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Event Notification Report for January 14, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/13/2000 - 01/14/2000

                              ** EVENT NUMBERS **

36358  36547  36570  36585  36586  36587  36588  36589  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36358       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 10/28/1999|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 03:45[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        10/28/1999|
+------------------------------------------------+EVENT TIME:        03:35[EDT]|
| NRC NOTIFIED BY:  BENDER                       |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |DAVID LEW            R1      |
|10 CFR SECTION:                                 |DAVID MATTHEWS       NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |CHARLES MILLER       IRO     |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |ROBERTA WARREN       IAT     |
|NOCM                     COMM ASST BRIEF        |RICHARD ROSANO       IAT     |
|                                                |GREG SMITH           IAT     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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       21       Power Operation  |21       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO BOMB THREAT                                    |
|                                                                              |
| Contact the NRC Operations Center for additional details. The NRC resident   |
| inspector will be informed.                                                  |
|                                                                              |
| * * * COMMISSIONERS' ASSISTANTS BRIEFING HELD AT 0630 EDT * * *              |
|                                                                              |
| Briefer: H. Miller. Participants: C. Miller (IRO), Adensam, Matthews (NRR),  |
| Ten Eyck (NMSS), Beecher (OPA), Lohaus (OSP), Hauber (OIP), Madden (OCA),    |
| Tschiltz (EDO), Paperiello (DEDE), Boyce, Olencz (Dicus), Sharkey            |
| (McGaffigan), Castleman (Diaz), Doane (Merrifield), Rosano, Warren (IAT),    |
| Screnci (R1PAO).                                                             |
|                                                                              |
| * * * UPDATE AT 1134 ON 10/28/99 FROM JOHN HUNTER TAKEN BY STRANSKY * * *    |
|                                                                              |
| The licensee terminated the Unusual Event at 1124 EDT. Searches of the plant |
| protected area were completed without the discovery of any suspicious        |
| devices. In addition, the threat, initially determined to be credible, has   |
| been determined not to be credible. The NRC resident inspector has been      |
| informed of this update by the licensee. Notified R1DO (Lew), NRR EO         |
| (Lyons), FEMA (Sullivan).                                                    |
|                                                                              |
| ******************** UPDATE AT 1712 ON 01/13/99 BY LEIGH TROCINE             |
| ********************                                                         |
|                                                                              |
| This event notification is being updated to document the NRC's response to   |
| this event.  According to the NRC HOO Log and a time-line generated from     |
| recordings of the event, the NRC entered the Monitoring Phase of Normal Mode |
| at 0454 EDT on 10/28/99, and the Monitoring Phase of Normal Mode was exited  |
| at 0955 EDT on the same day.                                                 |
|                                                                              |
| HOO NOTE:  The bomb threat was made at approximately 0243 EDT, and the       |
| Unusual Event was declared at                                                |
| 0335 EDT.                                                                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36547       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 12/29/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 17:10[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/29/1999|
+------------------------------------------------+EVENT TIME:        15:50[CST]|
| NRC NOTIFIED BY:  ROBERT WALTERS               |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 1-HOUR SECURITY REPORT INVOLVING HISTORICAL ACCESS AUTHORIZATION PROGRAM     |
| VIOLATION                                                                    |
|                                                                              |
| "During performance of a Plant Evaluation Checklist (PEC OB 99-1157) on the  |
| NRC Performance Indicator for [the] Physical Protection Area, a historical   |
| error was discovered pertaining [to] access authorization.  It was           |
| discovered that unescorted access was authorized to an individual from       |
| 11/10/95 to 01/16/96.  However, on 01/11/96, information was received that,  |
| had it been properly investigated, would have caused denial of unescorted    |
| access at that time.                                                         |
|                                                                              |
| "This event is reportable as a 1-hour report pursuant to 10 CFR 73.71 as an  |
| Access Authorization (AA) program violation as stated in an NRC letter from  |
| LeMoine J. Cunningham, Chief Safeguards Branch, USNRC to the NRC Regions     |
| chief, dated 05/19/95.  In the letter, Mr. Cunningham states that events     |
| involving AA program failure are reportable and a 30-day written report      |
| required."                                                                   |
|                                                                              |
| The licensee plans to inform the NRC resident inspector.                     |
|                                                                              |
| * * * RETRACTION ON 01/13/00 AT 1022ET FROM BOB WALTER TAKEN BY MACKINNON *  |
| * *                                                                          |
|                                                                              |
| Wolf Creek Nuclear Operating Corporation has further reviewed this event and |
| has determined in the information used to develop on 01/11/96 did not        |
| provide a preponderance of evidence to require access screening to further   |
| investigate the individual.  Investigation conducted by access screening     |
| identified that the Wolf Creek Nuclear Operating program for access          |
| screening met the guidance of NUMARC 91-03 and that a program failure did    |
| not occur as a result of this event.  Because a program failure did not      |
| occur based upon the reportability requirements as clarified by the 05/19/95 |
| Cunningham letter, this event is no longer considered to be a 1-hour         |
| reporting event.  Therefore, this event notification is being retracted.     |
|                                                                              |
| The NRC resident inspector was notified of this event retraction by the      |
| licensee.  The NRC operations officer notified the R4DO (Jeff Shackelford).  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|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:  01/13/2000|
|  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 (HPCS) 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.                            |
|                                                                              |
| * * * UPDATE AT 1826 ON 01/13/00 FROM MARK FELTNER TO JOLLIFFE * * *         |
|                                                                              |
| Following the identification of the above condition, licensee actions were   |
| taken to investigate the reported deficiency.  A loop calibration was        |
| performed on the HPCS pump suction transmitter with no abnormal conditions   |
| identified.  The HPCS pump was run in a variety of configurations including  |
| the configuration that produced the original event, and all the data         |
| obtained was satisfactory.  During each of these runs no abnormal noise,     |
| vibrations or pump characteristics were noted.                               |
|                                                                              |
| Based on the observed condition and the additional data obtained, a          |
| determination was made that the pump did not experience cavitation           |
| conditions for more than a short period of time (5 to 8 seconds) if at all.  |
| This, coupled with information obtained from the pump vendor, the subsequent |
| successful performance of multiple pump runs, successful calibration of the  |
| suction pressure transmitter, and the lack of any abnormal noise or          |
| vibration; provides assurance that the HPCS pump is capable of performing    |
| its intended safety function.                                                |
|                                                                              |
| Based on this information, the licensee determined that this condition is    |
| not reportable to the NRC and desires to retract this report.                |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC Operations |
| Officer notified the R4DO Jeff Shackelford.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36585       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 02:55[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/13/2000|
+------------------------------------------------+EVENT TIME:        00:59[CST]|
| NRC NOTIFIED BY:  STEWART DRESSER              |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|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 Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SWITCHYARD FAULT RESULTED IN MAIN GENERATOR TRIP/TURBINE TRIP/REACTOR TRIP.  |
|                                                                              |
| At 0059CT, a Reactor Trip occurred on Unit 2.  A fault in the switchyard     |
| resulted in a Main Generator Trip which caused a Turbine Trip/Reactor Trip.  |
| All rods fully inserted into the core.  All other systems responded per      |
| design with the following exceptions:                                        |
|                                                                              |
| 1).   A Unit 1/Unit 2 Containment Ventilation Actuation occurred (caused by  |
| electrical spike in the switchyard).  This is not an Engineered Safety       |
| feature (ESF) Actuation because all the Containment Ventilation Isolation    |
| valves were already closed.                                                  |
|                                                                              |
| 2).  A Fuel Handling Building Ventilation ESF Actuation occurred (caused by  |
| the electrical spike in the switchyard).                                     |
|                                                                              |
| 3).  An 'A'-Train Main Control Room Makeup Air Filter Unit ESF Actuation     |
| occurred (caused by the electrical spike in the switchyard).                 |
|                                                                              |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are   |
| fully operable if needed.  At this time, the Motor-Driven Auxiliary          |
| Feedwater Pump is maintaining proper Steam Generator Water Levels with       |
| T(ave) being maintained at a no load temperature of 557F.                   |
|                                                                              |
| The switchyard fault is being investigated.                                  |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36586       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [1] [2] []                STATE:  SC |NOTIFICATION TIME: 04:21[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/13/2000|
+------------------------------------------------+EVENT TIME:        03:26[EST]|
| NRC NOTIFIED BY:  JIM BURGESS                  |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ENTERED TECHNICAL SPECIFICATION 3.0.3 FOR 17 MINUTES DUE TO LOW DIFFERENTIAL |
| PRESSURE BETWEEN THE CONTROL ROOM AND THE AUXILIARY BUILDING.                |
|                                                                              |
| A LOW CONTROL ROOM VENTILATION SYSTEM DIFFERENTIAL PRESSURE WAS DISCOVERED   |
| WHILE A CONTROL ROOM VENTILATION SYSTEM AND AUXILIARY BUILDING VENTILATION   |
| SYSTEM COMPENSATORY ACTION WAS IN EFFECT DUE TO AUXILIARY BUILDING           |
| VENTILATION SYSTEM WORK.  THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 |
| AT 0326ET.  AT 0333ET, THE LICENSEE SECURED THE '2A' AUXILIARY BUILDING      |
| VENTILATION FILTER EXHAUST FAN.  TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AT |
| 0343ET AFTER CONTROL ROOM DIFFERENTIAL PRESSURE WAS VERIFIED ABOVE THE       |
| MINIMUM LIMIT.                                                               |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36587       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 09:39[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/12/2000|
+------------------------------------------------+EVENT TIME:        17:49[EST]|
| NRC NOTIFIED BY:  D.  LATZ/ WILSON             |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |CHARLES MILLER       IRO     |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT INVOLVING A LICENSED EMPLOYEE                        |
|                                                                              |
| A licensed employee was arrested offsite by the Security force for           |
| possession of a controlled substance. The licensed employee was released on  |
| his own recognizance.  The licensed employee notified his supervisor of his  |
| arrest, and his access to the protected area was suspended. The licensed     |
| employee took a drug test, and the results of the test have not been         |
| completed.                                                                   |
|                                                                              |
| (Refer to the HOO Log for further details.)                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36588       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 17:04[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/25/1999|
+------------------------------------------------+EVENT TIME:        15:30[EST]|
| NRC NOTIFIED BY:  STETSON                      |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT A SINGLE PASSIVE FAILURE OF THE INCLINED FUEL TRANSFER SYSTEM |
| FLAP VALVE MAY HAVE RESULTED IN A LOSS OF ECCS DURING A DESIGN BASIS LOCA    |
| (HISTORICAL EVENT)                                                           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "With the Inclined Fuel Transfer System (IFTS) flange removed at power, a    |
| single passive failure of the IFTS flap valve may have resulted in a loss of |
| Emergency Core Cooling System (ECCS) during a design basis Loss of Coolant   |
| Accident (LOCA).  This was determined during an engineering review examining |
| the effects on containment structural capability with the IFTS Blind Flange  |
| removed."                                                                    |
|                                                                              |
| "An assumed single passive failure of the IFTS flap valve would have         |
| resulted in inventory loss from the upper containment pools with the IFTS    |
| gate removed.  The postulated water inventory loss would reduce the          |
| inventory to less than required for the makeup to the suppression pool       |
| during a LOCA.  Therefore, ECCS may not have met single failure criteria     |
| during the period when the IFTS Flange was removed at power."                |
|                                                                              |
| "The IFTS flange was removed for approximately 3 days prior to the           |
| commencement of the seventh refueling outage.  Administrative controls are   |
| in place to preclude removal of the IFTS flange at power until this issue is |
| fully evaluated."                                                            |
|                                                                              |
| The licensee stated that this event was determined to be reportable          |
| approximately 10 minutes prior to the event notification.                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36589       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/13/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 17:41[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/13/2000|
+------------------------------------------------+EVENT TIME:        10:15[CST]|
| NRC NOTIFIED BY:  STEVE JOBE                   |LAST UPDATE DATE:  01/13/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     R4      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT -                                                    |
|                                                                              |
| A NON-LICENSED EMPLOYEE SUPERVISOR (PLANT EMPLOYEE) WAS DETERMINED TO BE     |
| UNDER THE INFLUENCE OF ALCOHOL DURING A FOR-CAUSE TEST.  THE SUPERVISOR'S    |
| PLANT ACCESS AUTHORIZATION HAS BEEN REVOKED.  THE LICENSEE INFORMED THE NRC  |
| RESIDENT INSPECTOR.  CALL TO THE NRC OPERATIONS OFFICER FOR ADDITIONAL       |
| DETAILS.                                                                     |
+------------------------------------------------------------------------------+