Event Notification Report for January 4, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/03/2001 - 01/04/2001 ** EVENT NUMBERS ** 37642 37643 37644 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37642 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/02/2001| | UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 22:05[EST]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/02/2001| +------------------------------------------------+EVENT TIME: 15:36[EST]| | NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 01/03/2001| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JAMES NOGGLE 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 Y 6.5 Power Operation |5 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUXILIARY FEEDWATER PUMP AUTOMATIC START | | | | The plant sustained a main turbine trip on steam generator high level, cause | | under review. The turbine trip caused a main feedwater trip which caused an | | automatic start of the 21 and 23 auxiliary feedwater pumps, as designed. | | The licensee review of the event determined, later in the evening, that the | | pump starts were reportable under 10 CFR 50.72(b)(2)(ii). | | | | The licensee notified the NRC Resident Inspector. | | | | * * * UPDATED AT 1633 EST ON 01/03/2001 BY ROBERT ALLEN TO FANGIE JONES * * | | * | | | | "The following is an update to NRC event report 37642: ESF Actuations | | | | "Indian Point Unit 2 sustained inadvertent ESF component actuations | | following a main turbine trip on high steam generator level that occurred | | during preparation for admitting steam to roll the main turbine for plant | | startup. There was no reactor trip nor was one required. The main turbine | | was latched with the stop valves open and the control valves closed. Steam | | Generator level control was in manual as is normal at low reactor power | | levels. A second condensate pump was started which caused an increase in | | main feedwater pressure which caused increasing steam generator levels. | | Operator attempts to reduce flow were unsuccessful and a high steam | | generator level turbine trip signal caused the main turbine stop valves to | | close (trip) and caused the main feedwater pump to trip. This high level | | trip signal also resulted in the closing of the main feedwater pump | | discharge valves (ESF valves), the closing of the steam generator blow down | | isolation valves (ESF valves) and the starting of the motor driven Auxiliary | | Feedwater pumps (ESF) as designed." | | | | The licensee intends to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 37643 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/03/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:03[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/02/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/03/2001| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |MELVYN LEACH R3 | | DOCKET: 0707001 |PATRICIA HOLAHAN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: M.C. PITTMAN | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 24 HOUR REPORT | | | | The following is quoted from the written report: | | | | At 1700, on 1/2/01 The Plant Shift Superintendent (PSS) was notified that | | the mass of U-235 was incorrectly copied from a Request for Waste | | Classification (RWC) onto the Waste Consolidation Container Log Sheet and | | incorrectly independently verified in violation of NCSA.WMO.004. Independent | | verification of the consolidation drum mass is used to ensure the total mass | | dose not exceed the 120 gram U-235 limit. The particular drum in question | | contains less than 15 grams of U-235. [This event actually occurred on | | 6/21/2000 and was found during a normal review of records on 01/02/2001] | | | | The NRC resident inspector has been notified of this event. | | | | PGDP Problem Report No. ATRC-01-0024; PGDP event Report No, PAD-2001-001 | | Event Worksheet | | Responsible Division: Production Support | | | | SAFETY SIGNIFICANCE OF EVENTS: Even though less than 15 grams of U-235 was | | involved in this incident, independent verification was not properly | | performed. This type of administrative control is used throughout the PGDP | | NCS program. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW | | CRITICALITY COULD OCCUR: In order for a criticality to be possible, | | multiple drums would have to be incorrectly consolidated and the resulting | | mass contained within the drum would need to exceed 1500 grams of U-235 at | | an enrichment of 5.5%. (This all was generated onsite and has an enrichment | | of less than 2.1 %.) | | | | CONTROLLED PARAMETERS (MASS, MODERATION GEOMETRY CONCENTRATION ETC): Double | | contingency for this scenario Is established by implementing two independent | | controls on mass | | | | ESTIMATED AMOUNT, ENRICHMENT FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE CRITICAL MASS): Less than 15 grams of U~235 at an | | enrichment of less than 2.1%. | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency is | | based on correctly calculating the cumulative U-235 mass in the | | consolidation drum to ensure the 120 gram limit is not exceeded. The actual | | mass was incorrectly copied from the RWC onto the consolidation log sheet, | | making it impossible to correctly calculate the consolidated mass. | | Therefore, the control was violated and the first leg of double contingency | | was lost. | | | | The second leg of double contingency is an administrative control to | | independently verify that the mass was copied correctly and the cumulative | | mass total is correct. The independent verification did not identify that | | the incorrect mass was copied. This control was violated and this leg of | | double contingency was not maintained. | | | | Since double contingency is based on two controls on mass, double | | contingency was not maintained. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: | | The area was immediately roped off and posted to control access and prevent | | the movement of fissile/potentially fissile material within the area. The | | actual mess of U-235 in the consolidation drum was verified to be less than | | 15 grams which reestablished control. The waste consolidation container log | | sheet was corrected and independently verified prior to removing the ropes | | and postings. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37644 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 01/03/2001| | UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:27[EST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/03/2001| +------------------------------------------------+EVENT TIME: 15:30[CST]| | NRC NOTIFIED BY: JAMES ODOM |LAST UPDATE DATE: 01/03/2001| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MIKE ERNSTES R2 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PHYSICAL SECURITY REPORT - 1 HOUR | | | | The licensee discovered a potential compromise of classified safeguards | | information and took immediate compensatory measures. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021