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Event Notification Report for March 24, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/23/2000 - 03/24/2000

                              ** EVENT NUMBERS **

36825  36826  36827  36828  36829  

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|Power Reactor                                    |Event Number:   36825       |
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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 03/23/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 13:11[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        03/23/2000|
+------------------------------------------------+EVENT TIME:        12:00[EST]|
| NRC NOTIFIED BY:  DENNIS CORNAX                |LAST UPDATE DATE:  03/23/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LOUIS MANNING        R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| C-3 DEFECTS DETECTED DURING EDDY CURRENT INSPECTION OF STEAM GENERATORS      |
|                                                                              |
| Indian Point 2 is conducting eddy current testing of 100% of the steam       |
| generator (SG) tubes.  With about 90% of the inspection complete, SG-21 and  |
| SG-24 tubes have defects in greater than 1% of the tubes inspected.  SG-22   |
| and SG-23 have defects in much less than 1% of the tubes inspected.  The     |
| majority of the defects are at the support plate intersections and in row 2  |
| U-bends.  There are 41 indications in SG-21, 40 at the support plate and 1   |
| in the U-bend.  There are 39 indications in SG-24, 36 at the support plate   |
| and 3 in the U-bend.  In accordance with Technical Specification 4.13, these |
| defects result in a C-3 classification.  The testing will continue until     |
| 100% of the tubes are inspected.                                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36826       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 03/23/2000|
|    UNIT:  [1] [] []                 STATE:  AL |NOTIFICATION TIME: 13:17[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/23/2000|
+------------------------------------------------+EVENT TIME:        08:30[CST]|
| NRC NOTIFIED BY:  WEST CUMBEE                  |LAST UPDATE DATE:  03/23/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THREE FUEL ASSEMBLIES DETERMINED TO BE IN WRONG POSITIONS IN THE SPENT FUEL  |
| POOL                                                                         |
|                                                                              |
| Unit 1 personnel determined that three fuel assemblies, in the Unit 1 Spent  |
| Fuel Pool (SFP), were in positions inconsistent with the Technical           |
| Specifications (TS).  Preliminary assessment indicates that the Keff limit   |
| of 0.95 (TS 3.7.15) for the SFP would have still been met.  This condition   |
| existed for ten days, since the last Unit 1 core offload.  The assemblies    |
| have been returned to the positions allowed by TS.  An investigation is in   |
| progress to  determine the cause of this event and to determine if the Keff  |
| limit was exceeded.  There will be a 30 day written report submitted.        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36827       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 03/23/2000|
|LICENSEE:  NDC                                  |NOTIFICATION TIME: 16:46[EST]|
|    CITY:  IRWINDALE                REGION:  4  |EVENT DATE:        03/21/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        06:30[PST]|
|LICENSE#:  145-19                AGREEMENT:  Y  |LAST UPDATE DATE:  03/23/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE YANDELL     R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  DONALD BUNN                  |MATT ROBERTS         DOT     |
|  HQ OPS OFFICER:  FANGIE JONES                 |JOHN WILLIAMS        DOE     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|NTRA                     TRANSPORTATION EVENT   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE/TRANSPORTATION EVENT INVOLVING A BURNED FEDERAL EXPRESS      |
| TRUCK CARRYING A GAUGE WITH A SMALL SOURCE IN IT                             |
|                                                                              |
| On 3/21/00 at about 6:30 AM in Oxnard CA, a Federal Express truck burned due |
| to an unknown cause.  It was discovered today, 3/23/00, that a thickness     |
| gauge from NDC of Irwindale, CA was on the truck.  The gauge contains a      |
| special form source of Curium-244, 100 mCi.  The source is thought to be     |
| able to survive the fire and is being sought.  Dr. Roy Parker, the Federal   |
| Express Safety Officer, is on the scene and following up on the incident.    |
|                                                                              |
| The National Response Center report number is 523952.                        |
|                                                                              |
| (Call the HOO for contact numbers)                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36828       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/23/2000|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 23:27[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/23/2000|
+------------------------------------------------+EVENT TIME:        21:40[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  03/23/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FULL REACTOR SCRAM SIGNALS GENERATED DURING TESTING WHILE REACTOR IS         |
| SHUTDOWN                                                                     |
|                                                                              |
| With Unit 2 in a refueling outage, control room operators were performing a  |
| Reactor Protection System scram discharge volume (SDV) high water level      |
| bypass switch (rod block) functional test.  During performance of the test,  |
| control room operators placed the SDV high water level bypass switch         |
| #2C71-54 in the bypass position and the reactor mode switch in the shutdown  |
| position.  This action caused the generation of a full reactor scram signal. |
| The Control Rod Drive System had already been deenergized and all control    |
| rods were already fully inserted into the reactor core.                      |
|                                                                              |
| Control room operators reset the reactor scram signal to normal and placed   |
| the bypass switch in the normal position in accordance with the test         |
| procedure.  However, the bypass switch was placed in the normal position     |
| before the SDV had time to drain down.  With the SDV water level above the   |
| high level alarm setpoint, a second full reactor scram signal was            |
| generated.                                                                   |
|                                                                              |
| The licensee restored all systems to normal and is investigating this        |
| situation, including reviewing the test procedure.                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36829       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/24/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 05:56[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/24/2000|
+------------------------------------------------+EVENT TIME:        04:45[EST]|
| NRC NOTIFIED BY:  DAVE WALSH                   |LAST UPDATE DATE:  03/24/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LOUIS MANNING        R1      |
|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                                   
+------------------------------------------------------------------------------+
| - 'C' INBOARD MAIN STEAM ISOLATION VALVE FAILED ITS LOCAL LEAK RATE TEST -   |
|                                                                              |
| During the performance of a local leak rate test of the 'C' main steam       |
| isolation valves (MSIVs) with Unit 1 in a refueling outage, the inboard MSIV |
| #HV141-F022C was unable to hold pressure.  This constitutes a failure of the |
| maximum path leak rate required by Tech Spec 3.6.1.3.                        |
|                                                                              |
| This condition constitutes a degraded condition of a principle safety        |
| barrier found while Unit 1 was shutdown.  No other adverse conditions were   |
| identified.                                                                  |
|                                                                              |
| Unit 1 remains safely shutdown and the licensee is conducting an             |
| investigation to determine the cause of the failure.                         |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
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