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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
| | |
| | |
+------------------------------------------------------------------------------+
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| "We have reasonable knowledge that we have withdrawn control rods in the |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| knowledge that on 10/31/99, a control rod was withdrawn with the Rod |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 |
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| 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
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| -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. |
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|Power Reactor |Event Number: 36475 |
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| 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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