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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Page Last Reviewed/Updated Thursday, March 25, 2021