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
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36825 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021