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Event Notification Report for May 9, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/08/2000 - 05/09/2000

                              ** EVENT NUMBERS **

36953  36981  36982  36983  36984  36985  36986  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36953       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 05/02/2000|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 10:59[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        05/02/2000|
+------------------------------------------------+EVENT TIME:        07:00[CDT]|
| NRC NOTIFIED BY:  TOM WEBB                     |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEFECTIVE STEAM GENERATOR TUBES                                              |
|                                                                              |
| Analysis of "B" steam generator eddy current results determined that more    |
| than 1% of the Westinghouse HEJ sleeve laser weld repaired tubes were        |
| classified as defective placing the "B" steam generator in the C-3           |
| classification per the Kewaunee Technical Specifications.   Two tubes of 59  |
| inspected contained indications in the weld repaired region.   There are 288 |
| total tubes in this population.   The licensee plans to increase the         |
| population size to 100%.                                                     |
|                                                                              |
| The NRC Resident inspector has been notified.                                |
|                                                                              |
|                                                                              |
| * * * UPDATE  ON 05/09/00 AT 1153ET BY TOM WEBB TAKEN BY MACKINNON * * *     |
|                                                                              |
| Analysis of "A" steam generator eddy current results determined that more    |
| than 1% of the tubes inspected in the hot leg tube sheet crevice region are  |
| classified as defective,  placing steam generator "A" in the C3 category per |
| Kewaunee Nuclear Power Plant Technical Specification.  Fifteen tubes out of  |
| 833 inspected were characterized as defective.                               |
|                                                                              |
| No scope expansion is necessary as 100% of the tubes for the hot leg         |
| tubesheet crevice region have been inspected.                                |
|                                                                              |
| Corrective Action:                                                           |
|                                                                              |
| 1. Plug or repair defective tubes prior to returning to operation.           |
| 2. Ensure plugging rate does not result in an unanalyzed condition.          |
|                                                                              |
| NRC R3DO (Brent Clayton) notified.                                           |
|                                                                              |
| The NRC Resident Inspector was notified of this update by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36981       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 00:44[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        00:15[EDT]|
| NRC NOTIFIED BY:  STEVE MYERS                  |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DIESEL GENERATOR STARTED DURING TESTING                                      |
|                                                                              |
| The 'A' emergency diesel generator (EDG ) automatically started due to a bus |
| undervoltage signal that was inadvertently caused when a procedural step was |
| misinterpreted. The EDG was secured. The licensee has informed the NRC       |
| resident inspector of this event.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36982       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 01:37[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/07/2000|
+------------------------------------------------+EVENT TIME:        22:43[EDT]|
| NRC NOTIFIED BY:  NICK CONICELLA               |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP ISOLATION DUE TO INADVERTENT STANDBY LIQUID CONTROL    |
| SIGNAL                                                                       |
|                                                                              |
| "On 5/7/00 at 2243 hours, a Reactor Water Cleanup System (RWCU) isolation    |
| occurred due to an inadvertent Standby Liquid Control System (SLC)           |
| initiation. At the time of the event, Hope Creek was in Operational          |
| Condition 5, Refueling, with core reload activities recently initiated and   |
| with all control rods fully inserted. SLC was not required to be operable    |
| and was removed from service (injection line check valves were closed) when  |
| the SLC initiation signal occurred. No sodium pentaborate was injected into  |
| the Reactor Coolant System. Preliminary investigation into the event         |
| determined that the SLC initiation signal resulted from activities           |
| supporting required surveillance testing of SLC along with surveillances of  |
| the Redundant Reactivity Control System (RRCS). The RRCS provides automatic  |
| SLC initiation. Although the RWCU isolation instrumentation was also not     |
| required to be operable at the time of the event, it was not removed from    |
| service. The RWCU isolation due to a SLC initiation signal is an ESF         |
| actuation. Both SLC pumps actuated as designed in response to the initiation |
| signal, however, a crack was observed in a weld in the 'A' SLC injection     |
| line when the SLC pump was removed from service. Event investigation is      |
| continuing and repairs to SLC are being initiated. The RWCU isolation signal |
| was reset and the RWCU was placed back in service. Core reload activities    |
| are continuing."                                                             |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36983       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 05:25[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        03:56[EDT]|
| NRC NOTIFIED BY:  RANDY HAISLET                |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POST-ACCIDENT SAMPLING SYSTEM ISOLATION DURING TAGOUT                        |
|                                                                              |
| While performing a tagout on the 'A' train of the post-accident sampling     |
| system (PASS) H2/O2 sampling system, solenoid isolation valve SV-5065-20B,   |
| which is a 'B' train valve, closed unexpectedly. The licensee restored the   |
| 'A' train of PASS H2/O2 monitoring to service and closed the redundant       |
| solenoid isolation valve in the 'B' train. The licensee declared valve       |
| SV-5065-20B inoperable.                                                      |
|                                                                              |
| After review of system electrical diagrams, the licensee determined that the |
| closure of valve SV-5065-20B was appropriate, although its closure was not   |
| anticipated in the tagout procedure. The NRC resident inspector has been     |
| informed of this event by the licensee.                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36984       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 05/08/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:22[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/05/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        21:30[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/08/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |BRENT CLAYTON        R3      |
|  DOCKET:  0707001                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILURE                                                     |
|                                                                              |
| At 2130 CDT on 5/05/2000, the C-337 Unit 3 Cell 2 Freezer/Sublimer A-valve   |
| failed to open while in TSR mode F/S 3 which requires operability of the     |
| A-valve in order for the valve to open if required to do so upon actuation   |
| of the Freezer/Sublimer High-High Weight Trip System.   An operator was      |
| attempting to place the Freezer/Sublimer into mode F/S 2 which does not      |
| require operability of the High-High Weight Trip System.  The                |
| Freezer/Sublimer was unable to enter Mode F/S 2 due to inability to open     |
| A-valve because of mechanical failure.  Actuation of High- High Weight Trip  |
| system did not occur.  However, had it been required to do so while in mode  |
| F/S 3, there is potential that the A-valve would not have opened as required |
| if actuation of system occurred.  Upon discovery of valve failure,           |
| Freezer/Sublimer was placed in mode F/S 4 which does not require operability |
| of the High-High Weight Trip system.                                         |
|                                                                              |
| The valve failure was caused by a failure of the motor operator in this six  |
| inch valve.                                                                  |
|                                                                              |
| The NRC Senior Resident Inspector has been notified of this event.  See      |
| related event 36985.                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36985       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 05/08/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:22[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/05/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        21:30[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/08/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |BRENT CLAYTON        R3      |
|  DOCKET:  0707001                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF A SAFETY SYSTEM                                                   |
|                                                                              |
|                                                                              |
| At 2130 CDT on 5/05/2000, the C-337 Unit 3 Cell 8 Freezer/Sublimer A-valve   |
| failed to open while in TSR mode F/S 3 which requires operability of the     |
| A-valve in order for the valve to open if required to do so upon actuation   |
| of the Freezer/Sublimer High-High Weight Trip System.  An operator was       |
| attempting to place the Freezer/Sublimer into mode F/S 2 which does not      |
| require operability of the High-High Weight Trip System.  The                |
| Freezer/Sublimer was unable to enter Mode F/S 2 due to inability to open     |
| A-valve because of mechanical failure.  Actuation of High-High Weight Trip   |
| system did not occur.  However, had it been required to do so while in mode  |
| F/S 3, there is potential that the A-valve would not have opened as required |
| if actuation of system occurred.  Upon discovery of valve failure,           |
| Freezer/Sublimer was placed in mode F/S 4 which does not require operability |
| of the High-High Weight Trip system.                                         |
|                                                                              |
| The valve failure was caused by a failure of limit switch on the valve.      |
|                                                                              |
| The NRC Senior Resident Inspector has been notified of this event.  See      |
| related event  36984.                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36986       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 20:56[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        20:25[EDT]|
| NRC NOTIFIED BY:  JOSEPH GIAR                  |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - FOULING OF THE REACTOR BUILDING CLOSED COOLING WATER  |
| HEAT EXCHANGER (RBCCW HX).                                                   |
|                                                                              |
| Surveillance testing has identified fouling of the Salt Service Water (SSW)  |
| side of the RBCCW HX.  The extent of the fouling on one of the two heat      |
| exchangers would prevent design basis containment heat removal post-accident |
| at maximum design basis ultimate heat sink (UHS) temperature (75F).         |
| Engineering evaluation has determined that design basis heat removal can be  |
| achieved with UHS temperature less than 70F.  Periodic evaluation will be   |
| performed to ensure that additional fouling has not further degraded the     |
| heat exchangers heat transfer capability.                                    |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
+------------------------------------------------------------------------------+