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Event Notification Report for April 30, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/27/2001 - 04/30/2001

                              ** EVENT NUMBERS **

37948  37949  37950  37951  37952  37953  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37948       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 04/27/2001|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 17:13[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        04/27/2001|
+------------------------------------------------+EVENT TIME:        14:51[CDT]|
| NRC NOTIFIED BY:  MIKE MCDONALD                |LAST UPDATE DATE:  04/27/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM                                                                |
|                                                                              |
| UNIT 3 scrammed on low reactor water level (+8") due to flow and power       |
| oscillations from 3B reactor recirculation pump.   The 3B recirculation      |
| motor generator set could not be tripped from the main control room and was  |
| tripped locally.   All rods fully inserted during the scram.  The unit is    |
| currently stable in mode 3.  There were no ECCS injections nor did any SRVs  |
| lift.                                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37949       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MONTANA DEPT OF TRANSPORTATION       |NOTIFICATION DATE: 04/27/2001|
|LICENSEE:  MONTANA DEPT OF TRANSPORTATION       |NOTIFICATION TIME: 22:50[EDT]|
|    CITY:  PLENTYWOOD               REGION:  4  |EVENT DATE:        04/27/2001|
|  COUNTY:                            STATE:  MT |EVENT TIME:        12:00[MDT]|
|LICENSE#:  25-11498-01           AGREEMENT:  N  |LAST UPDATE DATE:  04/27/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BILL JONES           R4      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  REX HOY                      |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED TROXLER GAUGE                                                        |
|                                                                              |
| A Troxler moisture/density gauge model 3440 was run over on a construction   |
| site.  The gauge contains 8 mCi of Cs-137 and 40 mCi of Am-241.  The serial  |
| number of the gauge is 20993.  The gauge was not seriously damaged.  The     |
| gauge was surveyed for contaminated and none was found.  The gauge has been  |
| removed from the job site and placed in storage pending further action.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37950       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 04/28/2001|
|    UNIT:  [] [2] []                 STATE:  SC |NOTIFICATION TIME: 21:10[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        04/28/2001|
+------------------------------------------------+EVENT TIME:        16:00[EDT]|
| NRC NOTIFIED BY:  JAMES WEAST                  |LAST UPDATE DATE:  04/28/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION - BORON RESIDUE ON REACTOR VESSEL HEAD PENETRATIONS     |
|                                                                              |
| Preliminary reactor head visual inspection indicates a small amount of boron |
| residue surrounding four control rod drive mechanism head penetrations.      |
| These indications are similar to those previously reported for unit one and  |
| unit three.  Additional inspection will be performed to determine the cause  |
| of identified boron accumulation.                                            |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37951       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 04/29/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 03:18[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/29/2001|
+------------------------------------------------+EVENT TIME:        00:50[EDT]|
| NRC NOTIFIED BY:  ROBERT KIDDER                |LAST UPDATE DATE:  04/29/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       16       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL SCRAM DUE TO DEGRADING VACUUM CONDITIONS                              |
|                                                                              |
| The licensee had reduced power to 16% and removed the main generator from    |
| service due to a stator water leak on the generator exciter causing a        |
| ground.  After the main generator was off line vacuum started deteriorating  |
| and the reactor was manually scrammed.  All rods fully inserted and all      |
| systems functioned normally.  The plant is presently using the reactor core  |
| isolation cooling (RCIC) system for makeup and the safety relief valves to   |
| the suppression pool for decay heat removal.                                 |
|                                                                              |
| The cause of the deteriorating vacuum condition is under investigation.      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 0526 EDT ON 4/29/01 BY TOM VEITCH TO FANGIE JONES * * *      |
|                                                                              |
| The plant is using RCIC for pressure control and the motor driven feedpump   |
| for makeup to the reactor coolant system.  Also, at 0116 EDT there was an    |
| automatic main steam valve isolation due to the deteriorating vacuum         |
| condition, an expected action.  This is reportable under 10 CFR              |
| 50.72(b)(3)(iv)(B) as an 8 hour report.                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R3DO (Thomas Kozak)   |
| was notified.                                                                |
|                                                                              |
| * * * UPDATE AT 1641 ON 4/29/01 BY TODD HENDERSON TO DOUG WEAVER * * *       |
|                                                                              |
| At approximately 0215 on 04/29/2001, the Main Steam Isolation Valves closed  |
| automatically as a result of the continued loss of vacuum. In a 0530 update  |
| to the original notification, this isolation was reported as a specified     |
| system actuation in accordance with 10 CFR 50.72 (b)(3)(iv)(A).  In that     |
| update, the time of the actuation was originally reported as 0116 on         |
| 04/29/2001.  At approximately the same time, Reactor Core Isolation Cooling  |
| (RCIC) was started to assist with pressure control.  At 0227, main condenser |
| vacuum was broken.  At 0247, a Safety Relief Valve (SRV) was opened and      |
| closed to control pressure, with the motor driven feed pump supplying        |
| feedwater.                                                                   |
|                                                                              |
| Approximately 2 minutes after the first SRV was cycled, a High Pressure Core |
| Spray (HPCS) RPV Level 2 (130" above the top of active fuel) initiation      |
| signal was received which started the HPCS pump and Division 3 emergency     |
| diesel generator.  No injection to the RPV occurred (or should have          |
| occurred) because reactor level was above the level where injection was      |
| required (Level 8  219" above the top of active fuel).  A Division 2 Balance |
| of Plant isolation signal and Redundant Reactivity Control System Level 2    |
| also occurred at this time (with expected plant response including the       |
| tripping of both Recirculation pumps).  The source of this signal has not    |
| yet been determined.                                                         |
|                                                                              |
| At approximately 0430, a Reactor Pressure High/Drain Temperature Low alarm   |
| was received, indicating thermal stratification in the reactor pressure      |
| vessel due to the loss of reactor recirculation. This originally delayed     |
| placing shutdown cooling in operation, but the condition has been cleared    |
| allowing progress toward initiating shutdown cooling.                        |
|                                                                              |
| The plant is currently in mode 3, with reactor level and pressure being      |
| maintained with periodic cycling of Safety Relief Valves and operation of    |
| RCIC. Residual heat removal (RHR) train 'B'  is being used for suppression   |
| pool cooling.  Actions are in progress to place RHR train 'A' in shutdown    |
| cooling, and bring the plant to Mode 4.                                      |
|                                                                              |
| The Senior Resident Inspector has been informed of the event.  The           |
| operations center notified the R3DO (Kozak).                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37952       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 04/29/2001|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 12:19[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        04/29/2001|
+------------------------------------------------+EVENT TIME:        11:28[EDT]|
| NRC NOTIFIED BY:  JOSEPH FRANKS                |LAST UPDATE DATE:  04/29/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID SILK           R1      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       97       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TURBINE TRIP - REACTOR TRIP                                                  |
|                                                                              |
| The loss of a circulating water pumped led to a turbine trip and reactor     |
| trip.  All rods inserted after the trip and the plant is stable in mode 3.   |
| Reactor coolant pumps are running and the steam generators are being fed     |
| with the mainfeed system.  The main condenser is available for decay heat    |
| removal.  One steam generator safety valve may have lifted during the        |
| transient, but is closed now.                                                |
|                                                                              |
| The cause of the circulating water pump trip is unknown.                     |
|                                                                              |
| The licensee informed the NRC resident inspector as well as State and local  |
| governments.                                                                 |
|                                                                              |
|                                                                              |
| * * * UPDATE AT 1715 ON 4/29/01 BY FRANKS RECEIVED BY WEAVER * * *           |
|                                                                              |
| This update corrects the time of the event from 1151 to 1128.  There was     |
| also a specified system actuation after the trip.  Two auxiliary feedwater   |
| pumps started after the trip on low steam generator level.   Once level was  |
| restored the pumps were secured.  The licensee notified the NRC resident     |
| inspector.  The operations center notified R1DO (Silk).                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37953       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 04/30/2001|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 02:24[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/29/2001|
+------------------------------------------------+EVENT TIME:        22:50[CDT]|
| NRC NOTIFIED BY:  DAVE HANKS                   |LAST UPDATE DATE:  04/30/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|*COM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EXPECTED LOSS OF SPDS FOR GREATER THAN 8 HOURS                               |
|                                                                              |
| Planned maintenance removed safety parameters display system (SPDS) from     |
| service for greater than 8 hours.  This requires a notification per 10 CFR   |
| 50.72(b)(3)(xiii) for loss of assessment capabilities.                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+