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Event Notification Report for October 13, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/12/1999 - 10/13/1999

                              ** EVENT NUMBERS **

36282  36283  36284  

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|Power Reactor                                    |Event Number:   36282       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 10/12/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 18:11[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        10/12/1999|
+------------------------------------------------+EVENT TIME:        17:00[CDT]|
| NRC NOTIFIED BY:  HEDGES                       |LAST UPDATE DATE:  10/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| PLANT LOST THEIR SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FOR APPROXIMATELY 26 |
| HOURS                                                                        |
|                                                                              |
| "On October 8, 1999, following scheduled maintenance, the plant's Nuclear    |
| Plant Information System (NPIS) experienced a series of intermittent random  |
| component and software related failures. The Safety Parameter Display System |
| (SPDS) relies on the NPIS computer to provide necessary information. These   |
| failures resulted in the SPDS being unavailable for a total of approximately |
| 26 hours since the October 8, 1999 maintenance evolution. The system has     |
| been operating without interruption since October 11 at 1758 hours.          |
|                                                                              |
| "10 CFR 50.72 requires licensees to report events that resulted in a major   |
| loss of emergency assessment capability.  NUREG-1022, Revision 1, indicates  |
| that a major loss of assessment capability would include those events that   |
| significantly impair the licensees safety assessment capability. NUREG-1022  |
| further states that the loss of SPDS for a short period of time need not be  |
| reported unless other assessment equipment is lost at the same time.         |
|                                                                              |
| "During the SPDS outages, other control room indications used in emergency   |
| response capability were available.  The licensee does not believe that this |
| out of service time resulted in a major loss of emergency assessment         |
| capability, since no other assessment equipment was lost during this period. |
| Although this event is not considered reportable under 10 CFR 50.72, this    |
| report is being provided for information, since the Emergency Response       |
| Facility Information System, which supplies the NRC Emergency Response Data  |
| System would not have been available during the SPDS outages."               |
|                                                                              |
| The Resident Inspector was notified.                                         |
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|Power Reactor                                    |Event Number:   36283       |
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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 10/12/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 23:27[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        10/12/1999|
+------------------------------------------------+EVENT TIME:        19:44[EDT]|
| NRC NOTIFIED BY:  LIZZO                        |LAST UPDATE DATE:  10/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| PLANT HAD AN INADVERTENT SAFETY INJECTION SIGNAL ACTUATION AND AN AUTO START |
| OF ONE EMERGENCY DIESEL GENERATOR.                                           |
|                                                                              |
| "At approximately 1944 hours on October 12, 1999, during thc performance of  |
| test 3PT-R003B "Safety injection Test Breaker Sequencing/Bus Stripping" a    |
| safety injection (SI) relay was inadvertently actuated.                      |
|                                                                              |
| "The technician performing the test was installing an electrical jumper in   |
| accordance with the procedure when the alligator clip used for the jumper    |
| slipped off and accidentally actuated the nearby SI relay. The relay         |
| actuated a SI sequence on the 480V bus 6A. The load stripping sequence for   |
| bus 6A was initiated and SI equipment sequenced on as expected. The          |
| associated SI equipment electrical breakers were racked into the test        |
| position for the purpose of the test, so no injection occurred. The EDG      |
| associated with bus 6A automatically started and came up to speed and        |
| voltage but did not load.                                                    |
|                                                                              |
| "The EDG was secured and equipment restored to the condition necessary to    |
| resume the test."                                                            |
|                                                                              |
| The Resident Inspector has been notified.                                    |
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|Fuel Cycle Facility                              |Event Number:   36284       |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/13/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 02:50[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/12/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        02:55[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/13/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JOHN MADERA          R3      |
|  DOCKET:  0707001                              |WILLIAM BRACH        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  J. UNDERWOOD                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24 HOUR REPORT - VALID ALARM ON PRIMARY CONDENSATE, A SAFETY SYSTEM          |
|                                                                              |
| "At 0225 on 10/12/99, the PSS office was notified that a Primary Condensate  |
| alarm was received on the C-360 position 3 autoclave Water Inventory Control |
| System (WICS). The WICS system is required to be operable while heating in   |
| mode 5 according to TSR 2.1.4.3. The autoclave was checked according to the  |
| alarm response procedure and subsequently removed from service and declared  |
| inoperable by the Plant Shift Superintendent.                                |
| Troubleshooting was initiated and is continuing in order to determine the    |
| reason for the alarm.                                                        |
|                                                                              |
| "The safety system actuation is reportable to the NRC as required by Safety  |
| Analysis Report, section 6.9, table 1, criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification."                      |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
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