United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 1999

Event Notification Report for June 10, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/09/1999 - 06/10/1999

                              ** EVENT NUMBERS **

35706  35809  35810  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35706       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 05/12/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 16:12[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        05/12/1999|
+------------------------------------------------+EVENT TIME:        15:15[EDT]|
| NRC NOTIFIED BY:  GREEN                        |LAST UPDATE DATE:  06/09/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CURTIS COWGILL       R1      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) WAS DECLARED INOPERABLE DURING A       |
| QUARTERLY SURVEILLANCE TEST.                                                 |
|                                                                              |
| DURING THE PERFORMANCE OF THE NORMAL QUARTERLY RCIC SURVEILLANCE TEST, THE   |
| RCIC TURBINE UNEXPECTEDLY TRIPPED WHEN THE  SUCTION PATH WAS SWAPPED FROM    |
| THE SUPPRESSION POOL TO THE CONDENSATE STORAGE TANK.  THE CAUSE OF THE RCIC  |
| TURBINE TRIP IS UNKNOWN AT THIS TIME, AND TROUBLESHOOTING IS CURRENTLY IN    |
| PROGRESS.  THE PLANT IS IN A 14-DAY LIMITING CONDITION FOR OPERATION ACTION  |
| STATEMENT.                                                                   |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| ******************** UPDATE AT 1600 ON 06/09/99 FROM MITCH ALMETER TO        |
| TROCINE ********************                                                 |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "In accordance with industry guidance (i.e., NUREG-1022), Nine Mile Point    |
| reports RCIC inoperability due to an unplanned occurrence.  The              |
| inoperability reported on 05/12/99 was as a result of preplanned maintenance |
| and a system configuration which is not expected to be duplicated under      |
| design conditions.  The preplanned inoperability did not reveal any          |
| non-conformance that would have otherwise impacted RCIC operability.         |
| Therefore, the RCIC trip/inoperability was not reportable."                  |
|                                                                              |
| "This event notification is being retracted."                                |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Caruso).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35809       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 06/09/1999|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 00:26[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/09/1999|
+------------------------------------------------+EVENT TIME:        00:20[EDT]|
| NRC NOTIFIED BY:  MIKE FERGUSON                |LAST UPDATE DATE:  06/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN - BOTH CHEMICAL & VOLUME CONTROL PUMPS           |
| INOPERABLE                                                                   |
|                                                                              |
| The licensee commenced a Tech Spec required shutdown at 0020 on 6/9/99.      |
| The shutdown was terminated at 0029 when the 1A Chemical and Volume Control  |
| (CVC) charging pump was returned to an operable status.   Reactor power had  |
| been reduced to 99%.                                                         |
|                                                                              |
| On 6/7/99 at 1500, the 1A CVC charging pump was declared inoperable because  |
| the "A" Service water pump was inoperable.  At  2320 on 6/8/99, the 1B CVC   |
| charging pump was also declared inoperable because of abnormal flow.   The   |
| licensee entered Tech Spec 3.0.3 at that time, and since the condition had   |
| not been repaired by 0020 on 6/9/99, a shutdown was commenced.               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35810       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 06/09/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 17:37[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/09/1999|
+------------------------------------------------+EVENT TIME:        16:40[EDT]|
| NRC NOTIFIED BY:  ZAREMBA                      |LAST UPDATE DATE:  06/09/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN CARUSO          R1      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |FRANK CONGEL         IRO     |
|NLCO                     TECH SPEC LCO A/S      |SCOTT BARBER/REG 1   DRP     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF CONTROL POWER TO THE ECCS RESTART PROGRAM FOR AN EMERGENCY BUS       |
| DURING PERFORMANCE OF MAINTENANCE ACTIVITIES AND RESULTING TECH SPEC         |
| REQUIRED SHUTDOWN                                                            |
|                                                                              |
| At 1640 EDT on 06/09/99, the control room received an annunciator (Restart   |
| Program Control Power Loss) which indicated a loss of 125-VDC control power  |
| for the emergency core cooling system (ECCS) restart program on the 10500    |
| bus (one of two 4,160-V emergency buses).  The licensee stated that this     |
| failure removed the ability to strip the 10500 bus of loads, isolate the     |
| bus, and then automatically reload the bus with power being supplied by the  |
| applicable emergency diesel generators (EDG).  It, therefore, prevents       |
| automatic startup of certain ECCS equipment and prevents loading of the      |
| associated EDGs on low emergency bus voltage.  (The licensee stated that     |
| everything is still functional.  However, if there was a situation where the |
| bus was stripped and where an automatic restart using power from the EDGs    |
| was required, the loss of control power to the restart program would prevent |
| automatic restart of the applicable ECCS equipment.)                         |
|                                                                              |
| The unit has four EDGs; two for each 4,160-V emergency bus.  The licensee    |
| stated that the EDGs associated with the 10500 bus were already inoperable   |
| at the time of the event.  However, the 4,160-V 10600 emergency bus and its  |
| associated pair of EDGs remained operable.                                   |
|                                                                              |
| As a result of the loss of control power for the ECCS restart program, the   |
| low pressure ECCS systems associated with the 10500 bus  ('A' and 'B'        |
| residual heat removal and 'A' core spray) and the pair of EDGs associated    |
| with the 10500 bus were declared inoperable, and the licensee entered        |
| Technical Specification 3.5.a.6.  The action statement for this technical    |
| specification requires the licensee to place the unit in a Cold Shutdown     |
| condition within 24 hours.  Accordingly, a unit shutdown from 100% reactor   |
| power was commenced at 1739 EDT.  The shutdown is planned to occur at a rate |
| of 50 MWe/hour.                                                              |
|                                                                              |
| The licensee stated that maintenance activities were ongoing at the time of  |
| the event.  A breaker was being racked in for another maintenance effort on  |
| some auxiliary contacts when the 'Restart Program Control Power Loss'        |
| annunciator was received.  Apparently, the fuses that control the logic for  |
| the restart program control power are located in close proximity to the      |
| breaker that was being racked in.                                            |
|                                                                              |
| Troubleshooting activities are underway.  The licensee is currently checking |
| the switchgear fuses and supply breakers and is also initiating corrective   |
| maintenance.                                                                 |
|                                                                              |
| Other than receipt of the annunciator in the control room, there were no     |
| automatic initiations (such as actual ECCS injections or engineered safety   |
| feature actuations) associated with this event.  There was no emergency      |
| declaration.  The licensee plans to provide additional information as it     |
| becomes available (when the situation mitigates or escalates).               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| ******************** UPDATE AT 2228 ON 06/09/99 FROM PETER ABBOTT TO TROCINE |
| ********************                                                         |
|                                                                              |
| Investigation revealed that a fuse holder had lost tension and was not       |
| making proper contact.  The fuse holder was subsequently adjusted and        |
| reinstalled, and the 24-hour action statement was exited at 2219 EDT.  The   |
| licensee was maintaining reactor power at 88% and is currently in the        |
| process of evaluating whether or not power ascension can be commenced.       |
|                                                                              |
| The licensee stated that the ability to manually start the affected ECCS     |
| pumps was not lost because 4,160-V bus power was never lost.  Therefore, the |
| affected ECCS equipment could have been manually started either from the     |
| control room or locally.                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Caruso), NRR EO (Zwolinski), and IRO (Congel).    |
+------------------------------------------------------------------------------+