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Event Notification Report for September 29, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/28/1999 - 09/29/1999

                              ** EVENT NUMBERS **

36171  36233  36234  36235  36236  36237  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36171       |
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| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 09/16/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 04:30[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/16/1999|
+------------------------------------------------+EVENT TIME:        01:15[EDT]|
| NRC NOTIFIED BY:  DOUG AMTSFIELD               |LAST UPDATE DATE:  09/28/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| - Secondary containment integrity lost due to a hatch cover being removed    |
| during maintenance activities -                                              |
|                                                                              |
| At 0115 on 09/16/99, Limerick Generating Station Unit 2 experienced a loss   |
| of secondary containment integrity.  At the time of the event, the Standby   |
| Gas Treatment (SBGT) System was in service.  The Reactor Enclosure HVAC      |
| System was not in service due to maintenance activities. The SBGT System was |
| unable to maintain reactor enclosure pressure greater than 0.25 inches of    |
| vacuum water gauge per technical specifications due to a hatch cover being   |
| removed for maintenance inspection activities.  This event could have        |
| prevented the fulfillment of the safety function of structures or systems    |
| that are needed to control the release of radioactive materials or mitigate  |
| the consequences of an accident.  The hatch cover was reinstalled properly   |
| by 0126, and the SBGT System was able to draw a vacuum on the reactor        |
| enclosure area greater than 0.25 inches of vacuum water gauge.               |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTION AT 0828 ON 09/28/1999 FROM GAMBLE TAKEN BY STRANSKY * * *   |
|                                                                              |
| "This is a retraction of a notification made on 09/16/99 at 0434 hours,      |
| (event #36171). This event was reported as a loss of safety function under   |
| requirement 10CFR50.72(b)(2)(iii)(D).                                        |
|                                                                              |
| "Unit 2 Reactor Enclosure HVAC was secured to perform an internal ductwork   |
| inspection. SGTS was in service maintaining negative pressure in the Reactor |
| Enclosure. An inspection hatch located outside of secondary containment was  |
| removed to perform the internal inspection. This created an unplanned breach |
| of secondary containment. Unit 2 Reactor Enclosure pressure increased but    |
| remained negative. The hatch was replaced, and integrity was restored within |
| 11 minutes.                                                                  |
|                                                                              |
| "The basis for this retraction is that the safety analysis assumes drawdown  |
| of the Reactor Enclosure will take 930 seconds post accident. T.S.           |
| 4.6.5.1.1.c.1 surveillance drawdown of the Reactor Enclosure must be         |
| completed within 916 seconds (15.26 minutes). Test results indicate drawdown |
| is complete within 2.5 minutes. The sum of the hatch removal time (11        |
| minutes) plus drawdown time (2.5 minutes) totals 13.5 minutes. This is less  |
| than the 15.26 minute requirement for establishing rated negative pressure   |
| in the Reactor Enclosure. The safety function of mitigating the consequences |
| of an accident was maintained. Therefore, this event is not reportable per   |
| the guidance of NUREG-1022, Rev 1."                                          |
|                                                                              |
| The NRC resident inspector has been informed of this retraction by the       |
| licensee. The NRC operations officer notified the R1DO (Silk).               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36233       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON                 REGION:  2  |NOTIFICATION DATE: 09/28/1999|
|    UNIT:  [2] [] []                 STATE:  SC |NOTIFICATION TIME: 00:47[EDT]|
|   RXTYPE: [2] W-3-LP                           |EVENT DATE:        09/27/1999|
+------------------------------------------------+EVENT TIME:        22:33[EDT]|
| NRC NOTIFIED BY:  DON KNIGHT                   |LAST UPDATE DATE:  09/28/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NORMAL POWER SUPPLY TO EMERGENCY  ELECTRICAL BUS LOST DUE TO PERSONNEL       |
| ERROR                                                                        |
|                                                                              |
| Emergency bus E2 was temporarily deenergized after a plant worker bumped 4kV |
| breaker 5215, the normal supply breaker to the bus, causing it to trip. The  |
| B emergency diesel generator (EDG) automatically started due to an           |
| undervoltage condition on bus E2 and loaded to the bus, restoring power. The |
| licensee reported that the operating residual heat removal (RHR) pump        |
| stopped running due to the loss of power to bus E2, but operators manually   |
| started the standby pump and restored shutdown cooling within 2 minutes.     |
| Reactor coolant system temperature did not increase appreciably during the   |
| alignment of the standby RHR pump.                                           |
|                                                                              |
| The EDG continues to supply power to bus E2 while the licensee makes         |
| preparations to transfer back to the normal power supply. The NRC resident   |
| inspector has been informed of this event by the licensee.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36234       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 09/28/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 08:34[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        09/28/1999|
+------------------------------------------------+EVENT TIME:        07:30[EST]|
| NRC NOTIFIED BY:  BRIAN ROKES                  |LAST UPDATE DATE:  09/28/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID SILK           R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO RAW SEWAGE RELEASE TO HUDSON RIVER               |
|                                                                              |
| The licensee notified the New York Department of Environmental Conservation  |
| (spill report 9907789) regarding the release of less than ten gallons of     |
| sewage to the Hudson River. At approximately 2043 on 9/27/1999, sewage was   |
| spilled from the warehouse sewage holding pit to a storm drain, which        |
| discharges to the Hudson River. Plant personnel secured the spill source,    |
| diked the drain, and cleaned up the residue. The NRC resident inspector has  |
| been informed of this event by the licensee.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36235       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 09/28/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 12:09[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        09/28/1999|
+------------------------------------------------+EVENT TIME:        09:09[CST]|
| NRC NOTIFIED BY:  RODNEY WHITLEY               |LAST UPDATE DATE:  09/28/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SUPPRESSION POOL CLEANUP ISOLATED DURING LEVEL INSTRUMENTATION CALIBRATION.  |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "While performing a scheduled calibration of Containment Spent Fuel Pool     |
| Level Transmitter, SFC-LT11B, a low level isolation signal was actuated,     |
| which resulted in the [Division] II Suppression Pool Cleanup (SPC) isolation |
| valve, RHS-AOV62, isolating.  The SPC system responded as designed.          |
| Abnormal Operating Procedure, AOP-0003, Automatic Isolations, was entered,   |
| and the SPC system was secured per the System Operating Procedure (SOP).     |
| Calibration on the level transmitter was secured.  The work instructions and |
| referenced calibration data did not include any note or potential isolation  |
| of the SPC system.  As written, the work instructions only referenced input  |
| to a computer point, an alarm, and a control room indication.  At the time   |
| of this event, the SPC system was not aligned to the dryer pool, and thus    |
| was not causing any changes in the bulk water volume of the pool.  Operation |
| of the SPC system did not contribute to this event.  Also, the SPC system    |
| performs a non-safety function.  Thus, its isolation did not impact safe     |
| plant operation."                                                            |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36236       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/28/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 12:24[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/27/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:09[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/28/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |TONY VEGEL           R3      |
|  DOCKET:  0707002                              |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOE HALCOMB                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALID ACTUATION OF A 'Q' SAFETY SYSTEM (24-hour report)                      |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "On 09/27/99 at 1609 hours, the X-333 Cascade Building operation personnel   |
| received three cascade automatic data processing (CADP) smoke head alarm     |
| actuations.  These smoke heads were monitoring operating cell 33-2-4 which   |
| was promptly taken off stream and shut down.  Emergency response personnel   |
| monitored the area, and all air sample results for hydrogen fluoride and UF6 |
| were below detectable levels."                                               |
|                                                                              |
| "This event is reportable due to the valid actuation of a 'Q' safety         |
| system."                                                                     |
|                                                                              |
| "This event is reportable to the NRC per Safety Analysis Report (SAR)        |
| Section 6.9, Table 6.9-1.  This is a 24-hour reportable event."              |
|                                                                              |
| "There was no loss of hazardous/radioactive material or                      |
| radioactive/radiological contamination exposure as a result of this event."  |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and plan to notify  |
| the Department of Energy site representative.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36237       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 09/28/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 17:43[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        09/18/1999|
+------------------------------------------------+EVENT TIME:        08:48[EST]|
| NRC NOTIFIED BY:  GORDON FIEDLER               |LAST UPDATE DATE:  09/28/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID SILK           R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       0        Startup          |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE TO PERFORM RCIC AND HPCI RESET PRIOR TO EXCEEDING 150 PSI DURING     |
| UNIT STARTUP                                                                 |
|                                                                              |
| On 09/18/99 while the unit was in startup, reactor core isolation cooling    |
| (RCIC) and high pressure coolant injection (HPCI) reset was not performed    |
| prior to exceeding 150 psi.  The reset was performed at 167 psi at 0848, and |
| 150 psi was exceeded at 0830.  Therefore, both RCIC and HPCI were inoperable |
| for 18 minutes.                                                              |
|                                                                              |
| The licensee stated that this issue was determined to be reportable at about |
| 1730 on 09/28/99 during performance of a reportability evaluation in         |
| accordance with 10 CFR 50.73.  The unit is currently operating at 100% power |
| (steady state).                                                              |
|                                                                              |
| The licensee plans to notify the NRC resident inspector and the state        |
| (Massachusetts Civil Defense).                                               |
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