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 May 4, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/03/1999 - 05/04/1999

                              ** EVENT NUMBERS **

35665  35666  35667  35668  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35665       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 05/03/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 10:01[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        05/01/1999|
+------------------------------------------------+EVENT TIME:        09:00[EDT]|
| NRC NOTIFIED BY:  BRODSKY                      |LAST UPDATE DATE:  05/03/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Hot Standby      |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE MADE AN OFFSITE NOTIFICATION TO THE STATE OF CONNECTICUT        |
| DEPARTMENT OF ENVIRONMENTAL PROTECTION THAT A FISH KILL OCCURRED.            |
|                                                                              |
| On May 5, 1999, at approximately 0900 hours the licensee discovered 13 dead  |
| fish at the Unit 3 outfall.  The licensee notified the Connecticut           |
| Department of Environmental Protection of the fish kill.                     |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35666       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 05/03/1999|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 13:12[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/03/1999|
+------------------------------------------------+EVENT TIME:        10:00[EDT]|
| NRC NOTIFIED BY:  JOSEPH SULLIVAN              |LAST UPDATE DATE:  05/03/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ONE HIGH HEAD SAFETY INJECTION LINE DETERMINED NOT TO HAVE FLOW DURING       |
| TESTING                                                                      |
|                                                                              |
| "During performance of the 18 month high head charging valve throttle test,  |
| it was discovered that the #21 high head cold leg injection line did not     |
| pass flow until the other three lines for high head cold leg injection were  |
| closed.  At that point, an audible indication was heard and flow was         |
| observed through the #21 cold leg.  All cold leg injection flows were        |
| subsequently balanced.  The cause of this is under investigation and will be |
| resolved prior to Mode 4."                                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector and will be notifying the   |
| local government agencies.                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35667       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 05/03/1999|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 21:45[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        05/03/1999|
+------------------------------------------------+EVENT TIME:        19:51[CDT]|
| NRC NOTIFIED BY:  PAUL SALGADO                 |LAST UPDATE DATE:  05/03/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MONTE PHILLIPS       R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFETY VALVE INOPERABLE ALARM                                                |
|                                                                              |
| The inoperable alarm was received for the '3A Target Rock Safety Valve'      |
| which is an indication that the safety function of this valve is inoperable. |
| It is probably a failed bellows, thus replacement of valve will be required. |
| This is a degraded condition per the licensee's reportability manual.        |
|                                                                              |
| The failure of the safety function puts the unit in a 12 hour to hot         |
| shutdown (Mode 3) and 24 hours to cold shutdown (Mode 4) per Technical       |
| Specification action statement 3.6.e.1.  The plant will stay in Mode 4 until |
| repairs are completed.  Actual plant shutdown will commence after all        |
| preparations are completed.                                                  |
|                                                                              |
| The licensee will notify the NRC Resident Inspector.                         |
|                                                                              |
| HEADQUARTERS OPERATION CENTER NOTE:  NOED was granted to the licensee at     |
| 0317 EDT on 05/04/99 to remain at power.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35668       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 05/04/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 00:09[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        05/03/1999|
+------------------------------------------------+EVENT TIME:        23:30[EDT]|
| NRC NOTIFIED BY:  DOUGLAS J. GOMEZ             |LAST UPDATE DATE:  05/04/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|10 CFR SECTION:                                 |CECIL THOMAS         NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |CHARLES MILLER       IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       90       Power Operation  |85       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION SHUTDOWN DUE TO THREE OUT OF FOUR OVERTEMPERATURE    |
| DELTA TEMPERATURE AND OVERPOWER DELTA POWER CHANNELS BEING DECLARED          |
| INOPERABLE.                                                                  |
|                                                                              |
| During calibrations of Protection Channels it was determined that 3 out of 4 |
| Overtemperature and Overpower  Delta Channels were inoperable requiring      |
| entry into Technical Specification 3.0.3 requiring Mode 3 (Hot Standby)      |
| within 6 hours (0530 EDT on 05/04/99).                                       |
|                                                                              |
| The summer coming out of the Delta Temperature Channels are superimposing an |
| AC ripple on top of the DC output and depending on whether it is feeding out |
| through an NUS bistable or Foxboro bistable the Foxboro bistable apparently  |
| allows the AC ripple to continue through and cause the  Delta Temperature    |
| Setpoints to be non-conservative.  The licensee did not know when the last   |
| time a surveillance test had been performed on the channels.                 |
|                                                                              |
| All Emergency Core Cooling Systems, and the Emergency Diesel Generators are  |
| fully operable. The electrical grid is stable.                               |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| **** Update on 05/04/99 at 0442 EDT by Dan Berry taken by MacKinnon ****     |
|                                                                              |
| The licensee exited Technical Specification 3.0.3 at 0437 EDT when 3         |
| Channels were declared operable and the fourth channel was defeated          |
| (bistables were tripped).   Reactor power level was reduced to 21% before    |
| Technical Specification 3.0.3 was exited. The licensee will increase reactor |
| power level to between 30 to 35 percent at which point they will stabilize   |
| reactor power level and repair a steam leak on MSR "2B".                     |
| R1DO (Jim Linville) notified.                                                |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+