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Event Notification Report for December 1, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/30/1999 - 12/01/1999

                              ** EVENT NUMBERS **

36397  36474  36475  36476  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36397       |
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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 11/04/1999|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 15:06[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        11/04/1999|
+------------------------------------------------+EVENT TIME:        10:00[EST]|
| NRC NOTIFIED BY:  BRIAN STETSON                |LAST UPDATE DATE:  11/30/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| CONTROL ROD WITHDRAWAL LIMITER DISCOVERED INOPERABLE DURING ROD TESTING      |
|                                                                              |
| "It has been discovered that following the insertion of a control rod, the   |
| Rod Withdrawal Limiter is inoperable until that control rod is deselected    |
| and reselected from the Rod Control & Information System control panel.      |
|                                                                              |
| "We have reasonable knowledge that we have withdrawn control rods in the     |
| past, while the Rod Withdrawal Limiter has been inoperable. We have specific |
| knowledge that on 10/31/99, a control rod was withdrawn with the Rod         |
| Withdrawal Limiter inoperable. This is a violation of Technical              |
| Specification 3.3.2.1 Action A.1.                                            |
|                                                                              |
| "This report is required due to the requirements of the Operating License    |
| for a violation of Technical Specifications."                                |
|                                                                              |
| This condition was discovered by operators during performance of control rod |
| speed adjustment of a single rod.  Control rod motion continued past the     |
| withdrawal notch limit of 4.  The operator immediately let go of the         |
| withdraw push button causing the rod to stop at the notch 6 position.  The   |
| licensee suspects this condition has existed since initial construction and  |
| has imposed administrative controls specifically referencing Technical       |
| Specifications requirements.                                                 |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1007 ON 11/30/99 BY BRUCE LUTHENEN TO JOLLIFFE * * *         |
|                                                                              |
| Licensee engineering personnel determined that the control rod withdrawal    |
| limiter was operable at the time of the event and would have fulfilled its   |
| specific safety function.  A revised operability determination was completed |
| on 11/29/99.  Therefore, a condition prohibited by plant tech specs did not  |
| exist.  Thus, the licensee desires to retract this event and is considering  |
| submitting a licensee event report on this issue.  The licensee plans to     |
| notify the NRC Resident Inspector.                                           |
|                                                                              |
| The NRC Operations Officer notified the R3DO Geoffrey Wright.                |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36474       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 11/30/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 06:12[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        11/30/1999|
+------------------------------------------------+EVENT TIME:        04:59[CST]|
| NRC NOTIFIED BY:  DALE BERRY                   |LAST UPDATE DATE:  11/30/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|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  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| -TS REQD PLANT S/D DUE TO FAILED ESFAS AFW ACTUATION LOGIC RELAY 48 VDC      |
| POWER SUPPLY-                                                                |
|                                                                              |
| THE LICENSEE DISCOVERED A FAILED 48 VDC POWER SUPPLY FOR THE BALANCE OF      |
| PLANT ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) AUTOMATIC ACTUATION |
| LOGIC RELAYS FOR THE TRAIN 'A' AUXILIARY FEEDWATER (AFW) SYSTEM.  TECH SPEC  |
| 3.3.2, FUNCTION 6.C, ACTION 21, REQUIRES THE LICENSEE TO RESTORE THE POWER   |
| SUPPLY TO OPERABLE STATUS OR TO PLACE THE PLANT IN HOT STANDBY MODE IN 6     |
| HOURS AND HOT SHUTDOWN MODE IN THE FOLLOWING 6 HOURS.                        |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A PRESS  |
| RELEASE.                                                                     |
|                                                                              |
| * * * UPDATE AT 0837 ON 11/30/99 BY DAVE DEES TO JOLLIFFE * * *              |
|                                                                              |
| AT 0724 CST, THE LICENSEE DISCOVERED THAT THE OVERVOLTAGE CUTOUT SETPOINT ON |
| THE POWER SUPPLY HAD DRIFTED LOW AND DEENERGIZED THE POWER SUPPLY.  THE      |
| LICENSEE ADJUSTED THE SETPOINT TO ITS PROPER VALUE, RESTORED THE POWER       |
| SUPPLY TO SERVICE, DECLARED IT OPERABLE, STOPPED THE POWER REDUCTION AT 31%  |
| POWER, EXITED THE TECH SPEC ACTION STATEMENT, AND BEGAN INCREASING POWER.    |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R4DO DALE POWERS.                    |
|                                                                              |
| SEE EVENT # 36476 FOR TECH SPEC REQUIRED SHUTDOWN.                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36475       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/30/1999|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 11:02[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/30/1999|
+------------------------------------------------+EVENT TIME:        10:05[EST]|
| NRC NOTIFIED BY:  DAVE WILLIAMS                |LAST UPDATE DATE:  11/30/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Florida DEP notified about an injured loggerhead sea turtle removed from   |
| the plant intake canal -                                                     |
|                                                                              |
| At 1005 on 11/30/99, the licensee notified the Florida Department of         |
| Environmental Protection (DEP) regarding the removal of an injured adult     |
| female loggerhead sea turtle from the plant intake canal.  The injuries are  |
| not believed to be related to plant operation.  The licensee plans to        |
| transfer the turtle to a rehabilitation facility.                            |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36476       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 12/01/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 03:24[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/01/1999|
+------------------------------------------------+EVENT TIME:        02:19[CST]|
| NRC NOTIFIED BY:  JENKINS                      |LAST UPDATE DATE:  12/01/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|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  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION  REQD  SHUTDOWN DUE TO FAILED TRAIN "A" ESFAS AFW    |
| ACTUATION LOGIC RELAY 48 VDC POWER SUPPLY.                                   |
|                                                                              |
| BALANCE OF PLANT ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS)          |
| AUTOMATIC LOGIC RELAYS FOR AUXILIARY FEEDWATER 48 VDC TRAIN "A" POWER SUPPLY |
| FAILED. TECHNICAL SPECIFICATION 3.3.2, FUNCTION 6.C, ACTION 21, WAS ENTERED  |
| AT 0117CT.  AT 0119 CT THE LICENSEE ENTERED AND COMMENCED A TECHNICAL        |
| SPECIFICATION REACTOR SHUTDOWN.  REACTOR POWER IS BEING REDUCED AT LESS THAN |
| 0.5% PER MINUTE. TRAIN "B" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP AND THE     |
| TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ARE FULLY OPERABLE.   THE FAILURE OF |
| THE 48 VDC POWER SUPPLY CAUSED THE BISTABLE TO CAUSE A FUEL BUILDING         |
| ISOLATION SIGNAL, CONTROL ROOM ISOLATION VENTILATION SIGNAL, AND CONTAINMENT |
| PURGE ISOLATION SIGNAL ACTUATIONS.  THE EMERGENCY CORE COOLING SYSTEMS AND   |
| EMERGENCY DIESEL GENERATORS  ARE FULLY OPERABLE. THE ELECTRICAL GRID IS      |
| STABLE.                                                                      |
|                                                                              |
| TWO INSTRUMENT AND CONTROL TECHNICIANS HAVE BEEN CALLED IN TO INSTALL A      |
| SPARE POWER SUPPLY. THE SPARE POWER SUPPLY IN PRESENTLY IN THE RECALIBRATION |
| SHOP. THE LICENSEE PROJECTS THAT THE SPARE POWER SUPPLY SHOULD BE INSTALLED  |
| BY 0430 CT AT WHICH TIME THEY WILL EXIT THE TECHNICAL SPECIFICATION REQUIRED |
| SHUTDOWN.                                                                    |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
|                                                                              |
| SEE EVENT # 36474 FOR THE SAME EVENT CALLED IN BY THE LICENSEE ON 11/30/99   |
| AT 0612 ET.                                                                  |
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