutdown.  The      |
| licensee stated that all other emergency core cooling systems are currently  |
| operable.                                                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36571       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  HOWARD UNIVERSITY                    |NOTIFICATION DATE: 01/07/2000|
|LICENSEE:  HOWARD UNIVERSITY                    |NOTIFICATION TIME: 16:45[EST]|
|    CITY:  WASHINGTON               REGION:  1  |EVENT DATE:        01/07/2000|
|  COUNTY:                            STATE:  DC |EVENT TIME:        16:00[EST]|
|LICENSE#:  08-00386-19           AGREEMENT:  N  |LAST UPDATE DATE:  01/07/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GLENN MEYER          R1      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GREGORY TALLEY               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INFORMATION REPORT REGARDING A FAILURE TO FOLLOW PROCEDURES FOR RECEIPT OF   |
| RADIOACTIVE MATERIAL (3 mCi OF TRITIUM) AT HOWARD UNIVERSITY IN WASHINGTON   |
| D.C.                                                                         |
|                                                                              |
| On 07/02/99, 3 mCi of tritium was transferred from George Washington         |
| University to Howard University using a private vehicle, and the Radiation   |
| Safety Office at Howard University was not notified until today (01/07/00)   |
| at 1630.  An individual brought the material with him when he transferred    |
| from George Washington University to Howard University and locked the        |
| material in a laboratory.  Apparently, this individual had the mistaken      |
| understanding that the material could remain in his laboratory until he      |
| became an authorized user.  After completing his training and becoming an    |
| authorized user, the individual informed the Radiation Safety Officer at     |
| Howard University (on 01/02/00) that he had brought 3 mCi of tritium with    |
| him from George Washington University (on 07/02/99).                         |
|                                                                              |
| The licensee stated that all of the paperwork for the transfer of the        |
| material was in order and that the Radiation Safety Office at George         |
| Washington University was informed of the transfer of radioactive material   |
| at the time of the transfer.  Between 07/02/99 and 01/02/00, the tritium was |
| locked in a laboratory at Howard University.  It was still in its original   |
| container.                                                                   |
|                                                                              |
| Call the NRC operations officer for a licensee contact telephone number.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36572       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 01/07/2000|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 21:24[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/07/2000|
+------------------------------------------------+EVENT TIME:        18:07[CST]|
| NRC NOTIFIED BY:  STEVEN SEWELL                |LAST UPDATE DATE:  01/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BLAIR SPITZBERG      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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF TRANSFORMER XST1 (ONE OF TWO OFFSITE POWER SOURCES TO THE CLASS-1E   |
| BUSES)                                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 1807 CST, Comanche Peak experienced a loss of power to transformer XST1  |
| (one of two offsite power sources to  class 1E buses).  Unit 2 momentarily   |
| [lost] power to [the] train 'A' and 'B' safeguards buses due to the          |
| [automatic] transfer to alternate offsite power.  [The] train 'A' and 'B'    |
| blackout sequencers operated to realign [engineered safety feature (ESF)]    |
| equipment.  [The] train 'A,' [train] 'B,' and turbine-driven auxiliary       |
| feedwater pumps started due to the blackout signal.  All safeguards          |
| equipment responded as designed."                                            |
|                                                                              |
| "Currently, ESF equipment has been restored to a normal lineup[, and         |
| transformer] XST2 is supplying offsite [Class-1E] power to [both Units] 1    |
| and 2.  An investigation into the cause of the event is in progress."        |
|                                                                              |
| "The NRC resident inspector has been notified."                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36573       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 01/08/2000|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 19:58[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        01/08/2000|
+------------------------------------------------+EVENT TIME:        16:31[EST]|
| NRC NOTIFIED BY:  E. V. McEVOY                 |LAST UPDATE DATE:  01/08/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TURBINE TRIP FOR UNKNOWN REASONS RESULTING IN AN AUTOMATIC REACTOR SCRAM     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 1631, Unit 2 received a main turbine trip signal and [an automatic]      |
| reactor scram [from 100% power.]  All systems operated as designed.  The     |
| investigation into the turbine trip is ongoing.  There was no release of     |
| radiation to the environment."                                               |
|                                                                              |
| The licensee stated that all rods fully inserted upon receipt of the reactor |
| scram.  There was no pressure transient.  Reactor vessel level decreased to  |
| approximately +10" and recovered to approximately +30".  (The reactor scram  |
| setpoint is at +12.5", and the emergency core cooling system actuation       |
| setpoint is at -38".)  There were no engineered safety feature (ESF)         |
| actuations (other than the reactor scram), and none were required.  The      |
| licensee also stated that there were no turbine-related maintenance or       |
| surveillance activities ongoing at the time of the event.  An AC bus outage  |
| was commenced the previous night.                                            |
|                                                                              |
| The unit is currently stable in Mode 3 (Hot Shutdown).  Normal condensate    |
| and feedwater is being supplied to the reactor vessel, and steam is being    |
| dumped to the main condenser.  There was no adverse effect on containment    |
| parameters.                                                                  |
|                                                                              |
| The licensee notified the NRC resident inspector as well as applicable state |
| and local agencies.                                                          |
|                                                                              |
| ******************** UPDATE AT 2338 ON 01/08/00 FROM PHIL CHASE TO LEIGH     |
| TROCINE ********************                                                 |
|                                                                              |
| The licensee updated this event notification to clarify that there was an    |
| ESF actuation.  The end of cycle recirculation pump trip breakers opened as  |
| designed on the turbine trip.                                                |
|                                                                              |
| The NRC operations officer notified the R1DO (Meyer).                        |
+------------------------------------------------------------------------------+